ML17214A681
| ML17214A681 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/09/1984 |
| From: | Harris K FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17214A680 | List: |
| References | |
| 3100021E, NUDOCS 8402070383 | |
| Download: ML17214A681 (112) | |
Text
Page 1 of 24 e
FLORIDA POWER i LIGHT COMPANY
/
ST.
L>'0IE PLANT E-PLAN IMPLEMENTING PROCEDURE NO-3100 21E
~ /
REVISION 15 +
~(vf=
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 Approved by ewed by ci y Review Group 3E'c~~6w i~
19f D
/
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
/R15 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.
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 situation.
e 3
3 -Authority:
This procedure implements the St. Lucie Plant Radiological Emergency Plan.
- SSOSOTOSSS SSOSO~a PDR. ADQCK 05000335 F
PDR'
il 4
ST.
LUGIE PLANT E-PL Ql IMPLEMENTING PROCEDURE NO. '3100021E, REVISION 15 DUTIFS AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR r
Page 2 of 24
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.
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".
/R15 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
ST.
LUGIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO.
- 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 3 of 24 5.0 Res onsibilities:
(Continued)
~
~5.4 If the TSC is activated, the Technical Support Center Supervisor shall fillout the checklist for Notification of Significant Events (to NRC) as soon as 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.
6.0
References:
/R15 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.
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES.AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 4 of 24
- 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 ii the situation is a fire or explosion, utilize the Fire or E
losion Emer ency Checklist (Page 12).
/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 TEAMS STATE OF FLORIDA BUREAU OF EMERGENCY MANAGEMENT U NRC OPERATIONS CENTER As Appears On C ec list LOCAL SUPPORT 1
FIRE AMBULANCE, ST ~
LUCIE COUNTY -FORT PIERCE FIRE DISTRICT 2.
MEDICAL, LAWNWOOD MEDICAL CENZER OR REEF AT MT. SINAI 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
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 310002 E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 6 of 24 PLANT/RADIOLOGICAL EMERGENCY CHECKLIST Date Seq.
Class at Time of D
Declaration E
Escalation Unusual Event D
Alert D
E Site Area D
E General D
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
ST.
LUCIE PLANT E PLAN 'MPLEMENTIN P PROCEDURE NO 3100021E P
REVISION 15 DUTIES AND RESPONSI BILITIES OF THE EMERGENCY COORDINATOR Page 7 of 24 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 0-2 Mile Radius 2-5 Miles for Sectors 5-10 Miles for Sectors Miles 11.
CURRENT OUTS IDE TEMPERATURE:
fA]
12.
RELEASE RATE:
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
~C
[E]
[F]
[G]
[Hl
[Il
[J]
[Kl
[Ll F
Q 10 METERS NOBLE GASES DEFAULT
[A]
Ci/Sec MEASURED
[B]
Ci/Sec INSTRUMENT LOCATION N/A 13.
SUPPLEMENTAL PAGES USED:
A NO MESSAGE RECEIVED BY:
IODIWEE
]C]
Ci /Eee
[Dl Ci/Sec
/
/
NAME OF STATE PERSON TIME.
~
DATE
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 8 of 24 14.
WIND DIRECTION DATA STATE OF FLORIDA NOTIFICATION MESSAGE FORM SUPPLEMENTAL DATA (Page 2 of 2)
S OR DIRECTION DEGREES DIRECTION SECTORS AFFE TED A
B C
E F
H J
K M
P Q
R N
NNE NE ENE E
WNW NW NNW 349-11 12-33 34-56 57-78 79-101 102-123 124-146 147-168 169-191 192-213 214-236 237-258 259-281 282-303 304-326 327-348 S
WNW NW NNW N
NNE NE ENE E
- MNP, NPQ P QR QRA RAB AB C B CD CDE DEF EFG FGH' H J 15 'ASIC DESCRIPTION OF RELEASE CHARACTERISTICS
- 16. Estimate-of Radioactive Material Released:
NOBLE GASES Radioiodines SOURCE TERM:
TOTAL RELEASE:
SOURCE TERM:
TOTAL RELEASE:
[A]
[B]
[C]
[D]
Ci/Sec Ci Ci/Sec Ci 23 ESTIMATE OF PROJECTED OFF-SITE DOSE RATE:
Dis=ance 1
Mile (Site Boundary) 2 Miles 3
.&les 4
'&les 5'Ales 10 Miles Thyroid (mrem/hr)
[A]
[C]I~*
[I]
[K]
Whole Body (mrem/hr)
[B]
[D]
"7X
[J)
[L]
24.
SPECIAL DATA:
[Ai NO
[B]
YES MESSAGE RECEIVED BY:
NAM OF STATE PERSON)
TIME DATE
/
/
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO.
- 3100021E, REVISION 15 DUTIES. AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 9 of 24 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'.
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)
/R15
- 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
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 10 of 24 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).
(To be done by TSC if properly staffed)
IF UNUSUAL EVENT, SKIP TO STEP 18
/R15 13.
Verify from Security Team Leader that the evacuation (if ordered) has been completed and all personnel are accounted for.
l 14.
15.
Reassess corrective and protective actions.
Verify activities
- underway, reassign personnel and teams as necessary.
4f 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.
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 1i DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINAT(>R Page 11 of 24 SIGNIFICANT EVENT REPORT or NRC Noti ication Date Facility Name Caller Name Time
'lorida Power
& Li ht St. Lucie Unit (applicable Unit) 1.
Description of Event Classification of Event Reactor'ystems Status
- Pressure Flow PER or RX Level Temperature Power level ECCS Operating/Operable 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 6
Activate the Fire Brigade and other appropriate emergency teams in accordance with Fire Emergencies EPIP 3100025E via a PA announcement.
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
/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
ST.
LUCIE PLANT E-PLAN IM 'LEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 13 of 24 FIRE OR EXPLOSION EMERGENCY CHECKLIST continued STATE OF FLORIDA NOTIFICATION MESSAGE FORM NUCLEAR POWER PLANTS 1.
Time and Date of Message / Reported by 3a Accident Classification oti ication o
Unusual Event
[B] Alert C]
Site Area Emergency 2.
Site fK]
St. Lucie Unit 1
[C]- St. Lucie Unit 2
Date
- 5.
Incident Involves:
[
4.
Time and Date of Incident/Emer ency Time 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 MESSAGE RECEIVED BY:
NAME OF STATE PERSON Page[a)
/
/
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
'T.
LUCIE PLANT 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
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. '3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 15 of 24 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.
17.
If the accident involves actual or impending releases of radiation, go to the PLANT/RADIOLOGICALEMERGENCY CHECKLIST.
18.
Reassess the Emergen'cy Classification and update the Notification Message Form with Technical Support Center Supervisor (if TSC is activated).
/R15
0 I
(
e 0
~ ST.
LUCIE PLANT E-PLAN IMPLEMENTING'ROCEDURE NO. '3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 16 o!
24 MEDICAL EMERGENCY CHECKLIST TIME I. Determine:
Name of Victim Employer (if not FPL) r 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 (State "State Warning Point Tallahassee, this is St. 'Lucie
+
Warning Point will give a go-ahead)
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).
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PR< CEDURE NO.
- 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 18 of 24 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 o
Unusual Event 4
- 5~
Time and Date of Incident/Emer ency Time Incident Involves:
II Date 6.
13
'ccident Related In uries:
[A]
No
[B]
Yes
[C]
Contaminated Injury Number of Injuries ITEMS 7 THROUGH 12 INCLUSIVE ARE N/A (NOT APPLICABLE)
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.
T'* END OF MESSAGE FORM **
/R15
it I
ST.
LUCIE PLANT
'-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 19 of 24 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
'f the GENERAL EMERGENCY has been declared due 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)
No protective action is recommended between a
5 and 10 mile radius from the plant
/R15 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.
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. '3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 21 of 24 FIGURE A-1 PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT CONDITIONS MIIES 2-5 MQES 5-10 MIIES QK KZ~
SECCmZ(1)
USS IE QNBKL M)
S (Z OF PLANK (5)
YES QKMi
<yam umz) ammzmeir FA1LURE HAS aXURam m m
IS 28IMM'(~)p YES SEE RNMHZ (R
E IN +S RS)
(3)
(1)
"Potential core melt, any cause" in EPIP 3100022E, "Classification of Emergencies.
(2)
Represents greater than lOOX gas gap activity in containment.
(3)
See "Loss of Containment Integrity;" EPIP 3100022E.
'(4)
Determine whether a "Puff" type 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
- LEGEND OF ABBREVIATIONS N
o protective action recoame:
S - Sheltering recommended E Evacuation recoamended IM Downwind + 2 adgoining secto RS - Remaining sectors CR - Complete circle around plant specified distance
II
ST.
LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 22 of 24 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)
(2)
(3)
Containment failure has occurred or is imminent, and Rate of release is much greater than designed leak rate, and 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 SECTOR A
[Bl
[C]
tD]
[El
[Fl
[G]
[H]
[K]
[Ll
[M]
[N]
tP]
[Ol
[R]
DIRECTION N
NNE NE ENE E
'W WNW NW NNW DEGREES 3
-11 12 33 34 56 II 57 78 II 79 101 I I 102 123 124 - 146 147 168 169 191 II
, 192 213 I
I 214 - 236 I I 237 258 II 259 281 282 303 304 326 327 - 348 WIND TOWARD DIRECTION S
WNW NW NNW N
NNE NE ENE E
JKL KLM LMN MNP NP0 PQR 0 RA RAB ABC BCD CDE DE F EFG FGH GH'J
ST.
LUCIE PLAhT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 15 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Page 23 of 24 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 DOSE (REM)
OR (REM) 0-2 MILES i I 2-5 MILES I I 5-10 MILES
< 0.5 1.0
>I
> 0' but
< 1.0 1 ~ 0 but
> I S(CR)
(
1 '
but
< 5.0
> 2' but
< 25.0
-> I E CR)
I E(DW) + S(RS)ll E(DW) + S(RS)I
> 5.0 I
E(CR)
I l~> ~
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 actions from 0-2 miles The dose 8
2 miles affects protective actions from 2-5 miles
'I The dose 9
5 miles affects protective actions from 5-10 miles The dose 9 10 miles can be used to evaluate protective actions for greater distances.
/R15
+LEGEND OF ABBREVIATIONS N
No protective action recommended S
Sheltering recommended E
Evacuation recommended 3W
Downwind + 2 adjoining sectors RS Remaining sectors CR Complete circle around plant at specified distance
'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 DOSE (REM)
OR (REM) 0-2 MILES I I 2-5 MILES I I 5-10 MILES I
)Use 1 Mi ValueI IUse 2 Mi Value( IUse 5 Mi ValueI
< 0.5
< 1.0
>I
> 0' but 1 ~ 0 1 '
but
< 2.5 0
1 '
but
< 5.0
> 2' but
< 25.0
> 5.0
> 25.0 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 actions from 0-2 miles The dose 9
2 miles affects protective actions from 2-5 miles The dose 8 5 miles affects protective actions from 5-10 miles The dose 9 10 miles can be used to evaluate protective actions for greater distances.
N S
E DW RS CR
/R15
- LEGEND OF ABBREVIATIONS No protective action recommended Sheltering recommended Evacuation recommended Downwind +
2 adjoini.ng sectors Remaining sectors Complet'e circle around plant at specified distance
I t
FLORIDA POWER
& LIGHT COMPANY DUTIES OF THE RECOVERY MANAGER, OFF-SITE EMERGENCY ORGANIZATION PROCEDURE 1102 12/15/83 Page 1
- 1. 0 Tlt'l e:
DUTIES OF THE RECOVERY MANAGER, OFF-SITE EMERGENCY ORGANIZATION Recovery Manager:
- Manager, Nucl ear Energy Alternate:
(1) Assistant
- Manager, Nuclear Energy Altern 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
$ 1984 Emergency Planning Supervisor Approved by Energy 2.2 List of Effective Pa es Vice President, Nuclear
, 1984
~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 1 ity.
n
3.3
~Author(t FLORIDA POWER 5 LIGHT OMPANY DUTIES OF THE RECOVERY
- MANAGER, OFF-SITE EMERGENCY ORGANIZATION PROCEDURE 1102 12/15/83 Page 2
This procedure.'implements the Turkey Point Plant Radiological Emergency Plan and-the St. Lucie Plant Radiologica'mergency Plan.
4.0 Precautions 4.1 4.2 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.
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 ities 5.1.
S.2 5.3 Inform the Emergency Control Officer periodically of the on-site status and immediately of any significant changes.
A Provide support and data as necessary to the Emergency Coordinator.
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 5.5 5.6 5.7 5.8 5.9 Provide protective action recommendations to offsite authorities when the EOF is manned and operational.
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.
Assure continuity of technical and admin strative support, and materi al resources.
Request additional support as necessary.
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.)
Authorize voluntary personnel to exceed 10 CFR 20 limits for personnel
F -ORIDA POWER 5 LIGHT COMPANY D TIES OF THE RECOVERY MANAGER~
Oi F-SITE EMERGENCY ORGANIZATION PROCEDURE 1102 12/15/83 Page 3
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 11/15/83 Page 4
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
[0j TURKEY POINT UNIT 3
[Cj SITE AREA EHERGfNCY
[Ej TURKEY POINT UNIT 4
[03 GENERAL EMERGENCY 4 ~
5.
TIME AND DATE OF INCIDENT /
EMERGENCY TIME INCIDENT INVOLVES:
DATE 6.
7.
9.
10.
11.
12.
YfS
[C3 CONTAMINATED INJURY ACCIDENT RELATED INJURIES [Aj NO
[Bg NUMBER OF INJURIES SITUATION INVOLVES:
A 'O RELEASE
[Bj POTENTIAL(POSSIBLE) RELEASE
[Cj A RELEASE IS OCCURRING - EXPECTfD
[0]
A RELfASE OCCURRED, BUT STOPPED-TYPE OF RELEASE IS:
A EOOE
[B]
NON-RADIOACTIVE GASEOUS
[C1 RADIOACTIVE LIQUID
[03 PARTICULATE HATTER
[E3 NOT APPLICABLE WIND DATA:
~J l~IND DIRECTION (FROM)
[Bj WIND SPEED TCT STABILITY CHTi
'0 AE E>>
0 ACTI ETOTIOEE:
A NO RfCOHHENDATIONS AT THIS TIME NO IFY THE PUBLIC TO TAKE THE FOLLOWING DURATION OR MAGNITUDE DURATION OR MAGNITUDE DEGREES 9 10 METERS MILES PER HOUR 9 10 HETERS PROTECTIVE ACTIONS:
., No Action Shelter
~B
~C
[Ej
[F3
[H3
[Ij
[Kl F 9 10 METERS Evacuate 0-2 Mile Radius 2-5 Miles for Sectors 5-:.0 Miles for Sectors Hi 1 es CUf!RENT OUTSIDE TEMPERATURE:
[Ag RELEASE RATE:
NOBLE GASES DEFAULT
[A3 Ci/sec MEASURED [Bj Ci/sec INSTRUMENT LOCATION 0
[Gj
[Jj
[Lj IODINES
[cj
[03 Ci/sec Ci/sec Ci/sec Ci/sec N/A N/A N A page s)
SUPPLEMENTAL PAGES USED [Ag Hf.'iSSAGE RECEIVED BY:
PROCEDURE 1102 12/15/83 Page 5
STATE OF FLORIDA NOTIF ICATION MESSAGE FORM 14.
15.
N/A (Intentionally left bl ank) e MIND DIRECTION DATA Wind from
~De rees Wind toward Sectors affected
[Aj fBj NNE
[C)
NE
[D7 ENE
[Ej E
[F)
ESE I Gl SE
[Hj SSE
[Jl s
fxj SSW
[L3 SW
[M]
WSW
[N3 W
[Pj WNM
[Q]
N
[R)
NNW BAS IC DESCRIPTION 349-11 12-33 34'-56 57-78 79-101 102-123 124-146 147-168 169-191 192-213 214-236 237-258 259-281 282-303 304-326 327-348 S
WNM N
NNW N
NNE NE ENE E
ESE SE SSE OF RELEASE CHARACTERISTICS HJK JKL KLM LMN MNP NP Q
PQR QRA RAB ABC B CD COE DEF EFG FGH GHJ 16.
17.
RADIOIODINES ESTIMATE OF PROJECTEO OFFSITE DOSE RATES:
ESTIMATE OF RADIOACTIVE MATERIAL RELEASED:
NOBLE GASES SOURCE TERM'Aj TOTAL RELEASE:
[Bj SOURCE TERM:
[Cj TOTAL RELEASE:
[03 Ci/sec Ci Ci/sec Ci 18.
DISTANCE 1
mile (Site Boundary) 2 mi 1 es 3
mi 1 es 4
mi 1 es 5
mi1 es 10 miles SPECIAL DATA:
[A3 NO
[B1 THYROID (mrem/hr)
[Al
[C1
[El
[Gj
[Ij
[X]
YES WHOLE BODY (mrem/hr)
[Bj
[03 fFj
[H]
[Jj fLj MESSAGE RECEIVED BY:
l.
I 0
PROCEDURE 1102 12/15/83 CHECKLIST 2 Page 6
Action RECOVERY MANAGER
~Time Lo 1.
'Time of receipt of initial notification from ECO.
2.
Obtain Checklist 1 data (to the extent available)
A.
Initi 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 off-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 Officer, 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 12/15/83 Page 7
CHECKLIST 2 Cont'd)
Action
~Time Lo 7.
8.
9.
Assess status of assigned responsibilities for the following 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)
Update Checklist 1 data periodically and communicate t~ state and county authorities Assess need for additional off-site support from U.S.
Coast
- Guard, U.S.
Department of Energy, REEF Associates,
- 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 12, 15/83 Page 8
FIGURE 1
CON'NGL OFFICER VICE RKSIQEHT. MA%EAR EhKAQY ASSIST~ TO VICE RKSIDENT, NKNC laNCIKNC NSCNeaTION MANNER VICE RKSIOEhfl; CERATE CO444PIICATIONS MAll4QKR OF CXNLLNICATICN WCCNKRY MAl4MKR MANOR OF l4NXLAR EhCAQY ASSISTANT MANrMKR OF lWCLEA$k ENEMY VICE NKCIIKNT.
VINCKIIIIL AFFIARS
.PHCRAL IKOILLATORY IKNKIKNTLTNK NCINCIKV TKCNIICIL NINLINII CHIEF ENSlhKER, POWUI PLANTS ASSISTANT CHIEF KNOI~R, POWER PLJWTS I IN IIVNI, CICJIVIKCIINIICIL ENQIhKERINQ MAl4MKR, ELECTRICAL ENQlhCKRINQ
~ICN PROST MANMKR.
TLNKEY POINT
~ICN PAOWCT MANOR.
ST. UJCIK
~LKNNIKYM!1NITV NNCNKC
$94IOR MCLRITY COIGNIHATOR.
l4JQLEAR MM4MKR CF &CLNITY CLNITY COIXQINATCN, l4CLEAR
tl
,1 0
EHERGFNCv COORDINATOR Additional notifica-tions per Plan and procedures EXECVFIVE VICE PRESIDENT Plant Duty call Supervisor L2 I
I System Opns.
Pover Coordinator alternates or NEDO EIM ESM Staf f=-
Support CD 2
m h) O W C:
CJl Pl Q7 H 47 w Nn'rsS:
<<Verify that EC has made or is in the process of making these notifications (for Unusual Event
& Alert).
For Site brea Emergency
& General Emergency, delegate com-munications responsibilities to these agencies to RM (after the EOF is manned and operational).
Federal and State Agencies 1 Notifications made pe" Procedure 1101 2 Notifications made per Procedure 1102
~P2 use 2
Notification Flov
1l
~~
I Ib 0
PROCEDURE 1102 12/15/83 Page 10 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 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, duration of the release, and the projected offsite doses prior to making any protective action recommend ati ons.
PROCEOURE 1102 12/15/83 PROTECT I VE ACTION RECOMMENDATIONS Page 11 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 12/15/83
'age 12 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 1
LOSS OF CONTAQL QF PLANT (5)
NO 5 (CR) 5 tDW)
E (CR)
CHAM p4M4 RA% (2 (CORK DAMA ONTAI FAII LjK HAS OCQJKO OR 15 IMMI~
(2)
E (CR)
(DW) i 5 (RS) 5 (CR)
E (CA)
SEE FOOTNOTE (i)
E (CR) 5 (CA)
CONTAItACN FAILLE HA5 OCCLiKD QR IMMI E" (CA)
E (CA)
(DW)
~ 5 (RS)
K (CR)
SEE FOOTNOTE (4)
E (CA)
(DW)
~ 5 (AS)
L (I)
POTENTIAL CORE LCLT. ANY CAUSE IN EPIP S)00022K. 'CLASSIFICATION OF EL@AGENCY.
'2)
IKPfKSKNTS GREATER THAN 1002 GA5 GAP ACTIVITY IN QNTAlhLCHT.
5EE LOSS OF CQN-Al aCMt INTKRGAITY.~IP 5100022K.
(4)
DETULIINE~~ A~ TYPK RELEASE 15 IN PROGRKSS tOR IMMI~VSWG ~ CON)ITIQNS LI5TKD ON hEXT PAGE.
(IO LOSS Of CONTROL Of VITALREACTOR OPERATE AREAS TO anRuOKRS.
IATI
~ PAOTKCTIVE ACTION RECOMvChOED 5-RCLTKAING AECO4CI4)ED K~ACVATIONAECQIACl4)ED DW~IN) i 2 ADJOINING SECTORS AS~INING 5ECTORS CAMOLOLETE CIACLE AAOLPO PLANT AT SPECIFIED 015TANCE Oa.&IISS IR
e 0
PROCEDURE 1102 12/15/83 Page 13 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 tions:
(1)
(2)
(3)
Containment failure has occurred or is imminent, and Rate of rel ease i s much greater than designed leak rate, and 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."
CA]
CB]
Ccl LD]
CE]
CF]
CG]
CJ]
CK]
LL]
CM]
CN]
LP]
CQ]
CR]
N NNE NE ENE E
WNW NW NNW 349 - 11 12 - 33 34 - 56 57 - 78 79 -101 102 -123 124 -146 147 -168 169'-191 192 -213 214 -236 237 -258 259 -281 282 -303 304 -326 327 -348 WIND FROM SECTOR DIRECTION DEGREES S
WNW NW NNW N
NNE NE ENE E
ESE SE SSE HJK JKL KLM LMN MNP NP Q
PQR QRA RAB ABC B CD C DE DEF EFG FGH GH J WIND TOWARD DIRECTION SECTORS AFFECTED
PROCEDURE 1102 12/15/83 Page 14 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 CN
~ OCTO 0K
0 2 MILES UK l Ml VALlE QK 2 MI V 5 IO MILE5 UK 5 Mt VPua C I)
N x I)5 IIEET C ll)
> Il)
SJT c L5 LIT c 50 j LS WT c 2SD E IWli 5 0I5I E IWl + 5 IRSI IF TlK ORATION OF TlK FCLEA5E IS PACLKCTXD TO M <SKATER~ CN ECLIAL TO 2 54%%5 Llà A~3e
+Tlat~ ~ l MILE AFFECT5 PROTECTIVE ACTICHS FROM 0 2 MIL!5 TlC 00% ~ 2 MILE5 AFFEC;T5 PROTECTIVE ACTIONS FACULA 2-5 MILE5 Tl+ ÃÃK ~ 5 MILE5 AFFEC:T5 PROTECTIVE ACTICH5 RKM 5 10 MILES TlK OAK ~ IO MILES CAN IK VRD TO EVALUATEPROTECTIVE ACTICNS FOR CHEATER DISTANCE N - NO PROTECTIVE ACTION $KCO4lQIED 5 - SCLTRRIFC IKCOv$4ED E - EVACUATION IKCQ4l9IED DW - DOWNWlle + 2 ADJOININO SECTORS R5 lSAAINI% SECTORS CR CO4RETK CIRCLE AROIPO PLANT AT
~CIFIED DISTANCE
PROCEDURE 1102 12/15/83 Page 15 FIGURE A-3 PROTKCTIVK ACTION RECO4LKhATIONS 8ASED ON ACTQAL RELEASE (G$KATER THAN OR EQUAL TO 2 HOCH DILATION WITH OFFSITE'OSE ESTIMATES)
MSED IN TO FIGLNE A 2 TNTROIO aXr OCR N4t m4t
~ MILES 0 2 MILES
~ I Ml VALLK QK2MI V 5-10 MILE5 QK 5 MI VALLE c 14 N
> QS 0/T c IAt j IAt SIT c 25 5 (C$D
-5 Wl NiT c 54t 2 25 SlT c 2LO EeW) iSIRSI EeWliSN 5 "CCRC E EDWI i 5 N IF TtC DNIATIONtK Tt+ IKLEASE IS PAOXCTXD TO M LES5 T14AN CN E~ TO 2 tCX$5 UK A.2 iTl%~ ~
1 MILE AFFECT5 PROTECTIVE ACTICN5 UK' 2 MILE5
,TtK~ ~ 2 MILX5 AFFECTS PROTECTIVE ACTICN5 FACM ~ MILE5 TtK OAK ~ 5 MILES AFFECT5 PROTECTIVE ACTICP45 RK54 5 10 MILES TlK OCR ~ 10 MILES CAN IK URD TO EVALUATEPROTECTIVE ACTICHS FOR <SKATER DISTANCE ATI N - NO PROTECTIVE ACTION IKCOIACt4)ED r
5 SCLTERIW IKCCLC)4ED E
EVACUATION iKCOMrEM)ED DW - DOWNWI% i 2 ADJOINlt4 ACTORS R5 IKL4AINING &CTtÃ5 CR - CCL5%ETK CIRCLE AAOLJQ PLANT AT PACIFIED 0I5TANCE
PROCEDURE 1102 12/15/83 Page 16 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 offsi 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 it may change or what it may change to."
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 12/15/83 Page 17 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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Page 19 PROCEDURE 1102 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 Turkey Point Plant FIGURE B-2 Page 20 PROT'.CTIVE hCTION RECOMMENDATIONS BASED ON hCTUAL RELEASE (GREATER TYZ:: OR EOUAL TO 2
HOU'R JRATION) WITH OFFSITE DOSE ESTIMATES
. (used in preference to Figure B-1)
DISTANCE FROM PLANT/RECOMMENDATIONS~
WHOLE BODY OR THYROID DOSE DOSE (REM)
(REM) 0-2 MILES use 1 mil value 2-5 MILES use 2 mile value 5-10 MILES use 5 mlle value
< 0.5 0 5 but
< 1.O 1.0 but
- 2. 5 S (CR).
S (DW)
S (DW)
> l.o but 5.0 but
<25.0 E (CR)
E (DW) +
S (RS)
E (DW) +
S (RS)
> 5.0 I
> 25.0 l
E (CR)
E (CR)
E (DW) +
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 The dose 8 2 miles affects protective actions from 2-5 miles The dose 9 5 m'les affects protective actions from 5-10 miles The dose 8 10 miles can be used to evaluate protective action~
fcr greater distances
~
N-S-
E-DW-RS-CR-h No protective action recommended Shelte~inn recomnended Evacuation recommended Downwind sector
+ 2 adjoining sec ors Remaining sectors Complete circle around plant at specified distance
PROCFDURE 1102 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)
Page 21 WHOLE BODY OR THYROID DOSE DOSE (REM)
(REM) use 1 mil value use 2 mil value use 5 mile value DISTANCE FROM PLANT/RECOMMENDATIONS~
0-2 MILES 2-5 MILES 5-10 MILES
< 0.5
< 1.0 I
N 0.5 but 1.0
> 1.0 but 2.5 I
S (CR)
S (DW)
S (DW) 1.0 but 5 0 2-5 but 25.0 S (CR)
S (CR) 5 (CR) 5.0 I
25.0 I
E (CR)
S (CR)
S (CR)
E (DW)
E(DW)
+
'.QTE: If the duration of the release 'is
- hours, use Figure B-2.
&he dose 8
1 mile affects protective actions from 0-2 miles The dose 9 2 miles affects protective actions fram,2-5 miles The dose 8
5 miles affects protective actions from 5-10 miles projected to be greater than or equal to 2 I
<<LEGEND OF ABBREVIATIONS N - No protective action recommended S - Sheltering recommended E - Evacuation recommended DW-Downwind sector
+ 2 adjoining sect RS-Remaining sectors CR-Complete circle around plant at specif'ed distance The dose 9
10 miles can be used to evaluate protective actions for greater distances.
h
PROCEDURE 1102 12/15/83 TURKEY POINT PLANT FIGURE B-1 Page 18 PROTECTIVE ACTION RECOMMENDATIONS BASED ON PLANT COPDITIOPS - PTP GENERAL EMERGENCY NO Line 1
YES CHRRM 1e3 E+4 R Hr YES CORE
'ELT SE UENCE NO SE YES NO LINE 2 Con"ider 2 mi e
precautionary evacuation and shelter other parts of the downwind plane exposure pathway
~
see line 3 IMM NENT LOSS OF CONTAINMENT INTEGR ITY NO LIh'E 4 YES LINE 5 LINE 0-2 MILES Ni S
(CR)
E (CR)
E (CR)
E (CR)
LEGEND OF ABBREVIATIONS 2-5 MILES N
S (DW)
S DW)
E(DW) + S(RS)
E (CR) 5-10 MILES fi S
(DW)
S (DW)
E(DW) + S(RS)
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
Pag. 19 PROCEDURE 1102 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 Turkey Point Plant FIGURE B-2 Page 20 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
(REM) 0" 2 MILES use 1 mil value 2-5 MILES use 2 mile value 5-10 MILES use 5 mile value
<0.5
)
< 1.0 N
N 0.5 but 1.0 1.O but
- 2. 5 S (CR)
S (DW)
S (DW) 1.0 but 5.0 l
2-5 but
<25.0 E (CR)
E (DW) +
S (RS)
E (DW) +
'(RS)
> 5.0 I
)
>25.O E (CR)
E (CR)
E (DW) +
S (RS) 1'ote:
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 />, use Figure B-3.
&he dose 8
1 mile affects protective actions from 0-2 miles The dose 8
2 miles affects protective actions from 2-. 5 miles The dose 9 5 miles affects protective actions from 5-10 miles The dose 8 10 miles can be used to evaluate protective actions for greater distances.
+LE~~ OF ABBREVIATIONS N - No protective action recommended
- Shelte~ing recommended E - Evacuation recommended DW-Downwind sector
+ 2 adjoining sectors RS-Remaining sectors CR-Complete circle around plant at specified distance
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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 Approved by K. N. Harri ust 8
1975 19~
Revision
~
R iewe by Faci iey Approved by V
Revision 9
R ewe b
Facil ty Approved by eview Group jR P. Pwr. Res.
19 P/
Group g 108 I
0 'r 19 c, wr. Res.
6 19'/
LL Revision 10 Rev'gdgby QG cp uoCA4 9
Approved by 4C A Dir., Nucl.".Energy
- /
1982.
1982.
This proce re provides instructions on the classi-fication emergencies at St. Lucie Plant.
0 SCOPE:
~4
.1
~Pur ose
.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.
0 I
Page 3 of 20 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
PRIMARY DEPRESSURIZATION Page 1 of 4 Page 6 of 20 EVENT UNUSUAL EVENT SITE AREA EflERGENCY CENERAL EMERCEHCY MISCELLANEOUS h)
Un lanned lniciacfon of ECCS
~B c
coocf s
e
- l. ECCS punps running as indi-cated by motor amps, AND
- 2. ElXS header isolation valves open as indicated by valve position indication lights, OR B) Safct or relief valve fails co close
- 1. Reactor coolanc s seem RCS
- a. Indication of flou through prcssuriter relief valves as indi-cated on che acouscic valve flou 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.
Loss of 2 of 3 fission roducc barrier ufth otencial for loss of the third (hny tuo of the follouing coudf-cions exist and the third is imminent.)
- 1. Confirmed fuel clad damage.
- 2. Confirmed 10CA
- 3. Confirmed concafnmcnt inte-grity breached and cannot be restored.
ACTION 1.
Complete accions lisced on the UNUSUAL EVENT CllECKLIST.
- 1. Complece actions listed on CEHERAL EMERGENCY CHECKLIST.
PRIHARY DEPRESSURIZATION Sheet 2 of 4 Pug<<
7 of 20 CLASS EVENf UHUSUAL EVENT ALERT SITE AREA EHERCENCY CENERAL EHKRCEHCY LEAK RATE b
Technical S ecificacions A. RCS vater inventory balance indicates
- 1. greater 1 gpm unidentified
- leakage, OR
- 2. greater than 10 gpm identi-fied leakage, OR B. Inspection reveals any RCS pressure boundary leakage.
ABNORHAL PRIHARY RCS leak<<
e rester chan ulloved RCS leak rehcer chan 50 rimar to atmos here (1) Charging/lecdovu mismacch backed up by RCS vacer.
inventory balance Indicating
> 50 CPH and <132 gpm
- leakage, AHD (2) Concainmenc or plane vent radiation process. monitor reading above pormal.
LOCA reater than cu ucic uf char'in um s (1) Unusual decrease in pres-surirer level and pressure vith conscant T(ave),
AHD (2) Hakeup rate greater chan capacicy of 3 charging pumps (132) gpm) AIID (3) Concainmenc pressure
.>2 psig, or containmcnc radiation monitors indi-cate
<<bove normal values.
A release has occurred or is in progress resulting in:
LOCA Dose Calculutiou QPIP 3100033K Appendix B vorksheec values in excess of 1 R/IIR (vhole body) or un integruced dose of 5R (chyroid) or cont<<lament high rungu radiation monitor gfeater than nr equal to 1.47 x 10> R/lh (post IiICA monitors greater. thun 1000 mr/hr if CIIRRH inoperablu)
ACfION
- 1. Complete actions listed on the UNUSUAL EVENT CHECKLIST.
- 1. Complete uccions listed on ALERT CHECKLIST 1.
Complete uccions listed on SITE AREA EHERCEHCY CIIECKLIST
- l. Complete acclons listed on GENERAL fHERCEHCY CNECKI.IS'f
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c PRIHARY DEPRESSURIZATION Sbeec 3 of 4 Page 8 of 20 CLASS UNUSUAL EVEHT ALERT SITE AREA EHERCENCY CEHERAL EHERCENCY TO SECONDARY 1 CPH
- l. RCS Mater invcncory balance indicaces:
~enerator tuba wi h loss of off~ice wer w i char in
~ic ABNORHAL PRIHARY RCS PRI SEC Leaka e Creater Than Ra id ross failure of one steam Rs id failure of sccsm cneracor cubes with a lose of off-site ower
> char in Lc.
- h. Greater than 1 CPH unidcncified leakage AND B. Blowdown process monitors and condcnsace air effector process monitor reading above normal or increasing.
tubes
> char in ca acit
- l. Unusual decrease in prcssurirer pressure and level, with constant Tave>
I ANO'
~ 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.
- 1. Unusual decrease in prcssuriser pressure and level with conscanc T ave.,
followed by;
- 2. Above normal or increasing steam generator blowdown and condensate air e)cctor radia-tion process monitor readings,
~AND
- 3. Loss of che 6.9 KV and 4.16 KV busses (IA1, IA2, IBl, IB2)
OR Ra id failure of steam cnerator (1) Unusual decrease in pres-surizer pressure and level with conscant T(ave),
AND (2) Above normal readings on radiacion process monitors for steam generator blow-down and condensate air e$ eccor, AND (3) Loss of the 6.9 kV and 4.16 kV busses (lhl, lA2, 151, 182),
AND (4) Simultaneous unusual increase in one steam generator's prcssure and level.
ACTION
- 1. Complete actions listed on che UNUSUAL EVENT CllECKLIST.
- 1. Complete actions listed on ALERT CNECKI.IST
~
- 1. Complete accions lisccd on SITE AREA EHERCENCY CHECKLIST.
PRIMARY DEPRESSURIZATIOH Sheet 4 of 4 Page 9 of 20 UNUSUAL EVENT SITE AREA EHERGEHCY GENERAL EMERGENCY LOSS OF SECONDARY COOlANT Ra id de ressurizacion of seconder side with no rimar co seconder leaks e.
- 1. Unusual decrease in pressurize pressure and level with decreasing Tave AND
- 2. Simultaneous abnormal drop in Main Steam or steam generator pressure co less than 500 psia.
Ma or steam leak wicb rester than 10 rimar seconder leak race
- l. Unusual decrease in pressurizei pressure and level, with decreasing
- Tae,
~AND'.
Abnormal drop in main sceam or sceam generator pressure to < 500 psia,
~AND
- 3. Sceam generator blowdown and condensate sir effector radiation process monitors indicate above normal, (OR, known pri-sec leak of > 10 Bpm) ~
Ma or steam leak with rester than 50 rimar seconder leak race and fuel dame e indi-dated
- 1. Unusual decrease in pressurizer pressure and level with decreasing Tave/
~AND
- 2. Abnormal drop in main steam or steam generator pressure to < 500 psia,
~AHD.
- 3. Steam generator blowdown and condensate air effector radiacion process monitors 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 cbe UNUSUAL EVBIT CHECKLIST.
- 1. Complete actions listed on ALERT CHECKLIST.
1.
Complece accions listed on SITE AREA EMERGENCY CHECKLlST.
ACCIDEtlT INVOLVIHG FUEL Page 10 of 20 EVEHT CLASS UNUSUAL EVEHT SITE AREA ENERGEHCY GEHERAL EHERGENCY I'UEL ELENEftf FAILURE FUEL NANDLIHG ACCIURIIF Fuel dame e indication
- l. Coolant accivicy greater than the Tech Spec limit for iodine spike Figure 3.4-1 AND
- 2. Coolanc activity greacer chan 100/E uci/ ram s ecific acc-Severe loss of fuel claddin includfn coolant um failure leadin to ross fuel failure (1) Letdown iodine process monitor alarms, AHD (2)
RCS 1-131 activity >
275 uCi/ml Fuel handlin accident uhich results in che release of radfo-accivit to contafnmenc or Fuel Handlin Buildin (I) Direct informacion from fuel handlfng personnel indi-cating that an'rradiated fuel assembly has been damaged and gas bubbles are
- escaping, AND (2) Associated area or process monitor channels are alarming.
Cora dame e uich fnade uate core coolfn determined b
(1)
RCS 1-131 activity >
275 uCi/ml, (2)
RCS temperature within 20 of T(sat),
AHD (3) Loop AT >44 P Ma or dame e co s ent fuel in containment or Fuel Handlin
~RIIA LA (1) Step increase in che readings of radiation monitors in che plane vent and/or in the fuel handling building, AND (2) Damage to more than onu fuR:1 assembly, OR (3) Uncovering of more chan one spenc fuRAI assembly fn che spent fuel pic.
h release has occurred OR is in progress resulting in:
Loca Dose calculation EPIP 3100033K Appendix B uork-,
sheeC values in excR.ss of I R/Nk (uholebody) or an integrated dose of 5R (thyroid) or concafnox."nt hfph ra~ge radiation monitor
> 1.47 x 10 R/Nr (post IANNA monicors
>1000 mr/hr if CNRRH fnoperablu)
/Rlo ACI'IOII 1.
Complete actions listed on thc UHUSUAI, EVENT CHECKLIST.
1.
Complete actions listed on ALERT CHECKLIST 1.
Complete accions listed on SITE AREL EHERGENCY CHECKLIST
- 1. Complete actions liscR.d on GENERAL EHERGENCV CHECKLIST.
ABNORHAL RADIATION CONTAHIHATION OR EFFLUEHT RELEASE VALUES Pagh ll of 20 EVENT CLASS UNUSUAL EVENT SITE AREA EIIERGENCY GENERAL EHERCL'HCY UNCONTROLLED EFFLUEHT RELEASE Radiolo ical affluent Tech.
S ecs.
Limits exceeded
- 1. Plant effluent monitor(s) exceed alarm secpoinc(a) followed by
- 2. Confirmed analysis resulcs for gaseous or liquid release uhich exceeds Tcchnical Speci-fication limits.
h release has occurred'or is in progress thee 1s 10 cimes che T.S. limit (as shown by sample/
survey) h release has occurred or is in progress resulting in:
LOCh Dose Calculation EP1P 3100033K Appendix B uorksheet values 1n excess of 50 HR/llR (whole body) 250 HR/HR (thyroid) for I/2 hour OR 500 HR/llg (vhole body) 2500 HR/NR (thyroid) for tuo min ac thu site boundry. or Containment Nigh Range Radiar1on Honitor >7.3 x 103 R/hr h release has occurred or is in progress resulcing 1n:
LOCh Dose Calculation EP1P 3100033E Appendix g uorksheet values in excess of 1 R/llR (whole body) or an Integraced dose of 5 R (thyroid)or contalnmenc high range radiation monitor > 1.47 x 105 R/hr (Pose 1 or 2 Honitor >1000 mr/hr if CNRRH inoperable)
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NICll RADIATIOH LEVELS IN PLANT High radiacion levels or high 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 UNUSUAL EVENT CHECKLIST l.
Complete actions listed on ALERT CllECKLIST
- 1. Complete actions listed on SITE AREA EHERGEHCY CNECKI.IST
- 1. Complete actions listed on GENERAL EHERGEHCY CllECKLIST
FIRES LASTING BORE TIUIN 10 MlNUTES Page 12 of 20 CLASS UNUSUAL EVENT ALERT S1TE AREA ENERCENCY GENERAL ENERGENCY Uncontrolled fire not involving a safety syscea, but requiring off-site support.
Uncontrolled fire, potentially affecting safety systems and requiring off-site supporc.
Fire resulting in degradation of safecy syntone.
ACYION 1.
Cosplece
<<ecions lisced on the UNUSUAL EVENT CNECKL1ST.
1.
Couplers accions listed on ALERT CUECKLIST 1.
Cospleca actions listed on S1TE AREA EHEKCENCY CUECKLIST
DEGRADATION OF CONTROL CAPABILITIES Sheet I of 2 Page 13 of 20 EVENT CLASS UNUSUAL EVENT SITE AREA ENERGEHCY GENERAL ENERGEHCY EHGLNEERED SAFETY PROTECTION SYSTEN SYSTENS TO PLACE PIJWT IH COLD
~Stilt-OONI COHTROL ROOH OPERATION AND FIRE PROTEGTIOH SYSTEH
- l. A safety features actuation system functional unit shown in Technical Specification table 3.3-3 becomes inoperable per Technical Specification 3.3.2.1 AND requires plant
- shutdown, OR
- 2. The fire suppression system or a portion thereof becomes inoperable per Technical Specification 3.7.11.1 AND requires plant shutdown.
- 1. Loss of functions needed for cold shutdown, OR
- 2. Failure of tlute Reactor Protection System to bring the reactor subcritical when
- needed, OR
- 3. Evacuation of control room (for other than drill pur-poses) with'shutdown control established locally at the Not Shutdown Control Panel.
ines of any function or system which precludes placing the plant in Not Shutdown, OR Control Room is evacuated (for other than drill purposes and shutdown control cannot be established locally at the Not Shutdown Control Panel within 15 minutes.
LOSS OF ALARNS Significant loss of effluent monitoring capability, meterolo-gicai monitoring instrumentation coamLunications, indication and alarm panels, etc., which impairs ability to perform accident or emergency assessment.
hll annunciators lost.
hll annunciator alarms lost
>15 minutes with plant not in cold shutdown; OR Plant transient occurs with s11 alarms lost.
ACTION
- 1. Complete actions listed on UNUSUAL EVENT CHECKLIST.
- 1. Complete actions listed on ALERT CHECKLIST.
- 1. Complete actions listed on SITE AREA EHERGEHCY CHECKLIST.
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NAZARDS TO STATION OPERATION Page 15 of 20 EVBIT UNUSUAL EVENT S1TE AREA EMERGENCY GENERAL EMERGENCY AlRCRAPT Visual sighting of aircrafg crasb on-site or of unusual alrciaft activity over facility, Aircraft crash onsite damaging plant structures.
hircraft crash on site damaging vital plant systems or structures.
ONSKTE RXPIDSIDII Visual or audio indication of an explosion near or on-site.
Damage to facility by explosion wbicb affects plant oPeration.
Damage to safe shutdown equipment from missiles or explosion TOXIC OR PULH-HABLE GAS Indication (visual or otherwise) of a near or on-site toxic or flammable gas release.
Entry of toxic or.flammable gss onto areas potentially affecting plant operation.
Alarm indication is received on Detecto-Cblor or toxic or flammable gas has diffused into vital areas.
MISSILES Visual or audible indication of missile impact on plant structures.
Damage to safe shutdown equip-ment from missiles or explosion.
TURBINE FAILURE Visual indication tbat tbe turbine casing bas been penetrated by blading.
ACTION
- l. Complete actions listed on thu UNUSUAL EVP2Ã CUECKLIST.
- 1. Complete actions listed on ALERT CNECKLIST.
- 1. Complete actions listed on SITE AREA EMERGENCY CNECKLIST.
ELECTRICAL MALFUNCTION Page 16 of 20 CLASS UNUSUAL EUENr ALERT SITE AREA EHERCENCV GENERAL EHERCENCY LOSS OF POIIER Loss of off-site ower or loss
'of on-site AC ower ca abilit
- l. Turbine generacor tripawich plant scarcup cransformers unavailable for servicet OR,
- 2. Loss of voltage on both IA3 AND l83 4.16 KU busses for more than 15 seconds.
Imss of offsite ower and loss of all onsite AC wer 1.
Turbine generator 'trips wich plant acarcup crans-formera non-functional,
~AND.
2.
Failure of both auergency diesel generators to start or synchronize OR Loss of all onsice DC ower Loss of offsite er and loss of onsite AC ower
> 15 minutes l.
Turbine generator trips with plant startup transformers unavailable for service, AND; 2.
Sustained failure of boch emergency diesel genera-tors co scarc or synchronice for > 15 minutes.
Drop in A and 8 DC Bus voltages to < 70 volts.
OR 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 UNUSUAL BURNT CIIECKLIST.
- 1. Complete actions listed on ALERT CHECKLIST.
- 1. Complete actions listed on SITE AREA MERCENCY CHECKLIST.
SECURITY EHERGENCIES Page 17 of 20 EVENT CLASS UNUSUAL EVEHT SITE AREA EHERGENCY GENERAL EHL'RGL'NCY A security alert has been called by the security force in res-ponse to one or nore of the itcas listed belou.
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 A security caerycncy has been called by the security force as defined in the Safeguards Contingency Plan.
A security esergcncy has progressed to the'point that takeover of the plant is probable A successful takeover of thu plant including the Control Roon has occurred.
AClION
- 1. Coaplete actions listed on UNUSUAL EVEHC CHECKLIST.
- l. Coeplete actions list~el on t
ALERT CHECKLIST.
- 1. Couplete actions listed on SITE AREA EHERGENCY CHECK-LIST.
- 1. Cosplete actions listed on CENERAL EHERGENCY CHECKLIST
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HISCELLANEOUS EVENTS Shoat 1 of 2 Page 19 of '20 EVENT CLASS UNUSUAL EVENT 4
ALERT SITE AREA ENERCENCY CENERAI ENCRCENCY ABNORNAL
~TEHPRRATURE PRESSURE hbnornal coolant ceu erature ANDlOR ressura abnoreLal fuel
- 1. Subcooling uargin a+niter indicates less chen 20 P sub-o
- 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.
COHTAHIHATED INJURY hny concaainaced Individual is transported off-site to a hospital for creataent of ingurias.
ACTION
- 1. Complete actions listed on che UNUSUAL EVEHT CHECKLIST.
NISCEILANEOUS EVENTS Sheet 2 of 2 0
Page 20 of 20 UNUSUAL EVEHT ALERT SITE AREA ENERGENCY CENERAL ENERCENCY OTHER CONDITIONS CREASED AMARE-NESS
- l. A pinup shutdown is required by Technical Specifications; OR
- 2. The slant is shuc down under abnornah conditions (e.g.,
exceeding cooldown races or primary system pipe cracks're found during operation).
The Technical Supporc Center
~AHD OR Hear Site Emergency Operacions Facility are activated for other than drill purposes.
- 1. The Emergency Centers sru acCivated;
~AND 2; Honitoring Teams are mobilited;
~AND
- 3. A precautionary public notification is made con-cerning an abnormal plane condition for other than drill purposes.
An evenc resulting in escalation of the Emergency Classification to Ceneral Emergency with Imminent Subscantial Core Damage and potential for release of large amouncs of radioactivity in a short period of cime; such asc 1.
- 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 che UNUSUAL EVENT CHECKLIST.
- 1. Complete actions listed on ALERT CllECKLIST.
- 1. Complete actions listed on SITE AREA ENERCEHCY CHECKLIST.
- 1. Complete actions listed on CEHERAL ENERCEHCY CHECKLIST.
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