ML20069A913
ML20069A913 | |
Person / Time | |
---|---|
Site: | Saint Lucie |
Issue date: | 06/05/1981 |
From: | FLORIDA POWER & LIGHT CO. |
To: | |
Shared Package | |
ML17212B225 | List: |
References | |
PROC-810605, NUDOCS 8112220065 | |
Download: ML20069A913 (150) | |
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Pagn 8 of 11 E-PLAN IMPLEMENTING PROCEDURE No. 3100023E, REV. 20 EMERGENCY ROSTER EMERGENCY ROSTER APPENDLX A O MAad iG-5BI DUTY CALL SUPERVISORS MAINTENANCE DUTY OPERATIONS DUTY H. P. DUTY CALL CALL SUPERVISOR CALL SUPERVISOR SUPERVISOR T. A. Dillard g D. A. Sager G. M. Green i -
C. F. Leppla i J. A. Spodick f H. F. Buchanan
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J. E. Bowers B. W. Mikell -
l H. M. Mercer ,
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M. B. Vincent C. A. Pell J. H. Barrow P. L. Fincher N. G. Roos R. S. Glaze i i
M. D. Sheppard ,
Beeper No. Beeper No. Beeper No. \
8112220065 811215 PDR ADOCK 05000335 F PDR a
l Prga 10 of 11 E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 20 EMERGENCY ROSTER Plan Manager
. %W) hb' Date APPENDIX C 1
DUIT CALL SUPERVISOR'S CALL LIST PHONE TITLE NAME HOME OFFICE _
g Emer. Recovery & Restoration C. M. Wethy Ex. ,
I team leader - Plant Manager i Alternate: Ops. Superintendent J. H. Barrow \
Ex.
Emergency Control Officer A. D. Schmidt Beeper ALTERNATES -
Manager Power Res.-Nuclear C. O. Woody ,,
BeJper g
Asst. Vice Pres. Power Res. J. R. Benson k-Seeper, Asst. Mgr. Pwr. Res.-Nuclear K. N. Harris (Ft. Pierce-Weekendt
) (Miami-Veekdays Beeper Mgr. of Pwr. Res. H. N. Paduano __
4-Nuclear Services Beeper Pwr. Res. Specialist D. K. James _ ..
Beeper k '
, Pwr. Res. Sec. Supv. Plant R. J. Acosta -
~ ~ ~ 5,t e pe r .
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4 Pwr. Res. Sec. Supv. Health J. L. Danek ;
B2eper, -
o Systems Operations Power Coordinator TEAM LEADERS & ALTERNATES g j Emergency radiation team H. F. Buchanan ,
3 Ex.
leader Alternate emergency H. M. Mercer Ex..
radialon team leader ,
Alternate emergency G. M. Green or Ex. i radiation team leader R. M. McCullers Ex.
\
Plant Fire Protection W. J. Barrow 4 Ex. I Coordinator !
g - -- - ___ . .. _ _ . ,
FLORIDA POWER & LIGRT COMPANY ST. LUCIE UNIT #1 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E REVISION 10 l 1.0
Title:
DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
2.0 Approval
Reviewed by Plant Nuclear Safety Committee July 25, 1975 Approved by K. N. HarrisPlant Manager July 29, 1915 Rev. 10 R wed FRG. )hfap . j2 9 1 Approved '171ch Pres. Power Resources hL, 19
3.0 Scope
3.1 Purpose
This procedure provides the instructions to be followed by the Emergency Coordinator when an emergency occurs that requires the initiation of the Emergency Plan.
3.2 Discussion
The Nuclear Plant Supervisor becomes the Emergency Coordinator upon initiation of the Emergency Plans and, as such, directs the On-Site Emergency Organization to bring the emergency under control.
3.3 Authority
This procedure implements the St. Lucie Plant Radiological Emergency Plan.
4.0 Precautions
4.1 The Nuclear Plant Supervisor and the shif t operating staff represent the first-line of response to any developing emergency condition.
The primary responsibility of the Nuclear Plant Supervisor is to control the condition as well as possible. However, the success of the Emergency Plan and Procedures requires immediate classification of the emergency (in accordance with E-Plan Implementing Procedure i 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, the content of that notification and of providing protective action recommendations to state and local authorities.
When the TSC is operational, the Emergency Coordinator can delegate all of f-site communications to the TSC Supervisor. /R10
Page 2 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DITIIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
5.0 Responsibilities
5.1 If the Nuclear Plant Supervisor is incapacitated, the Emergency Coordinator shall be (in order of succession):
5.1.1 Nuclear Watch Engineer 5.1.2 Any other member of the plant staff with a Senior Reactor Operator License.
5.2 The Emergency Coordinator shall only grant permission for watch relief, including his own, when it is safe in his judgement to do so.
5.3 The Operations Superintendent, the Operations Supervisor or a Operations Duty Call Supervisor can assume the Emergency Coordinator function at his discretion following the proper turnover procedure.
5.4 The Technical Support Center Supervisor shall fill out the checklist for Notification of Significant Events (to NRC) as soon as possible after activating the TSC and preferably before calling the NRC.
5.5 The Emergency Coordinator is responsible for providing protective action recommendations to off-site authorities. This responsibility
. cannot be delegated. /RIO 6.0
References:
6.1 St. Lucie Plant Radiological Emergency Plan 6.2 E-Plan Implementing Procedures, as follows:
EPIP-3, Classification of Emergencies.
EPIP-5, Criteria for and Conduct of Evacuations.
EPIP-6, Radiation Release and Dose Projection.
7.0 Records
All significant information, events, and actions taken during the emergency period shall be recorded as directed by the Emergency Coordinator.
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Page 3 of 20 E-PLAN IMPLEMENTING PF.0CEDURE NO. 3100021E, REV. 10 DITTIES AND RESPONSIBILI"'IES OF THE EMERGENCY COORDINATOR
8.0 Instructions
8.1 Classification Immediately upon becoming aware of an abnormal condition, the Nuclear Plant Supervisor shall classify the condition in accordance with the criteria given in E-Plan Implementing Procedure 3100022E, Classi.fication of Emergencies. If the classification is, UNUSUAL EVE!ff, ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, the Nuclear Plant Supervisor shall declare an emergency and become the Emergency Coordinator. The Emergency Coordinator shall, until relieved, remain in the Control Room at all' times during emergency situations that require Faergency Plant implementation unless, in his opinion, his personal evaluation of the situation is necessary to maintain plant safety.
8.2 The Emergency Coordinator shall mobilize the On-Site Emergency Organization to begin required corrective and protective actions.
8.3 UNUSUAL EVENT If an UNUSUAL EVENT is declared, the Emergency Coordinat.or shall complete the actions specified in the attached UNUSUAL EVENT CHECKLIST. These actions include required off-site notifications and on-site protective actions.
8.4 ALERT 4
If an ALERT is declared, the Emergency Coordinator shall complete the actions specified in the attached ALERT CHECKLIST. These actions include required of f-site notifications, on-site protective actions, and activation of on-site support centers.
8.5 SITE AREA EMERGENCY If a SITE AREA EMERGENCY is declared, the Emergency Coordinator shall complete the actions specified in the attached SITE AREA EMERGENCY CHECKLIST. These actions include required off-site notifications, on-site protective actions, and activation of on-site support centers.
,i 8.6 GENERAL EMERGENCY
'; If a GENERAL EMERGENCY is declared, the Emergency Coordinator shall
! complete the actions specified in the attached GENERAL EMERGENCY l CHECKLIST. These actions include required off-site notifications, on-site protective actions, and activation of on-site support centers.
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4 Page 4 of 20 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
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8.0 Instructions
(continued) 8.7 MEDICAL EMERGENCIES The attached MEDICAL EMERGENCY CHECKLIST shall be followed in the 5 event of injury to plant personnel or visitors. The MEDICAL NOTIFICATION FORM attached to the Checklist shall be prepared for each victim and shall, if possible, accompany the victim to off-site 1
emergency treatment. The MEDICAL EMERGENCY CHECKLIST may be followed independently of the Radiological Emergency Plan.
8.8 Responsibilities for off-site communications and coordination shall
- be relinquished first to the Technical Support Center Supervisor and j then to the Energency Control Officer when they establish contact and assume responsibilities.
I 8.9 0FF-SITE EVACUATION RECOMMENDATIONS The Emergency Coordinator is responsible for providing protective action recommendations to off-site authorities in accordance with Table 1, " Guidelines for Protective Action Recommendations to Off-site Authorities". /RIO d
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Prga 5 cf 20 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 10 DITTIES AND PSSPONSIBILITIES OF THE EMERGENCY COORDINATOR UNUSUAL EVEVr CHECKLIST ACTIONS TO BE TAKEN BY EMERGENCY COORDINATOR OR HIS DESIGNEE IN THE EVENT OF AN UNUSUAL EVENT
- 1. Order initial corrective action per Emergency Operating Procedures.
Fire / Explosion - aee attached FIRE / EXPLOSION CHECKLIST Medical - see attached MEDICAL EMERGENCY CHECKLIST
- 2. Mobilize Interim Emergency Teams to respond as necessary.
- 3. Commence preparation of the attached EMERGENCY INFORMATION CHECKLIST excluding off-site dose projections.
- 4. During current business day, 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 Manager Operations Superintendent Operations Supervisor Technical Department Supervisor
- 5. Within 15 minutes of classifying the emergency:
- 1. Notify, by telephone, the State Warning Point at the Bureau of Disaster Preparedness in Tallahassee and communicate EMERGENCY INFORMATION CHECKLIST data.
PHONE NO. . ._. 4 Florida Marine Patrol-Alternate State Warning Point _
f~
NOTE: Expect a message validation callback. from B.D.P.
- 2. Notify, by telephone, the State Radiological Emergency Duty Officer at Radiological Health Services in Orlando and communicate EMERGENCY INFORMATION CHECKLIST data. PHONE No. f
- 6. Prepare attached SIGNIFICANT EVENT REPORT (if time permits) and notify NRC via hot-line (within one hour) /RIO
- 7. Reassess the Emergency Classifica* ion and update the EMERGENCY INFORMATION CHECKLIST. /RIO
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i Page 6 of 20 j E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DLTflES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ALERT CHECKLIST ACTIONS TO BE TAKEN BY EMERGENCY COORDINATOR OR HIS DESIGNEE IN THE EVENT OF AN ALERT
- 1. Order initial corrective action per Emergency Operating Procedures.
Fire / Explosion - see attached FIRE / EXPLOSION CHECKLIST Medical - see attached MEDICAL EMERGENCY CHECKLIST
- 2. Notify personnel of the emergency condition over the Unit
- 1 PA system, giving location, class, and type of emergency.
Repeat announcement
- 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:
Area to be evacuated Areas to be avoided, if possible, during the Evacuation Assembly area-
- 4. Mobilize Interim Emergency Teams to respond as necessary, i 5. Commence preparation of the attached EWMERGENCY INFORMATION CHECKLIST including off-site dose projections using E-Plan Implementing Procedure 3100033E, Radiation Release and Dose Proj ection.
( 6. Relay information to the Duty Call Supervisor (see NPS Bulletin Board for scheduled supervisor and telephone number). Order him to notify the following:
Plant Manager Operations Superintendent Operations Supervisor Technical Department Supervisor Emergency Control Officer (or Radiological Duty Officer)
Other Department Supervisors (Primary Team Leaders)
(ALTERNATE METHOD if Duty Call Supervisor is unavailable-Notify Emergency Control Officer.
- 7. Notify the following within 15 minutes of classifying the emergency:
\ . . - - . . . - - _
Pg2 7 cf 20 E-PLAN IMPLEMENTINC PROCEDURE No. 3100021E, REV. 10 DtTTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
. 3 ALERT CHECKLIST (Continued) 7.1 Notify, by telephone the State Warning Point at the Bureau of Disaster Preparedness in Tallahassee and communicate EMERGENCY INFORMATION CHECKLIST data. PHONE NO. _ _ _.. _ . or Florida Marine Patrol-Alternate State Warning
~-
Point NOTE: Expect a message validation callback from B.D.P. /RIO 7.2 Notify, by telephone the St. Lucie County Disaster Preparedness Office in Fort Pierce, and communicate EMERGENCY INFORMATION CHECKLIST data. PHONE NO. 911 7.3 Notify, by telephone the Martin County Disaster Preparedness Office in Stuart and communicate EMERGENCY INFORMATION CHECKLIST data. PHONE NO. '/
7.4 Notify, by telephone the State Radiologhical Emergency duty Officer at Radiological Health Services in Orlando and communicate EMERGENCY INFORMATION CHECKLIST data. PHONE NO.'s /
~-_/
- 8. Prepare attached SIGNIFICANT EVENT REPORT (if time permits) and notify NRC via hot-line (within one hour).
(To be done by TSC if properly staffed)
- 9. Verify from Security Team Leader that all personnel are accounced for (if local evacuation was conducted).
- 10. Reassess corrective and protective actions. Verify activities underway, reassign personnel and teams as necessary.
- 11. Activate the Technical Support Center and the Operational Support Center. Appoint OSC Supervisor.
- 12. Brief the Technical Support Center Supervisor on events. Order him to provide state and county with periodic updates and to refine dose projections when the Chemistry Department representative arrives. ~
- 13. Reassess the Emergency Classification and update the EMERGENCY INFORMATION CHECKLIST with Technical Support Center Supervisor.
- 14. Relinquish responsibilities for communications with off-site support agencies when the Emergency Control Officer notifies the Emergency Coordinator that he accepts these responsibilities.
Page 8 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SITE AREA EMERGENCY CHECKLIST ACTIONS TO BE TAKEN BY EMERGENCY COORDINATOR OR HIS DESIGNEE IN THE EVENT OF SITE AREA EMERGENCY. .
- 1. Order initial corrective action per Emergency Operating Procedures.
- 2. Notify personnel of the emergency condition over the PA system (connect all units), giving location, class, and type of emergency.
- 3. Order all non-essential personnel to commence evacuation of the Owner Controlled Area in accordance with E-Plan Implementing Procedure 3100026E, Criteria for and Conduct of Evacuations.
- 4. Sound Site Evacuation Alarm.
- 5. Repeat PA announcement.
- 6. Oruer Security Team Leader to evacuate Owner Controlled Area and to report personnel accountability as soon as possible.
- 7. Mobilize other Interim Emergency Teams to respond as necessary.
- 8. Commence preparation of the attached EMERGENCY INFORMATION CRECKLIST, including off-site dose projection using E-Plan Implementing Procedure 3100033E, Radiation Release and Dose Projection. Fire / Explosion and Medical Checklist are attached if required.
- 9. Relay information to the Duty Call Supervisor (see NPS Bulletin Board for scheduled supervisor and telephone number). Order him to notify the following:
Plant Manager Operations Superintendent Operations Supervisor Technical Department Supervisor Emergency Control Officer Other Department Supervisors (Primary Team Leaders)
(ALTERNATE METHOD If Duty Call Supervisor is unavailable-notify Emergency Control Officer.
1
PIga 9 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 310002)E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE EMERGEN".Y COORDINATOR SITE AREA EMERGENCY CHECKLIST (Cont.inued) l
- 10. NAWAS Announcement: (to be accomplished within 15 minutes af ter declaring the emergency condition).
" State Warning Point Tallahassee, this is St. Lucie One (State Warning Point will give a go-ahead)
" State Warning Point Tallahassee, this is St. Lucie One, Ground Fog, SITE AREA EMERGENCY, repeat SITE AREA EMERCENCT." Additional data will be transmitted by Local Government Radio.
Time
" Acknowledge, over."
(ALTERNATE METHOD if NAWAS is unavailable-telephone State o Warning Point at PHONE NO.
Patrol-Alternate State Warning Point ~
_[~ ;or Florida Marine a
, 11. State Warning Point Message Validation Time (NAWAS and LGR announcement also serves to notify St. Lucie and Martin Counties and the State Department of Health and Rehabilitative Services.)
- 12. Relay EMERGENCY INFORMATION CHECKLIST data including off-site dose projections by LGR. /R10 i'
- 13. Also, by LGR, contact St. Lucie County Disaster Preparedness, inform them that site evacuation has started, location of assembly area (s), evacuation route (s). Notify l- them of any wind changes, and when evacuation is completed.
I, .
l 14. Prepare attached SIGNIFICANT EVENT REPORT (if time i permits) and notify NRC via hot-line (within one hour).
(To. be done by TSC if properly staffed.)
l 15. Verify from Security Team Leader that Owner Controlled l Evacuation (including Unit #2 construction site) is L complete and that all personnel are accounted for.
l, 16. Reassess corrective and protective actions. Verify
!! activities underway, reassign personnel and teams as necessary.
- 17. Activate the Technical Support Center and the Operational Support Center.
3
- 18. Brief the Technical Support Center Supervisor on events. Order him to update state and county periodically and to refine dose projections when the Chemistry Department representative arrives.
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s Page 10 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DITTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SITE AREA EMERGENCY CHECKLIST (Continued)
- 19. Reassess the Caergency Classification and update the EMERGENCY INFORMATION CHECKLIST with the Technical Support Center Supervisor.
- 20. Relinquish responsibilities for communications with off-site support agencies when the Emergency Control Officer notifies the Emergency Coordinator that he accepts the responsibilities.
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- Pega 11 cf 20 E-PLAN IMPLEME.VIING PROCEDURC NO. 3100021E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR GENERAL EMERGENCY CHECKLIST ACTIONS TO BE TAIGN BY EMERGENCY C00RDIJATOR OR HIS DESIGNEE IN THE EVEN! 0F GENERAL EMERGENCY
- 1. Order initial corrective action per Emergency Operating Procedures.
- 2. Notify personnel of the emergency condition over the PA system (connect all units) giving location, class, and type of entgency.
- 3. Order all non-essential personnel to commence evacuation of the Owner Controlled area in accordance with E-Plan Implementing Procedure 3100026E, Criteria for and Conduct of Evacuations.
- 4. Sound Site Evacuation Alarm.
- 5. Repeat PA Announcement.
- 6. Order Security Team Leader to evacuate Owner Controlled Area and to report personnel accountability as soon as possible.
- 7. Mobilize other Interim Emergency Teams to respond as necessary.
- 8. NAWAS Announcement:(to be accomplished within 15 minutes af ter declaring the emergency condition.)
- i " State Warning Point Tallahassee, this is St. Lucie One"
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(State Warning Point will give a go-ahead.)
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" State Warning Point Tallahassee, this is St. Lucie One Ground Fog, we have a GENERAL EMERGENCT, repeat GENEPAL EMERGENCY.
l Time
' Wind aph from degrees i .
Meteorological conditions are (stable / unstable)
I Additional EMERGENCY INFORMATION will be forthcoming I shortly.
Acknowledge, over."
,! (ALTERNATE METHOD If NAWAS is unavailable, telephone State
' Warning Point at PHONE NO. . _. ..
or Plorida Marine Patrol-Alternate State Warning Point /Rire L' 9. State Warning Point Message validation Time . /R18
}; (NAWAS announcement also serves to notify St. Lucie and I
Martin Counties and the State Department of Health and i
Rehabilitative Services.)
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Page 12 of 20 E-PLAN IMPLEMENf1NG PROCEDURE NO. 3100021E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR GENERAL EMERGENCY CHECKLIST (Continued)
- 10. Complete EMERGENCY INFORMATION CHECKLIST including off-site dose projections using E-Plan Implementing Procedure 3100033E, Radiation Release and Dose Projection.
- 11. Transmit EMERGENCY INFORMATION CHECKLIST data by LGR (NAWAS or telephone of LGR not operational).
- 12. State Warning Point Acknowledgement Time .
- 13. Also by LCR, contact St. Lucie County Disaster Preparedness, inform them that site evacuation has started, location of assembly area (s), evacuation route (s). Notify them of any wind changes, and when evacuation is completed.
- 14. Relay information to the Duty Call Supervisor (see NPS Bulletin Board for scheduled supervisor and telephone number). Order him to notify the following:
Plant Manager Operations Superintendent Operations Supervisor .
Technical Department Supervisor Emergency Control Officer Other Department Supervisors (Primary Team Leaders)
ALTERNATE METHOD if Duty Call Supervisor is unavailable-Notify Emergency Control Officer.
- 15. Prepare attached SIGNIFICANT EVENT REPORT (if time permits) and notify NRC via hot-line (within one hour).
(To be done by TSC if properly staffed.)
- 16. Verify from Security Team Leader that Owner Controlled Evacuation (including Unit #2 construction site) is complete and that all personnel are accounted for.
- 17. Reassess corrective and protective actions. Verify activities underway, reassign personnel and teams as
, necessary.
- 18. Activate the Technical Support Center and the Operational Support Center. -
- 19. Brief the Technical Support Center- Supervisor on events. Order him to update state and county periodically and to refine dose projections when the Chemistry Department representative arrives. (EOF will perform these tasks when operational).
.~ ...
Page 13 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR GENERAL EMERGENCY CHECKLIST (Continued)
- 20. Reassess the Emergency Classification and update the EMERGENCY INFORMATION CHECKLIST with the Technical Support Center Supervisor.
- 21. Relinquish responsibilities for communications with off-site support agencies when the Emergency Control Officer notifies the Emergency Coordinator that he accepts the responsibilities.
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Page 14 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DUTIES AND RESPONSIBIL! TIES OF THE EMERGENCY COORDINATOR EMERGENCY INFORMATION CHECXKLIST
- 1. Description of incident
- 2. Emergency Classification j 3. Location of Incident
! 4. Date/ time of Incident
- 5. Assessment of the emergency (including) potential for esca-lating to higher class) 4 l
' 6. Personnel injuries and radiation exposures
- 7. Estimate of radioactive material released.
I I- 8. Areas potentially affected
- 9. Wind speed
- 10. Down wind direction and /RIO range over past nour 1
- 11. Assessment of potential j' -
radiation exposure to
! persons off-site (use
! E-Plan Laplementing ll. Procedure 3100033E, i'
Radiation Release and Dose Projection) 1 I ._ _ _ . . . .__ __ _.
. _ , . . _ _ _ . . _ .-.___ . _ _ _ _ _ . . . ~
__ _ _. _._. _. . . . . . _ . . _.m_. __ _ . _-__ _ . __ . . _ . . _. .
Page 15 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST TIME P.A. Announcement of location and extent of fire.
Sound Fire Alarm.
Activate the Fire Brigade and other appropriate emergency teams in accordance with Fire Emergencies EPIP 3100025E - PA announcesent. /R1(-
St. Lucie County - Fort Pierce Fire District PHONE No. 911.
Return to appropriate UNUSUAL EVENT ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY n c~ecklist.
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Page 16 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DITfIES AND RESPONSIBILITIES OF THE EMERGENCY COORDIf{ATOR MEDICAL EMERCENCY CHECKLIST TIME Determine:
Name of Victim Employer (if not FPL)
Nature and Extent of Injury Location Is victim contaminated?
Activate First Aid and Personnel Decontamination Team (Notify Chemistry Supervisoe).
Notify:
Health Physics Plant Manager Operations Superintendent When determined, notify Captain of Guard where to direct
- ambulance, etc.
Determine mode of transportation based on nature and extent of inj uries. (Ensure victim's TLD, selfreader, ID badge and key card are retained on site).
- a. Medical treatment for serious injury:
[ AMBUIANCE PHONE NO. 911
- b. Medical treatment for minor injuries:
FPL Venicle/ Private Vehicle Send all victims to LAWNWOOD MEDICAL CENTER PHONE NO. _ /
Radioactively contaminated victims: ~
( Notify REEF PHONE NO.'
! If Plant Manager not available, notify Duty Call Supervisor and Health Physics Duty Call Supervisor-See Emergency Roster for Off-site notifications.
Complete attached Medical Notification form to accompany victim.
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Page 17 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE DfERGENCY COORDINATOR MEDICAL NOTIFICATION FORM
, In the event of a radiation emergency which requires the transportation of casualties to REEF, located within Mt. Sanai Hospital, Lawnwood Medical Center, or Radiology Associates, the Emergency Coordinator shall transmit the i following information, if it is available:
1
- 1. Name and security badge number of the cas,ualty Name Number
- t 2. Number of casualties being transported
! 3. Types of injuries involved and body part:
- a. Fractures
- b. Burns
- c. Hemorrhaging
- d. Other
{
i e. Ambulatory: Yes No j 4. Radiation contamination status:
t
! a. Type of instrument used I
, b. BEFORE Decontamination AFTER Decontamination Body Part C/M Distance C/M Distance 1
2.
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- l. 4.
- c. Radioisotopes involved
- d. Decontamination procedures used
- 5. Type of transporting vehicle
- 6. Time of departure from plant I
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Page 18 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SIGNIFICANT EVENT REPORT (for NRC Notification)
Date Time Facility Name Florida Power & Light St. Lucie Unit #1 /R10 Caller Name
- 1. Description of Event Classification of Event Reactor Systems Status Pressure Temperature Power level Flow ECCS Operating / Operable (Pumps on)
- PZR or RX Level Cooling Mode Any Radioactive Release or Increased Release?
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! Path Stopped? Release Rate
! Monitored 7 t Steam Plant Status: S/G Levels Equip. Failures Feedwater Sourec/ Flow Electrical Dist. Status: Normal Off-site Power Sources Available?
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Major Busses / Loads Lost
]' Safeguards Busses Power Source ij D/G Running? Loaded?
Personnel Casualties / Contamination?
j 2. Consequences of Event:
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,! Actual and Potential Safety Hazards:
al.
N Tech. Spec. Violations?
Il State Notified? Press Release Planned?
- 3. Cause of Event:
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!. Corrective Actions taken:
- i Planned:
..._s..--_.~._.
Page 19 Of 20 E-PLAN IMPLEMEIRING PROCEDURE NO. 3100021E, REV. 10 DttflES AND RESPONSIBILITIES OF Tile EMERGENCY COORDINATOR 5
EMERGENCY .
COORDINATOR STATE OF FLORIDA DUTY CALL EMERGENCY CONTROL OFFICER FPL BUREAU OF DISASTER SUPERVISOR OR +
j PREPAREDNESS
,7 ALT. E.C.O.; 7> RADIOLOCICAL DUTY OFFICER OFFSITE EMERGENCY ORGANIZATION ,
l g STATE OF FLORIDA L_______J ADDITIONAL j! DEPT. OF HEALTH &
m PLANT SUPPORT
! REllABILITATIVE SERVICES I
ST. LUCIE/ MARTIN COUNTIES EMERGENCY TEAM N TEAM MLMBERS j OFFICE OF DISASTER e
- LEADERS PREPAREDNESS
{
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OPERATIONS CE!RER TELEP110NE EMERGENCY TEAMS I
LOCAL SUPPORT J. FIRE / AMBULANCE; ST. LUCIE COUNTY-FORT PIERCE FIRE DISTRICT _
! 2. MEDICAL; TIIESE AGENCIES WILL RECEIVE i LAWNWOOD MED. CTR. '
NOTIFICATION AS FOLLOWS A
OR REEF AT Mr. SINAI ALERT: PROMPT VIA TELEP110NE SITE OR GENERAL: PROMIT VIA NAWAJ ST. LUCIE PLANT INITIAL NOTIFICATION FLOW PRIMARY COMMUINICATIONS FLOW FIGURE 1 ALTERNATE (X)MMUNICATIONS FLOW l
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Pign 20 of 20 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 10 -
DiffIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR {
Table 1 ~
Guidelines for Protective Action Recommendations i to Offsite Authorities .
I
! N=No Recommendation S= Shelter r E= Evacuate ,
RADIUS FROM PLANT /(Sector Affected-Downwind) l Condition 2 Miles -
5 Miles 10 Miles j
Unusual Event N N N
' Alert N N N Site Area Emergency N N N l
, General Emergency with the post Loca i monitors reading 1000 MR or greater E(360 ) E(90 ) N i
General Emergency with the post Loca
! monitors reading 1000 MR or greater E(360 ) E(360 ) E(90")
j AND with actual containment failure Actual releases (regardless of emergency class) with off-site doses estimated to be: E(360 ) S(360 ) S(360 )
a) Whole body: > 1 rem l or Thyroid: < 5 rem b) Whole body: > 1 rem to ' 5 rem Thyroid: > 5 rem to 7 25 rem E(360 ) E(360 ) E(90*)
c) Whole body: > 5 tem Thyroid: > 25 rem E(360 ) E(360 ) E(360 )
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Page 1 of 10 FLORIDA POWER & LIGHT COMPANY ST LUCIE UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E REVISION 1
1.0 Title
ON-SITE SUPPORT CENTERS
2.0 Approval
Reviewed by F ilit Revi Group d'l1c$ Lo41f 19 Gl Approved by M V. P. Power Resources 4(#f2M M,19 Rev 1 Review y Facility Review Group .
3y 4 8 19M Approved by V. P. Power Resources A 2.,195 /_
3.0 Scope
3.1 Purpose This procedure provides guidelines and responsibilities for activation and use of the on-site Technical and Operational Support Centers. This procedure describes interim facilities '
and shall be revised when permanent facilities are operational.
3.2 Discussion The activities of plant management, technical, and engineering support personnel are an important part of the overall site response to an accident, and must be properly defined and logistically supported. The need for additional operational support personnel, other than those required and allowed in the Control Room, is also recognized as vitally important in properly responding to an emergency.
The intent of'providing Technical and Operational Support Centers is to provide bases where post-accident emergency planning can be conducted and required operational support personnel can assemble for potential duty. Both centers will be in close communication with the Control Room via the PAX phone system, without disrupting, congesting, or confusing the activities in the Control Room by the physical presence of additional personnel.
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Page 2 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 1 ON-SITE SUPPORT CENTERS 3.0 Scope (cont):
! 3.3 Description i
3.3.1 Technical Support Center (TSC)
The TSC is located in the training classroom area, adjacent to the Unit #1 Control Room. Emergency supplies available near the TSC are listed in Table 1. Documents and drawings available are listed in Table 2.
3.3.2 Operational Support Center (OSC)
The OSC is maintained in the first floor maintenance. area of the Service Building.
3.3.3 Communications Equipment The Control Room contains necessary telephone and public address systems for communications within and outside the plant. The Control Room also cantains NAWAS and Local Government Radio fer communications with state and county
. agencies. Use of these systems is described in the Appendix.
The TSC contains necessary telephones to communicate with the Control Room, OSC, the General Office Emergency Center, the Emergency Operations Facility and outside agencies.
It also contains an ENS dedicated telephone to the NRC Operations Center and the NRC Region I office.
. 3.4 Authority This procedure implements the St Lucie Plant Radiological
T
4.0 Precautions
4.1 The TSC and OSC shall be activated upon the direction of tbe Emergency Coordinator or his designated alternate only.
- 4.2 Radiological conditions in the on-site Technical and Operational Support Center shall be monitored when required to be in use.
Radiation levels in the TSC should be monitored using available
-(control. room) portable instruments, in addition, Health Physics Department shall provide an NMC portable monitor to the Technical R1 Support Center- for radioiodine monitoring. This monitor can also
- be used for monitoring the control room.
4.3 The Emergency Coordinator shall recommend a suitable location other than the designated areas if radiological conditions warrant such actions.
Paga 3 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV L ON-SITE SUPPORT CENTERS
5.0 Responsibilities
5.1 The Emergency Coordinator is responsible for activating the TSC, activating the OSC, and arranging for staffing through the Duty Call Supervisor.
i 5.2 The TSC Supervisor will be the most senior person available to remain at the TSC of the following:
Primary: Operations Superintendent Alternate 1: Operations Supervisor Alternate 2: Operations Duty Call Supervisors Alternate 3: Off-Duty Nuclear Plant Supervisors He is responsible for. supervising TSC activities, reporting to the Emergency Coordinator, and communicating with the Emergency Operations Facility.
5.3 Each cepartment head or designated alternate is responsible for reporting to the TSC when called.
t 5.4 Those reporting to the Operational Support Center are responsible i for being prepared to carry out support functions designated by the Emergency Coordinator.
5.5 The Emergency Coordinator has the overall responsibility for the conduct of emergency operations and activities and should work closely with the TSC to ensure all information is used in making accident recovery decisions.
I
- 5.6 The QC department is responsible for ensuring that records,
';. documents, and prints are maintained in the TSC or are available for immediate use in the Document Control vault.
.j 6.0
References:
'I i 6.1 St Lucie Plant Radiological Emergency Plan i
i 6.2 E-Plan Lnplementing Procedure 3100021, Duties of the Emergency Coordiantor.
7.0 Records
A record of actions taken at the TSC shall be maintained by the TSC Supervisor.
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Page 4 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 1 ON-SITE SUPPORT CENTERS
8.0 Instructions
8.1 Activation i .
} The Emergency Coordinator shall activate the TSC and the
[ OSC for an emergency condition classified as Alert, Site Area
, Emergency, or General Emergency.
8.2 Staffing i
l The Emergency Coordinator shall arrange for staffing through i the Duty Call Supervisor, Table 3 identifies the TSC staffing j requirements.
l 8.3 Use of the Technical Support Center The TSC shall be used to provide plant management and technical support to plant operations personnel during emergency-conditions. A primary task shall be to relieve the Emergency l Coordinator of off-site communications to the state and local l agencies, NRC and the FPL Off-Site Emergency Organization.
The TSC staff shall provide technical support as requested by the Emergency Coordinator and shall direct itself toward de-termining current and projected plant status and providing in-i depth diagnostic and engineering assistance, as required.
t 8.4 Use of the Operational Support Center The Emergency Coordinator shall assign available plant staff not needed in the TSC or Control Room to the OSC. The OSC Supervisor (senior stuff member present) shall maintain communications with the TSC and report as directed by the Emergency Coordinator or TSC Supervisor.
8.5 Deactivation It is the responsibility of the Emergency Coordinator or his designee to deactivate and secure the TSC and OSC when the emergency condition no longer exists, t 8.6 Alternate OSC In the event that the OSC becomes untenable, the Emergency Coordinator shall designate an alternate location.
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Page 5 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 1 ON-SITE SUPPORT CENTERS TABLE 1 4
RADIOLOGICAL EMERGENCY EQUIPMENT ST LUCIE PLANT CONTROL ROOM STORAGE LOCKER
, (ALSO FOR TSC USE)
- 1. Coveralls
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- 2. Hood
! 3. Gloves l
j 4. Shoe Covers iI
- 5. Self Contained Breathing Apparatus
!. 6. Full Face Respirators and Filters
- 7. Pocket Dosimeters
- 8. Dosimeter Chargers
- 9. TLD's
, 10. Portable Count Rate Instrumentation i
- 11. Portable Dose Rate Instrumentation Il
- 12. Contamination Smears
- 13. Envelopes
- 14. Radiation Tape / Rope i
- 15. Radiological Signs I
- 16. Industrial First Aid Kit
- 17. Step-Off Pads i
- 18. Plastic Bags i
}
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Page 6 of 10 EMERGENCY PIAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 1 ON-SITE SUPPORT CENTERS TABLE 2 EMERGENCY DATA, DRAWINGS AND DOCUMENTS MAINTAINED AT THE TSC ST LUCIE PLANT
- 1. Plant Technical Specifications '
- 2. Plant Operating Procedures
- 3. Emergency Operating Procedures
- 4. Emergency Plan and Implementing Procedures i 5. Final Safety Analysis Report
- 6. Drawings, Schematics and Diagrams 1
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- l Page 7 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 1
)I ON-SITE SUPPORT CENTERS
, , TABLE 3
- i l! TECHNICAL SUPPORT CENTER STAFFING l* ST LUCIE PLANT i
I TSC Supervisor l
Primary: Operations Superintendent Alternate 1: Operations Supervisor j Alternate 2: Operations Duty Call Supervisors Alternate 3: Off-duty Nuclear Plant Supervisors t'
Technical Supervisor Health Physics Supervisor a
'i l Chemistry Supervisor
,1 i Reactor Eilgineering Supervisor i
Maintenance Superintendent
~
ik Quality Control Supervisor Support Staff as determined by these supervisors l,
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Page 8 of 10 EMERGENCY PLAN DIPLEMENTING PROCEDURE NO. 3100032E, REV 1 j ON-SITE SUPPORT CENTERS t
t
- APPENDIX COMMUNICATIONS EQUIPMENT A. Use of the NAWAS System
{ 1. The NAWAS is used for announcing the initial warning to the State Warning Point at the Bureau of Disaster Preparedness i (BDP) and St Lucie Disaster Preparedness Coordinator of a
+
SITE AREA or GENERAL EMERGENCY.
i l 2. The NAWAS is a direct, protected telephone land line with
! the handset installed in the Control Room.
- 3. Picking up the handset from its cradle activates a response
' at the State Warning Point and St Lucie and Martin County Disaster Preparedness Offices. The Nuclear Plant Supervisor I
(Emergency Coordinator) will advise the personnel on the other l end of the system, in a coded message, of the conditions at
- the plant. He then places the handset back on its cradle, as j this is the only use for it during an emergency. His message j will activate the required state and local emergency teams.
i
- 4. The procedure for reporting an emergency via NAWAS is summarized l in E-Plan Implementing Procedure 3100021E, Duties of Emergency
. Coordinator, and described in detail below.
i
- A. In the event of a SITE AREA EMERGENCY or GENERAL EMERGENCY incident, the following reporting procedure will be used
i . (1) The initial report will be handled over NAWAS by code.
(2) .The followup data will be handled by LER or telephone.
Provide the data on Emergency Information Checklist, E-Plan Implementing Procedure 310G021E, Duties of Emergency Coordinator.
/R1 (3) The following code name will be used to identify the /R1
. geographical location of the St Lucie Plant:
^
St Lucie Plant ST. LUCIE ONE 9
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Page 9 of 10 EMERGENCY PIAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 1 ON-SITE SUPPORT CENTERS i
- APPENDIX (cont) 1 A. Use of the NAWAS System (cont)
- 5. Classifications i The classes of Radiological Emergencies are described in E-Plan
,' Lnplementing Procedure 3100022E, Classification of Emergencies.
l
<! 6. Low Population Zone A. The Low Population Zone will extend outward from each nuclear power plant for a radius of five (5) miles, and shall be segmented into 22-1/2 arcs and will be lettered A through R (excluding I'and 0) for the 360 of the compass.
B. Each area is divided into SECTORS beginning at the center and extending outward in mile increments One through Five.
Contaminated area, extending outward from the nuclear plant, will be located and reported as discussed in E-Plan Implementing-Procedure 6, Radiation Release and Dose Projection.
B. Use of the Local Government Radio (LGR) i 1. The LGR is used, unless inoperative or unavailable, for maintaining j communications with various state and local disaster preparedness
, ! personnel. Messages are transmitted and received on frequencies allocated by the state Bureau of Disaster Preparedness. After initial NAWAS notice, detailed reports shall be by LGR.
1 4
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- 2. The LGR control unit is installed in the Control Room.
C. Use of the ENS (OFX) Telephone Network
- i
- 1. Within one hour of the time that the Emergency Plan or any part of the. Emergency Plan is implemented the NRC shall be notified and an open, continuous communications channel established using
- the NRC ENS circuit (red phone) . The Nuclear Plant Supervisor (Emergency Coordinator) shall be responsible for assuring that this
< notification 'is taade.
, 2. To initiate a signal to the NRC Operations Center, remove the handset from the receiver.
4 3. When the NRC Duty Officer answers, identify yourself as " Florida i
Power & Light, St Lucie Plant".
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Page 10 of 10 EMERGENCY PLAN IMPLEMENTING PROCEUDRE NO. 3100032E, REV 1 ON-SITE SUPPORT CENTERS APPENDIX (cont) i C. Use of the ENS (OPX) Telephone Network (cont)
- 4. Make the notification.
- 5. Maintain the line open and manned until allowed to terminate j the call by the NRC Duty Officer.
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, Page 1 of 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100027E, REV. A i 1.0 TITLE:
l RE-ENTRY
- 2. APPROVAL:
Reviewed by Facility Review Group July 25, 19 75 Approved by K. N. Harris Plant Manager July 29, 19 75 Revision 3 ,iteviewed by Pac 111ty Review Group,tiu.A s,+u 19 d[
Approvedgby/,///jd. - ,
eg. M. P. Power Resource #/4/c4 K,l9 #7 Revision 4 evi ed by Facility Review Group ttiv 1 3 19 8/
Approved by/ N P. Power Resources A J,19 #/
I 4
3.0 SCOPE
3.1 Purpose This procedure provides guidelines for the sele ~ction of the Re-entry Team members and provides instructions to follow during re-entry.
3.2 Discussion 3.2.1 Re-entry into an evacuated area shall be made only when authorized by the Emergency Coordinator as follows:
- 1. To ascertain that all personnel who were in the affected area have been evacuated and to search for unaccounted for personnel.
- 2. To rescue any injured or trapped personnel from the affected area.
- 3. To perform operations which may decrease the severity of the emergency.
- 4. To determine the nature and extent of the emergency and the radiological conditions.
- 5. To establish definite personnel exclusion area boundaries.
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- Pagn 2 of 6 s FLORIDA POWER & LIGHT COMPANY i EMERGENCY ?LAN IMPLEMENTING PROCEDURE
- 3100027E, REV. 4 3.0 SCOPE (Continued 3.2 (Continued) 3.2.2 The Emrtrgency Coordinator should select individuals with appropriate qualifications in First Aid, Operations, Health Physics, and Maintenance for the Re-entry Team.
j 3.2.3 The initial entry of the Re-entry Team, and all subse-
! quent entries, until radiation areas have been properly marked, shall take place under the supervision of the
. Radiation Team Leader.
r 3.2.4 The Re-entry Team Leaders should be fully briefed concerning the nature of the emergency. Information for these briefings will be obtained from the applicable available sources including current operating records, interviews t with evacuated employees, and surveys conducted by the
' Radiation Team.
3.3 Authority This procedure implements the St. Lucie Plant Radiological Emergency Plan.
4.0 Precautions
4.1 There shall be no re-entry into the area affected by the emergency
, after an emergency evacuation unless authorized by the Emergency l
a Coordinator.
j 4.2 All Re-entry Team members shall wear protective clothing, dosimeters, respiratory devices, and other protective devices as specified by i
the Radiation Team Leader.
i 4.3 The team members should not deviate from the planned route, unless required by un-anticipated conditions such as rescue, performing an operation which would minimize-the emergency condi-tions, etc.
4.4 If the monitored dose rates encountered during the re-entry exceed the limits set by the Emergency Coordinator and the
! Radiation Team Leader, the Re-entry Team shall return to the area i from which they were dispatched.
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- . Page 3 of 6 1
' FLOR 1DA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100027E, REV. 4
4.0 Precautions
(Continued) i 4.5 The following guidelines for emergency exposure of personnel shall be followed during the re-entry operation:
4.5.1 The Emergency Coordinator and the Re-entry Team Leaders shall make every effort to minimize re-entry personnel exposures, utilizing radiation survey and monitoring devices, protective clothing, breathing apparatus, and other special equipment as required.
4.5.2 Under emergency conditions not requiring action to prevent serious injury or a catastrophic incident,
, Re-entry Team personnel exposure in excess of 10 CFR 20 i limits may be authorized by the Emergency Coordinator,
! but shall not exceed 5 Rem whole body exposure.
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4.5.3 A planned emergency dose to prevent serious injury or to prevent destruction of equipment which could result t in serious injury should not exceed 12 Rem whole body dose.
I 4.5.4 Under emergency conditions where immediate action is necessary to prevent serious injury or a catastrophic incident, Re-entry Team members' exposures authorized by the Emergency Coordinator, wit > the consent of the
, individuals to be exposed, should not exceed 25 Rem whole body expos 6re, except for life saving actions.
4.5.5 For life saving actions, an individual may receive a dose of up to 75 Rem whole body exposure.
4.6 A Re-entry Team shall consist of at least two persons.
5.0 Responsibilities
I 5.1 The Emergency Coordinator has the retsonsibility for authorizing re-entry into an area after it has been evacuated. It shall be his responsibility to select qualified personnel for the Re-entry
, Team and make clear what their assigned duties are prior to re-entry.
5.2 The Radiation Team Leader shall be responsible for the supervision
. i of the initial entry into an evacuated area, and for all subse-quent entries until radiation areas have been properly marked and a l safe route determined. He shall also make recommendations to the l Emergency Coordinator as to the expected doses the Re-entry Team
- personnel will be subjected to and the feasibility of attempting re-entry into a given area.
i Y
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. Page 4 of 6 i FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN DIPLEMENTING PROCEDURE
- 3100027E, REV. 4
5.0 Responsibilities
(Continued) 5.3 It shall be the responsibility of the person appointed Re-entry Team Leader to strictly follow the orders given to him by the Radiation Team Leader and at all times to protect the members of the Re-entry Team from possible injury and excessive radiation exposure.
6.0
References:
6.1 St. Lucie Plant Radiological Emergency Plan 6.2 St. Lucie Plant Radiation Protection Manual 7.0 Records and Notifications:
j Detailed records of all significant actions of the Re-entry Team shall be recorded by the Emergency Coordinator.
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_, Page 5 of 6 j FLORIDA POWER & LIGHT COMPANY l EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100027E, REV. 4
8.0 Instructions
~
8.1 The Emergency _ Coo _rdinator'5r the Radiation Team L_gader ._ ._. --
_or their._ designee shall: _ __ _ _ _
, 8.1.1 Select at least two qualified persons to form a Re-entry Team. One of the members shall be qualified
- in Health Physics procedures.
! 8.1.2 Brief the team members concerning the nature of the lt emergency and the possibility of hazards being present.
j 8.1.3 Instruct the team members as to what is required of them t while in the emergency area. This may consist of the
! following:
- 1. Search for injured, trapped or unaccounted for
.
- personnel.
- 2. Operate equipment as needed
- 3. Determine the nature and extent of the emergency and I radiological conditions.
i
- 4. Establish definite personnel exclusion areas and i access routes.
lf 8.2 The Radiation Team Leader shall:
i 8.2.1 Evaluate the emergency to determine the possible dose rates l* and stay times. Refer to Step 4.5 of this procedure for
, guidelines.
8.2.2 Supervise the initial entry of the Re-entry Teams into the
,I area of the emergency and any subsequent entries until
!' readiation areas have been properly marked.
i 8.2.3 Based on the information available, select a route for the Re-entry Teams to follow into the affected area.
l1 i
8.2.4 Assure that all Re-entry personnel are properly equipped
- l; with protective clothing, high range dosimeters, low range ll dosimeter,TLD, rest.iratory devicata, and other protective jj equipment as required.
'I 8.2.5 Specify self-monitoring and decontamination procedures for the Re-entry Teams.
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Page 6 of 6
- FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMILNTING PROCEDURE
- 3100027E, REV. 4 ,
8.0 Instructions
(Continued) 8.3 The Re-entry Team members shall:
8.3.1 Wear protective clothing and other protective devices as specified by the Radiation Team Leader.
8.3.2 Unless unanticipated conditions are encountered, follow the pre-planned route into the affected area,
- and perform the assigned jobs quickly and safely.
8.3.3 Monitor the dose rate along the route followed, and identify high radiation areas.
I i 8.3.4 Frequently observe their dosimeters and withdraw to a safe area before established dose limits are received.
8.3.5 When re-entry is completed, follow the self-monitoring and personnel decontamination procedures as specified by the Radiation Team Leader.
8.3.6 Record and report to the Emergency Coordinator or his designee the radiological conditions and extent of damage l
in the affected area.
4 8.4 The Emergency Coordinator and the Recovery and Restoration Team Leader shall evaluate the existing conditions and plan further l actions as required.
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Page 1 of 20 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100022E, REV. 9.
4 i
l.0 TITLE:
CLASSIFICATION OF EMERGENCIES
2.0 APPROVAL
Reviewed by Facility Review Group August 8, 19_75, Approved by K. N. Harris Plant Manager August 19_25 Revision 3 RpyiewegbyFaciieyReviewGroupMW4104tf 19 8/
Approved by _//_ /_//_//M-V.P. Pwr. Res. //dic 4 2-(, 19 [
i Revision 9 R ewe b Faci 1Jty Review Group M a.1af 19 P/
Approved by_ M F V.P. Pwr. Res. M 'Z., 19 P/
l
3.0 SCOPE
3.1 Purpose This procedure provides instructions on the classi- /R9 fication of emergencies at St. Lucie Plant.
3.2 Discussion
. In order of increasing seriousness, these are:
Unusual event Alert Site area emergency General emergency A gradation is provided to assure fuller response preparations i for more serious conditions.
3.3 Authority
= This procedure implements the St. Lucie Plant Emergency Plan._ ...-.S -
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, Page 2 of 20 FLORIDA POWER & LIGHT COMPA.W ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100022E, REV. 9
3.0 SCOPE
(Continued) i
! 3.4 Definitions 3.4.1 Unusual' Event - This classification is represented 'tnr Off-normal events or conditions at the plant for.which no sig _
nificant 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-l tion of the level of safety of the plant combined with a J potential for limited uncontrolled releases of radioactivity j from the plant.
f 3.4.3 Site Area Emergency - This classification is composed of
} events which involve actual or likely major failures of
. plant functions needed for protection of the public combined with a potential for significant uncontrolled releases of radioactivity from the plant.
3.4.4 General Emergency - This classification is composed of events which involve actual or baninent substantial core
{'
degradation and potential loss of containment integrity combined with a likelihcod of sign 1ficant uncontrolled l releases of radioactivity from the plant.
I* 4.0 Precautions i
4.1 Conflicting Information When apparently conflicting information is available, the condition i shall be classified at the most serious level indicated.
4.2 Judgmental Decision If, in the judgment of the Nuclear Plant Supervisor (Emergency
- Coord1nator), a situation is more serious than indicated by
' instrument readings or other parameters, the emergency condition j shall be classified at the more serious level.
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Page 3 of 20 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCI PLAN IMPLEMENTING PROCEDURE f
- 3100022E, REV. 9 l,
1 I 5.0 Responsibilities i
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 Supervisor 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.
i j 5.2.3 If an emergency has been declared the Nuclear Plant /R9 Supervisor shall become the Emergency Coordinator and retain this position until relieved.
6.0
References:
4 3 6.1 St. Lucie Plant Radiological Emergency Plan i
6.2 E-Plan Implementing Procedure 3100029E, Duties of Individual Discovering Emergency Condition
. 6.3 E-Plan Laplementing Procedure 3100021E, Duties of Emergency
! Coodinator i
! 7.0 Records and Notification t
The basis for classifying an emergency condition shall be recorded.
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Page 4 of 20 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100022E, REV. 9-
8.0 Instructions
l 3.1 The Nuclear Plant Supervisor shall initially classify a
- situation within 15 minutes of the time he has become aware of it. The initial classification shall be made on the basis.
- of readily available observations and shall not rely on laboratory analyses, measurements, or calculations which would require more than 15 minutes to perform.
- 8.2 If subsequent information of a more detailed nature (e.g.
! sampling results) becomes available after the initial classi-I fication has been made, the event shall be reclassified by the Emergency Coordinator if appropriate.
I
- 8.3 The Nuclear Plant Supervisor shall classify events in accordance
! with the attached Classification Tables. The event shall be ,
i classified by matching the actual situation to the one most closely approximating it in the tables.
l 8.4 Classification Tables are provided for the following categories:
- 1) Primary Depressurization
. Miscellaneous
- Abnormal Primary Leak Rate j Abnormal Primarq/ Secondary Leak Rate i Loss of Secondary Coolant I-
- 4) Accident Involving Fuel
- Fuel Element Failure j Fuel Handling i
t 2) Abnormal Radiation, Contamination of Effluent Release Values
{
4 Uncontrolled Effluent Release High Radiation Levels in Plant i
- 3) Fires Lasting More Than 10 Minutes
- 8) Degradation of Control Capabilities
,,f Engineered Safety Features l: Loss of Containment Integrity
- jj Loss of Alarms i
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h Page 5 of 20 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100022E, REV. 9 ' ,
8.0 Instructions
8.4 (Continued)
- 9) Hazards to Station Operation Aircraft Toxic or Flammable Gas Onsite Explosion Missile Turbine Failure
- 7) Electrical Malfunctions Loss of Power i 10) Security l 5) Natural Emergencies i
. Hurricane I
Tornado Water Level Abnormal I
i 6) Miscellaneous Events Conenminated Injury Abnormal Temperature Abnormal Shutdown i
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. _ _ _ . _ . . _ - _ . - _ . t-tage 6 of 20 1NIMANY DEPkESSURIZATiON Page 1 of 4 CLASS j gygy7 UNUSUAL EVENT ALEET i
N SITE AREA EMERGENCY CENERAL EMEkGENCY ,
MISCEli.ANEOUS A) Unplanned initiation of ECCS 1.ous of 2 of 3 fieston product (Eamergency Core Coolinit SYutem) barrier with potential for loss l
- 1. ECCS pumps running as indi- of the third !
cate4 hy motor ampa, g .
2, ECCS header isolat$on valves j open se ludicated by yelve (Any two of the foliowing condi- .
position tuJScation !!ghts, tions maist anJ the third in OR $mminent.)
B) Saf 5 or relief valve fails 1. Confirmed fuel clad damage.
to close
- 2. Confirmed 1DCA 1, Beactor coolant s_ystem (RCS)
- a. Indication of flow 3. Coefitmed contalument tute-grity breached and cannot be through pressurizer gestored, re!{e( valves as indt-cated on ti.e acoustic valve flow monitar, AND
- b. RCS pressure drope to
< 1600 pata. k9 l
- 2. h in Steam System ;
- a. Unusual decrease in I pressurizer pressure and Izvel with decreasing i Teve AND 3
- b. Abnormal drop in steam generator pressure to i lume than 500 psia, AND
- c. Visual or audible verif t- {
cation or steam relief lifting.
I ac m u t. CumpieteLesun.14.teaon. i. Complei. .ction. li. tea on the UNUSUAL EVENT C11ECKLIST.
GENERAL EMERGENCY CH CKLIST.
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! Page 1 of 20 PRIMARY bEPRESSURIZATION g Sheet 2 of 4 i CLASS ERNT UNUSUAL EVENT ALERT SITE AREA EMERGENCY Gl.NERAL EMERGENCY l
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, ABNORMAL PkiMAR{ kCS leakage greater than allowed lLCS leak greater than 50 gym -
i EEAK BATE by Technical Specifications IDCA greater than cepecity of & release has occurred or is in primary to atmosphere charging pumps I i
' 4. RCS water loventory balance proggene geaulting ins ,'
indicates
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(5) Charging / letdown mimmatcli (1) Unusual decressa in pres-
- l. greater ! gym un1Jentified backe4 up by RCS wates IDCA Dose Calculation EPIP leakage, OR suriaer level and pressure 310003)E Appendia B worksheet Inventory balance indicating with constant T(ave). AND
- 2. greater than 10 spa Ident4- > 50 Crit and <lu spa (2) Makeup rate greater than values in excesa of 1 R/HR
- fled leakage, & leakage, AND (whole body) or an integrated capac$ty of 3 charging dose of SR (thyroid)
, 5. Inupaction reveals any BCS (2) Containment or plant veut pumps (132) gpa) AND radiation proceau monitor E9 pteasure boundary leakage, (3) Containment pressure >2 reading above nuamal. pois, or containment radiation monitors tudi- i case above normal values. i
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Fage 10 ut 20 ACCIDENT INVOLVING FUEL
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I UNUSpy. EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY i
! FUE1 EL DtENT Fuel damage ludication Severe loss of fuel claJJing Cure Jamage with inadequate core. A release has occurreJ OR is l fall.URE including coolant pump failure cooling determined byg in progress resulting tus A. Letdowa $odine process awq$$or leading to gross fuel fatture Loca Dose calculation alarm fo}1 owed by ,
- 8. Coqfirmed $CS sampip (odicat{pg (gggCS1-131 activity > EPIP 3100033E Appendia B wusk- .
()) 1.etdown todine process 275 uC1/m1, sheet values in escene of I a/um i
- 1. Coolant activity greater monitor alarms, AND. (2) ECS temperature within 20" (wholabody) or an integrated i tha4 the Tech Spec limit for (3) RC4 1-131 octivity > of T(mat), AND, June of SR (thyro 1J) todine spike Figure 3 4-1,$N9 275 uC$/ml (3) g,oop ay >Mog
- 3. Coolant activlty greater than R3 100/E uct/ gram specific act; FUEL HANDLING Fuel handling accident which Halor Jamage to spent fuel ACCIDElft results in the release of radio- in containment or Fuel Handling i
activity to containment or Fuel Building Handling Building L (1) Step increase in the (1) Ditect information from fuel readings of reJ1stion bandling persuunel 1sull- monitors to the plant veut cating that an irrmJ1sted i anJ/or in the fuel haud!!ng fuel assembly has been bu11 Jing,.MD l damaged and gas bubbles are (2) Damage to more than one '
escaping. AND fuel assembly, OR (2) Associated area or ptocess (3) Uncovering of more than one I monitor channels are spent fuel assembly in the alarming. spent fuel pit.
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the UNUSUAL EVElff CHECKLIST. on ALERT CliECKLIST on SITE AREA EMERCENCY , CENERAL EMERCENCY CHECKLIST.
- CHECKLIST
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ABNORMAL RADIATIOW. CONTAMINATION OR Fage Il of 20-f _ RFFLUENT REIEASE VAIUES l
CtAS6 i UNUSUA).EVIKF ALERT SITE AREA ptERGENCY GENERA 1. EMESCENCY EVENT UNCON1 ROLLED Radiological effluent Tech. Specs. A release has occurred or is tu A release has occurred or is A release has occurred or is
, EFFLUEFf REI. EASE I.imite exceeded progress that is 10 times the in progress resulting in: in progress resulting in
).FlanEeffluentmonitor(s) T.S. limit (as shown by sample / LOCA Dome Calculation EPIP LOCA Dome Calculation EPIP ,
onceed glarm setpolg[(9) syrvey) 31000338 Appendia a worksheet 31000335 Appendia B worksheet ;
(allowed by values in excess of 50 HR/uR values la excess of 1 R/ua 6
- 3. Confirme4 analysis results (or (whole body) 250 MS/HR (whole body) or an integrated k' gaseous or liguld gelease (thyroid) for 1/2 leur OR Jose of 5 R (thyro!J) ,
which esceads Techqlcol gpgel- 500 HR/liR (whole body) 2500 29 ;
(Acattog $1 mite. HR/WR (tlayro!J) for two sin at
! the ette boundry. )
e HIGH RADIATION tilgh radiation levels or high LEVELS IN PLANT '
airborne contamination which indicates a severa degradation '
, in the control uf radioac$1ve i materials (1) Installed radiation monitor-i ing stations inJ1cate abnormally high reJ1stion levels, OR , j, (2) Installed mist.orne particu-l t late or toJine activity -
monitore inJ1cate abnormally l i?' l high levels, AND ,l (3) Levels >1000 times norma! 8 are confirmed by area
! surveys anJ/or analysis of grab samples. I l
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GENERAL EHERGENCY I
. 1, 10SS OFl'outu 1.ous of of{-ente power or loue of on-ette AC pouer capability Iose of offette pyw.1 =yd loss Buse of offuite power and o{ all onsite AC power loss of onsite AC power
___45 minutes
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i I Drop in A and B DC beu ou voltaJeu to ( 70 volta, '
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'} Sheet 2 of 2 i
N UHYSpAL EVENT f g ALERT SITE AREA EMLRGENCJ CENESAL EMERGENCY i -
l OTutR CONN 8TIONS ), A plant shutJuun le required itse Technical Suppurt center 1. The F. mas 8sncy Centers are Aa event seenttlug la escalative
'BEQUIRIW3 IN- by Techalcal Spec {f{ca$jongj AND/OR Hear Site Emesgracy activateJ; AND. of the Emergency Classificattua CREASED AWARE- OR Opgratione Fecility sta act$vated 3. tiunitoring Teams ese to General Emessency uith NESS 2. The plang is etaus Joun spiJer for otbst St au drill purposes. mobiliseJ3 AMD. lessiamat Substantial cure Lamase -
abnornal condit ione (e.g. . 1. A precauttuaary pubtle anJ poteattel for setease of asceeJing coolJoua gateg oT notification to maJe cua- lange asuvate of saJioactivity primary system pipe 8: recks' cesalag an abnormal plant la a short periuJ of time; such 39 que (oun4 .jpring opeystlina)t condition for other than ass
, l 1.1DCA uith f atiuse of RECS.
- 2. Imes of SeconJasy Heat Stak.
- 3. SustaineJ statica blackout l witt Jose of secondary B. eat i stuk.
- 4. Failuse of containment tient removal systems in the later ' ?
stages of as acc!Jeut result-lag la loss of containement.
li l
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- 4 Page 1 of 26 FLORIDA POWER & LIGHT COMPANY f ST. LUCIE Pi. ANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100033E REVISION 1
- 1.0
Title:
LOSS OF COOLANT ACCIDENT DOSE CALCULATIONS
2.0 Approval
Reviewed by cility Revie gGroup March 20 and 25, 1 98 Approved b _ /MrM 77 Vice Pres-Pur Resourcesh "M i 19 Rev. 1 Revi ed by FR M3y 12 19 0 f Approvedg by //// 8 fe 7w% ice Pres-Pwr Resources h L 191 Rev. Reviewed by FRG 19 Approved by Vice Pres-Pwr Resources 19
3.0 Scope
3.1 Purpose This procedure provides a method for estimating thyroid and whole body doses for the area surrounding the plant out to ten miles.
This procedure is intended for use by the Emergency Coordinator upon indications that a loss of coolant accident has occurred.
3.2 Discussion 3.2.1 The Emergency Coordinator shall estimate thyroid and whole body doses for off-site locations from one mile to ten miles if a loss of coolant accident has occurred.
3.3 Authority-This procedure implements the St. Lucie Plant Radiological Emergency Plan.
4.0 Precautions None.
5.0 Responsibilities
The Emergency Coordinator or his designee has the responsibility for making whole body dose rate estimates and calculating integrated whole body doses.
The Chemistry Department representative shall make refined estimates upon arriving at the scene at the direction of the Emergency Coordinator.
- - - - - - -- - - . . ~ . - _ . _
Page 2 of 26 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100033E REVISION 1 6.0
References:
6.1 St. Lucie Plant Radiological Emergency Plan 6.2 St. Lucie Plant Radiation Protection Manual.
7.0 Records and Notifications:
Detailed records of meteorological conditions used to estimate doses, and the estimated thyroid and whole body doses shall be kept on the attached worksheets. As deemed appropriate by the Emergency Coordinator, the off-site authorities shall be notified of:
- 1) Meteorological conditions (wind speed, vind direction, stability and precipitation).
- 2) Projected thyroid and whole body doses at 1, 2, 5, and 10 miles, and
- 3) Whether default values of actual measurements were used for dose estimates.
t i e
Page 3 of 26 FLORIDA POWER & LICHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN DfPLEMENTING PROCEDURE 3100033E REVISION 1
8.0 Instructions
8.1 The Emergency Coordinator shall, upon the initiation of an event which is determined to be a loss of coolant accident, project the
, thyroid and whole body doses in areas surrounding the plant as i follows:
l 8.1.1 The dose rate as measured by the post-LOCA radiation
- monitor at the shield building wall shall be determined and recorded.on App. A . The monitor reading shall be used to further categorize the event in accordance with the following
Initial Post-LOCA Category of Monitor Reading LOCA
< 30 mr/hr Case A 30-100 mr/hr Case B 100 mr/hr - 1R/hr Case C
> 1 R/hr Case D This category shall also be included on App.= A . If it has been determined that a Case A LOCA has occurred, doses will be low and no further estimates are required.
4 8.1.2 Determine stability class from the temperature difference between the 200 foot temperature sensor reading and the 32.0 fo. temperature sensor reading from the meteor-ological tower (i.e. 200 foot reading minus 32.8 fcot reading). This value should be an average for at least a fifteen minute period. Record this value on Appendix A. R1 8.1.3 Determine the stability class from the following Table based on the temperature difference measurement:
AT(from 8.1.2) Stability Class
< - 1.6 A and B
-1 5 to - Os5 C and D
> - 0.4 E and F i
Record the stability class on Appendix A. R1 l
NOTE: If temperature difference measurements are not avail-f able, then a default value for stability class is required.
During daytime assume C and D stability and during night-time assume E and F stability. Record the stability class on App.. A, and note that it represents a default value.
%~ . . _ . _ _ - . _
. -.y-w- ----.eg..p, - - - - ,we yv-r---c,.g- g 4 -.e m - .-e - . . . . , ,
Page 4 of 26 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PIANT UNIT NO.1 EMERCENCY PLAN IMPLEMENTING PROCEDURE 3100033E REVISION 1
8.0 Instructions
(cont'd) 8.1 (cont'd) 8.1.4 Determine the average wind speed over at least the most recent fifteen minute period using the output of the wind speed sensor at the lower level on the meteorological tower. Record on App. A.
NOTE: If the lower level sensor value is not available, use the upper level sensor value and note on App. A. If neither sensor output is available, assume a default value of 5 mph during daytime and 5 mph during nighttime. Record this value and note on Appendix A that it represents a default __ _ R1 value.
8.1.5 Determine the average wind direction value over at least the most recent fifteen minute period from the wind direc-tion sensor at the lower level of the meteorological tower. Record this value on Apo. A. If the lower level value is not available, use the upper level sensor value and note this on App. A. If neither sensor output is available, record "ALL" for wind direction on App. A.
8.1.6 Select the thyroid and whole body time-dose-distance l tablescorresponding to the meteorological conditions '
recorded on App. A f' rom Tables D-1 through D-18.
Record the dose factor on Ap'p . A - based on the following:
1 LOCA Type Dose Factor Case B 1 Case C 6 Case D 60 Case B dose estimates are read directly from Tables D-1 through D-18. >For Cases C and D the table values are multiplied by the dose factor.
8.1.7 Position the overlay, Figure D-1, with the " PLANT" reference point over the center of the' reactor containment building on a map of the site area.,
Position the centerline of the overlay plume in the direction towards which the wind is blowing.
l l
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Page 5 of 26 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100033E REVISION L
8.0 Instructions
(cont'd) 8.1 (cont'd) 8.1.8 For each time period of interest (e.g. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 4 hours, etc.), record the dose information (Table values multiplied by the dose factor) on App. B. In order to account for wind shifts, the values should be recorded in the sectors adjacent to the indicated downwind sector.
If "ALL" has been recorded for wind direction on App. A then it shall be assumed that the estimated doses could occur in any sector.
NOTE: To conservatively accommodate any plume stabilizatr 1 effects that could conceivably result from a postulated potential stabilizing effect of the Indian River, those residents in sectors K, L, or M (between SW and WNW of the facility), should be considered to' reside at 1.0 miles. Thus, Tables D-1 to D-18 should be used at a 1.0 mile distance for these environs.
8.1.9 If there is a shift in wind direction of more than 450, the procedure shall be repeated.
l i
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__r_~:r-- _T-__ __ _ T_ _ _ _ __ _ _ - - _ - __ -
_ n- __ _ _ _ -
Page 6 of 26 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100033E REVISION 1 APPENDIX A DOSE CALCULATION WORKSHEET TLE INITIAL POST-LOCA MONITOR READING:
CATEGORY OF LOCA: CASE TDfPERATURE DIFFERENCE: OF STABILITY CLASS:
WIND SPEED: mph WIND DIRECTION:
DOSE FACTOR:
i L
~
Page 7 of 26 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 DiERGENCY PLAN IMPLDIENTING PROCEDURE 3100033E REVISION 1 r
APPENDIX B i
. CUMULATIVE DOSE DISTRIBUTION TIME RELEASE ASSUMED TO OCCUR:
TIME THROUGH WHICH THIS DISTRIBUTION APPLIES:
Thyroid Dose Whole Body Dose Met Station Downwind Distance Downwind Distance Wind Direction Downwind (miles) (miles)
(As Read) Direction 1 2 5 10 1 2 5 10 180 N ALPHA 202.5 NNE BRAVO 225 NE CHARLIE 247.5 ENE DELTA 270 E ECHO i 292.5 ESE FOXTROT 315 SE GOLF 337.5 SSE HOTEL 000 S JULIET 022.5 SSW KILO 045 SW LIMA 067.5 WSW MIKE 090 W NOVEMBER 112.5 WNW PAPA 135 NW QUEBEL 157.5 NNW ROMEO
. - . - ~ - - .- .- - -
TA BLl' D-t .
a
'- ~ '0VEldlAND DISPfR$gon " - - " - - ' - - ' -- - - - -
'Page 8 of 26 PASOUILL ST Aalllif CL ASSES a E a
- WlHDSPEEDal 8'Pil DisTANEE (I*iLE$)
T illE 1.4Q 2.00 3.00 8.00 5.00 4.00 7,00 4.00 9.00 10.00 ;
22 nin 2.aE-02 0 u, 0. O. O. Q. 9 O. O.
3,.ft!N - -"y'iE-02 0; = 07-~ ~~0. - -' 0 O, -~0 ,- '- 0 .-' " 'c. 'O.
45 HIH 5.7E-02 q.3E.03 0, 0, c. 0.
~
O. c. O, O. ,
I HR 0 HIN 0.0E-02 7 2E-03 0 O. O.
O. e) . O. c. O.
j - -- I HR 30 HIT "- 8.0E l .4r-02 6.0E-03 "2.5E-03 ~0 9. O. c. O. O.
i 2 HH O HIN ,,,8.20-06 8 7E-02 9.7E-03 5.9E?03 2.8E-0}
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, , , 0. 9. O. O, c.
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2 HR 30 HIH 1.3L-01 1.9E-02 1.1[-02 7.4E-03 5.7f 03 3.lE-03
- 1.5E.03 c. 0, C. i 3 et ~ 0 Mitl'---- 1 ;5E-O l--'2; 2E*02 li 3E-0 2 ~ 9. l E- 0 3 6,7E-03 '5.lE-03"),5E-03' l.8E-03 0 0 i 6 HH 0 HIN 2.4E-Ol 3.5E-02 2.lE-02 8.'iE-02 e.5E-03 1,2E.02 7.0E-03 6.5E-03 5.6E 03 ~4.8E-03 7 lan 0 HIH 2.6E* 0 4 3.0E-02 2.3E-02 l.7E-02 1.3E-02 1.lE-02 8.9E-03 7.5E-03 'L 6.4L-03 5.5E 03 10 HR -- O' idlN -3,2C-01 4.0E-02 ~2.9E 2.~2E-02l 7E-02"l'.4E-02t.2E-02 1.0E-02',a.9E-03 7.8E-03 12 HR 0 HIN 3,5E-04 5.2E-02 3.2E-02 2.aE-02 1.9f-02 s.6E-02 1.3E-02 1.2E-02 1.0E-02 9.0E-03 l 14 hR 0 MIN 3.8E-04 5.5E-02 3.4E-02 2.AE-02 2.0E-02 3.7E-02 3.8E-02 1.2E-02 1.1E-02 9.8E-03
- - --- 16 H H "--- 0 " n ! N $0E*01 S;9E-0 2-1;7E-0 2 -I;7E-02 '"'2.2E-02 ' l .8E-02 1.5E.02~ ' l . 3E-02 't.2E-02 1.0E-02 20 HR 0 HIH 4.SE-01 6.6E-02 'e.lE-02 3.tE-02 2.5E-02 2.0E-02 8.7E-02 1.5L-02 't.3E-02 1.2E-02 , l 24 HH 0 HIN 5.0E-OS 7.3E-02 a.6E-02 3.eE-02 2.7E-02 2.2E-02 *l.9E-02 8.7E-02 8.5E-02 1.3E-02 I
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- f i
} %
I a as as N as na as na ,ns N N
as S O t O o O O O O O O O, O e O e e is e e is s- a :s e e L/
e 4 lia,6 M LaJ I ta,# W taa ed .W has ' W O 8 M e
.e e . . .
. e. e ,'-=e Mie, ,Ne
@ P=
.Pe Ml P.
y O O O O e O == no M e
Ps pr w e
w art o
I,e, N
l l
~
. M ~ ~ ~ N ~ ~ ~ ~ ~ N O s O O o O O O O O a o O O 8 9 3 g g p 3 e +
3 g o w. w L,8 w w w w- w w w eo .e n. n. O N e Ni on L.3 P ~. ,.
cc t e e o e e sa e e.ie e. .e
- ao O O O O O O N ir .e M .e w o. .ed .e
, I l i
. N N ~ N ~ N N ~ ~ N ~
OO O O O O O O O O o O O O D 4' t S 4 9 et E 8 re p 3 e8 an,a - la.A laa Lad ,
tad w w! w ad te,a w 4 4 8 pt 80 M P == en & O 4 3 e e es e e e. e ,e . =e 6 e .Pe as.s .o. ee e e
, O O O O O .* N M W W tft 4 e .e >= e %
l I i I 8 N MS N N N fte N N Me ns me N O 6
- O O O O O O O Oe O O O O
, O e {s e e as a s is ai 6 te e a ea 4.a w i.a a.a w w w w w ins ma u
! Pm 9 O id1 4 N . M P= . O w ==
, e . e e o e se e e .N. y e ie e O.
l . O O- ..O O ie
N M at to e P= O su e e l
no ne ne l l \
0 f. N N N N O '
O 8 O O O O O O O O O po O O f = O 9 18 0 0 't 0 0 9 0 e le W O
[
ee *5 Lad nad Lee laJ 1.ad Ina Ina tne tad be ha tad 4 8 EF"' =e - EB en == P= O == ne ~
j u a e e e e le e- e ee en. e. l. e e o e, me.
2e O O. O O e e nn p= p= P = ee .=
L E9 l
me. a. taA e Z,, K3 En me 8 0 N N Rs N N == .e. == es me == ==
we >= **. so :: O s oe iO O O O O O O O O ,O O O l cr. ; u e .e n. taa e O s e le 4 w* Z EL .A E d 9 *8 is hae-e the w e
ta,e e is taJ a e le e a and led tad had ed ms nna 4 8 tea ane u em 8 til O in *= 4 lit 0" . N M M e y1 P=
Q an. , c e. .
in X e a e e *
- 6e o e ie e e ;e e, e le e e ea sg a >= a =e O O O O O M tFl e Ga =e W Qt naa e* P= Q E Ql I Xll3 me' tad tne 0 V Eng .,,J, W tae 3 N N N =* == ee == ee me we == .e '. -
% Q-* me G. t O 8 O O O O C
- e. . =. e O X. . c. i a a is O. O. is O. O. :. O. , a O. O. O.
Q == set at C >= 9 e B taa kad lad led led End nad led taJ ens t,# ta,a gg u .,s em Z et 0 WO F F* W r= == at W% P= et F ,0 N M
, w 3 tg up me == g 3 e e e e le o e le e e le e e le o e Z .,A lae 3 Q 9 G .O O N ,=O E0 (Pa we == == .e == N as eg
== > .J e Q .,,a
- p.= em 9 P=3 MB me e me == -e .e me == == .* .ie .e.
I e3 = O t O O O O O O O O O in 2 O e s 3 .. i e e O. O.. e is O. O.
o.
, ea w w w w w w P=w w w wl. w s.J w w as M g = 4 N w e N ar p. mj O me w P.
g, B e e e = l*
- e ) e. e e Io e, e ie e o j - O C 4 4 =* .e .* >= N N N Me M M M t N e == == .e .= -e .e .e .= e .e e .e O S O O O O O O O O O O O. O O O O O 8 48 8 8 18 5 8 !S 8 8 8 0i O .8 0 t ee be tnd taJ lad tad las tad and laa hJ 1aJ l tad led ha 1na N I AD N P= M P= O N N its ce Tl P= 7* W's O g e o e e o e e le e e 6e o e 4e e e O == ** M N P9 '9 w w WD Wt tft WD 4 P=
. O*O O O le
-e O
- .= -
O O le O
.e O O
.o .
O O
L.
O O O
O O
O O
O O
O g
C 3 e 8 0 8 3 4 <s.
- e. ei e. e . + g. %
laa tai w laJ t taJ LaJ 1ed ta,A l.2 w '
. n td, .aa 1.a3
.ee .8 - O - e O .inA M ,I.,A .laJ ,l - O O ~
i s = ie *
- 8* * * ** e .. *' e te o e as g e a P as e ip .e- == -e se ne na e
d e e e-o me me e e . .
e .e e me ==
5 E 5 $ $ $ $ $ $ $ $ $ $ - $ E $
I 6 : I e ad O Itt OL O O O O O O O O O O O O na 89 C3" M 389 h3 9
.E. S3 *
>= 5 E. E E E E Q". E E E CC (C CC E
- - Z. Z .,a. e. .-i 3 * .a-i 6 .
s
- " Af no M 4 P= O A8 Er 4 O. *F
= => m m NgN g O
-,-4.-
( TABLE D-6 Page 13 of 26 IHY903D DO5f IREH)
BT. 1.UC)[ EHEHr.ENCY PLAN
'-'- ~
OVERE4 0 pl0PERalDH
. PA40UILL STABILITY CLASSES C & D f HINDEPE[ps4 HPjl
{ DI$i4HCE IHILE6[ )
71HE 1.00 2.00 3,00 a.00 5.00 6.00 7.00 s.00 9 00 10.00 I 22 HIN 1,9E-01 4.6E-n2 0 9. O. ~0. E. C. O, O. 1 1 l
.40 HIN 2;ag-gi 673F02775E;E27.5E;04 0, 0, 6, 6 4, 6. l l
45 MIN 3.3E-01 9.5E-02 4.lE-02 2.lE-02 8.lE-02 2.9E-04 0 O. 9 O.
HR 0 HIH 3.9E-01 1.3E-0) 5.9E-02 3.?E-02 1.9E-02 1 lE-02 6.8E-03 2.5E-09 0 O.
~*- I HR J0 His gi6E30I l'ibE;0M;9E301 4!9F02 374E;02 3.5EIM l';7t;42 ITIE;02 777t;D)N2E;01 l 2 HR 0 HIN 5.2E-08 1.7E-01 9.2E-02 5.rE-02. 4.0E-02 3.0E-02 2,3E-02 13 8Ep2 1,5E ,02 1,2E-02 E
2 HR 30 HIN 5.7E-01 8.9E-01 l.0E-01 6.5E-02 4.6E-02 3.4E-02 2.6E-02 2.lE-02 8.7E-02 1.4E-02
~~3 NR 0 f11N 8slE-01 27tE301 1 TIE;DT 77tF02 4;9E;62 17E302 2!9t;02-~2;4E;02T6E;62 T 6E;02 6 HR 0 HIH 8.0E-Ol 2.7E,01 1.4E-01 9.cE-02 6.aE-02 4.8E-02 3.8E-02 3.lt-02 2,6E.02 2.2E-02 ll l' I HR 0 HIH 8.5E-01 2.aE-gl 3.5E.01 9.AE-n2 6.8E-02 5.lE-02 4.lE-02 3.3E-02 2.,8E-02 2.4E-02 l'
l*
-~10*HR 0 HIN 9 7E-01 3.2EE01 IT7E301- 1 TIE;DJ 7.7E;02 578E D2 4 6E;D2 378Ee02 3!2E;027.7E;02
',! .--- 12 H.. .R 0 HIH 1.0Et00 3.4f-01 1.0E-01, l.lE-ol adE-02 6.lE-02 a.9E.02 43 0E-02 3dE.02 2 dE,-02 14 HR 0 HIH $,lEt00 3,6E-04 1,9E-08 1.2E-04 8.5E-02 6.aE-02 5 lE-02 4.2E-02 3.5E-02 3.0E-02 6.7E 62 5D E;02 4.lEdO2 3 4EI 02 371E;02 if - I 6" HR U HIN ITID 00 3 7E;UI (.0FD'l -)T2E;DI T 9E;52 20 HR 0 HIrl 1.2Et00 4.lE-01 2.lf-01 1.0E.08 9.7E.02 7.3E-02 5.8E.02 4.7E-02 4.0E-02 3.4E-02 l
l} 29 HR 0 HIN 1.3E+00 4.4E-01 2.3E-01 1. '1E - 0 4 1.0E-08 7.9E-02 6.2E-02 5.lE-02 4.3E-02 3.6E-02 g l1 i
-i r
! / ;
l t 1
e e
3 .= .= a.e .
.e oe os o .o of a o o o .
O g 8 je (v
3 3 0 8l *A 8 -
4 o
- 0 end w w ena and tese tad 6.ma ,. e o -
O.I ee i
- . . . . . e. , . re N. .t .. e e s.
o o o oo o o o m. m #9 M ar my er er i e
- I I e
n l l l 4
6 !- I ei ,
-a, e = - = -
o ti ( o oe a .o o* O o o o is.4 se e I
- e; e a 0 e le s 3 i o o si i I *
- w w w wl w tas w
. . or m
e st at o
. l.
e o o o o o o l
3 f.
m m.
e.
m 6 m.
er c
== ar e.
e
(.
in4,.
o wt
- m.
ut g
- lo . i i l t
} g af l 3
.== r.* p.e g o eI e o o- r~ o of a o o a g oe e 4 si '9 8e 9 0 8 9 e 3 4.4 tad 5 :. And taJ I w had ns.a enA o3 o=t *e o N8 4 e egg e . . . . e' . .o. e e i e e. at. .. ee e o o os o o o a Er e to W1 in att en ,o
~
oa o o
.e l
. L =,t _ _ -.
o o8 8 et ci o o 8 IS Ol Ot C* O 3 Be is B 3 ee inJ tad 6i.a. taa nnJ taal Ine tad w In.# *
>= e . e N, o N, o- er 3 . .. . . . . m N. se = e. e e n. .e. e e o o ce o o o == ,N Ut we l.4 4 e e P.- P=
3 38 . o9 e o l
o o L
to o
.e o o
-e.
o
.e o
\
o 8 e8 e 8 9
lad f8 laa 0
nna i 0
6.
IS Led S S one
{t Lee B
ene 9
taa
. 4 9 e er p.4 ar sad ,
om o pte sue 7 ene e en e . .. e e. e- ee WD. e e e ae . .=.
== o o C o o o N les e e IW.e p Pm C ut. eur -
.4 e i i i g
=== C .":". ena l l !
re o es e. s .
== .e o o o o inJ. D= M 3 oB oe o o :o Ot o to o o o o o Zl ti rd3 4 13. and 8 o Sl 0l 9 i8 9l 3 ;3 4 + y e. * +
] Z. E .J & J 8 e GI ed and .na s los taa w w td m,a and .nad %# ** 8 M f 4rt f%s .u* Mg 4 l C u.
N, na;' L2 dL M 1 8 9 * * * . . ej
- j* et * , .i tr G.1 O. .) .
f%e s'r ! E go > a ee 9 o o o c3 o- N wt 4 e o ep on pe
- e c C?
Q taA E 4 see P=
ee Q
laJ ana 8 4-l l 1 }
y tea f Ia u9 3 .= =* - o o o o o o o o g Q C e.J 4. I 4 oO o o o o o o o o o eso the Z M et ** O O 8 C O O O 3 $ 8 { 8, +o
- 3.* *g * '=e= 0 +.
Os ** 4 4 Q ** 9 *O
< tr ' 4a '.,& t=< 2 M 9 5 9 nad and tea es nas Lad i tea te.4 s=*
ind e Mt er w h enJ . w e
H >= 3 an 53 * ** g e a. . e e se trt e e ,toe = = .. N en e ge o e ur um. e Z .J &7 3 O 9 O O O o N Wt P. EP .e .e == .*
l.
=== .= .e
== > A j t t l e- C .J l l l
>= *.* O l = o o o o o e o o o a 40" 3 oG O o o o o o ao o- o o*o o o o 9 e 9- * .= as- *
- ben * + so-
- 4 W3 *4 &na tnd laJ na La taa nne ind laJ nn.3 4 M 9 pe .La.d N M P.J P.J Ipm o . o .he 8 N er
- 11. 8
- en e . g. e e'
- 0*
i*
- 6*' *1 * * *
"'t o o o no .o N N N sti oO 8 ==
o e
Lo D o o o o o o
o o o o o o og o o o o v
o o
' o0
- I 6 0 == e- *= u. + +- ao= e= t g= w. o.= c'. .
kne laa nad tee 144 La.a naa tad the inJ lee nnJ Lad N st j. . tad . e o m e m e .e -
4-O e e4 e e e p. e. a. ee e4 e. e. e. .
. o to a N N N m m M 9 m es*
6 o et o o e o- o o
o *o o o o o i
o I
o o o a2 o ea e- +.
o o a o o o a 4
o oj o o o o
,e.,
- 8! n=6 La4 Las taa s.a w taa taJ w u taa 16 saa na n.a : Ia /
= e: o ut s * *
=
e ar.
er
- 1. o.
tre e
o
- i. N.4 p
M s.
P.4 3 o.
m e a. '
- le. hj
- e== es e r wt vt un p= r o e om . e- "*. Y.
E *2
- 2."
o 2. T.e e
T-
== .= ~Ze - e2 Ze
. 4 e 2* 2* 2 2"
e 2e o Z.
e T.
E E E Z Z Z Z E E E E E* Z, K Z Z
- f' I s a e ! 6 l A8 o Ut o o o o o o o o o* o o a. o
-4 * #ie* W W pm m e ene 9 a ;.
i = e, I l.
- 0
- l s l T M E E E Ej C Ci- - E i !"I t
. = = x 2 = z. .
- E-M 2
Ml M
=>i z e
e
= w N N .M e4 % o m, y e et e s 91 8 ? N i I I .
I I i-3,
/
%./
ew . . . % .
.w *e=w =em.- ' * ' * ' #
, y - * -e
g -- . _ _ - . . . . . . . . .
I I
N -e .e me me == e .e .e
) oe 8
g o o e o o os O o o o i
o9 l 8 'O O .
S 48 99 9' f8 e 8
- 8 1 ind nad nad taA anJ) naJ .' eaa w 1*J O 8 I W 4r .ind es s == pal Ws 40 . %1 Po e
.o I o e ed o e' e e e ie e. e .e op e. Ie e e O O o e O O e N N N N Aa. N N N
, ~
. ~ .e _ l_e _ _. I_ .e -
56 8 oe o- O ro o o no Of oa O ee s ;e o o-oe e; e ls e. e le a e O
e u ina w w. ins sa .a l ind w naal w M
in o. aes e. m e-1e W; m o **
e- mi e o
- I.
.='
e *
- a; e * .e e e e e e. e.
( O o o o O ses .e 1 N N sn N pa M M i G l l e
00 M .e == ee == == p== ee we 9
gg o; o o o O 08 o o o o
% O S O e e- e iins, o.
a e .e eI e e w
e e 4
w w w: ina Las ina e8 ea i.s tiv e .= wl m ? n.aa fts . M o 4 e a e e o e e e e ;e es e 4e e e' Ie e
- o o go 9= .* N N As M M M M M O O l
.e _ .* _
oe
, N o
.e O.
.e O
o o o O a o O o o oa o. e is e e is w w w, u a
laa .a w e
w e
e i1s.s u w w w o- f== M 4A
" P= 5- P89 4 M @ M W P= 71 *
- e e e se e e ?e ei e qe e e e e4 o o e o 4 .mo N fie M M M qO se e T e
3 .e we . .e me \
O B o of O so o o o o , o ,O o e In.
O 8 lt lad 8'
lad! lad B IE Lee 9 5 saa le nnJ 8g had t laA I IS nnA 8
laJ M 8
88
- O M 4 4 9 m tre l O* e l.ad
. N se roe l O* G e e o $e *
- 2 hJ e er o e o g e. e- e 6e le
- e B
O o o o e.* As M. De es e*W W W in W9 W9 1
.J .5
- ==.8 th. O tad [ ==
s== 8 6 ene ==> ase ens == ee e .=
t) W9 o Z{
W. 3= ==* et 2 e et O 4 of O M3 o o c o o e o cc u e s ee saa n.J nasi laa nas and naJ ln4 .e w tag saa naa tad
.O su & tr9 C o M E Er he did P=
N W U f .4 >= = e5 8 i eB 8
>= 3 cm e me- == 0i e a e e e ge e e e e e ie e e le e O*
e Z .4 w F C3 8 o e o ao e art- >= pe P= c e Do O*
- e. > .J l } }
- C l 1 l
.J
== == .e ==- === c o O o o o o o
>= *= 8 o O O O o W3 3 o8 o o O o O O O O O ta e is e- o- * *
- as- + *=
o O 8 4 5 B naJ tad lad nnJ w lad w and
.3 *8 inJ L.A Lad. taJ Ia.4 LaJ c'9 o o se N N N 9 4 Er
- M $ N in rat **t e e e e e o e e o en e le o e le e o tn. e
~
cm o na M k P=. e up .e ** .e == .= ==
l_ _
I I O O o
.* lO O o
o o
O O
O O
o o
o o O O o
O o
O O
e o
o o
O 4 * *= b O $ t0 3 8 e. e= e- =e. *
- ase *l * =o=
nae ns hiJ aaJ taJ Ia LaJ 1.4 6as iaJ aJ tad e 8 la.s sad L.as si f N N l p e3 N
- M ar its e e p e e N e e
in e
a e. eo e e le o e ;e o e ie fe O in G N N N N N s
f o o D o o 9 .m> O O O O o o o o a O or O O o O O O O O O O O o O O O Ot C S e :*= * * *** *= *= e= * * *Ln4 * *= * ==
- inA e naA la4 LaJ lad na LaA naJ &
_laJ i,a,J
.* .4 . M o M r.A .inJ e.a La- .n.a,J e
in O le
~.
e
.L.A la.a e
le e e g a ge e e ie e e .e o.
D* =* .* N iM M st' M @ at as in nrt M 4 4 T T T 2 2 Z Z 2
== .
2 me
.T
. 2.e .Z~
.e Z. Z- Z.*
e me == 2.e Z Z Z 2* E Z Z E Z Z E Z Z Z. E Z 8 l 1 6 1
- N 'o trl O O O o O o o 43 o o O o o
- } N et W "'1 781 i
l lea= 0
.ee 0
- >= 9 & E M G". M E C 2 C T M Z E l = ;c s x == z x x = x = z 3 '
- N N M e N o e @ o 4
- = N_ 4. w m N N
.. ]. . I F ... l. l i s .
I - . . . _ , - .
g -- .-- _. .- ._ _ _ . . _ _
D e r4 M N e .e se .= .e OO C O O O O O O O* O o O O O a is el e le et a :s s' e e e a W *e w u w w ws a w w. w w w w , h C O a wt Oi e e M. w wt irs: e .o re O *
-en 6 e o e e ie ei e e es e go og e te e e ,
W O O O O M O EP' == == .o .e l
. . .,, N, == .- ee _ .* .e .* _o _
og e3 9 o O} O to O. O O O O o O O tg 'S 9 I9 81 0 8 9 !4 99 5 e t 9 g,, o *8 na =J: mA l=9 a eaa ena naa n.d . an.a ind
'P= 0 ea rm, == m tag 9 e p a3* en .aJ.
gy O n.aa
=
4 e e se e ie e e l* e. e ie e, e ;e e e o o O O We (P . == _ == .o N N
. . ., ,,, _ _ _o .e _
O 8 O O O O O Os O O O. O o o O O 9 9 19 86 9 at B4 0 9 9* 9 9 9 9
- 8 nad LaJ 1 mal na&. taJ 1aA 6 tad laa taa 4.J ta laJ OO P= Ne W es e e O h.J
.. s== aw o,d e
$ e o e e f
ge et e trl a e e, e io e e . , e e O O O .= Pe ** == **t == N N N. ais N N
. M .o _ _ _ _ .e __ _ _
0 9 O e O
e i.
o O. O. o.
O ei e O O ti Cl Oe a i.
O O e
O e
h
- 3 haa ena led tea laA; lad led wl h.8 taa had w fe. 8 M O 4i P* E3 ==4 N W Ws lit =G Pe 96 w 3 e e o e pe ej e eo si o ee e e (e e e O O O ar L== N- N as fie- e%s as N to. O-e
, M Q
N O
e_
o O
O lo Ol O O O em O
L e
_e O
O
- O e o e is a e se ei e is 6 s .a e e \
e es w w w w w w wtes wP= L pawl c, w w w u ee e en art so == r%s .e- ris M wa tea e
- e * * *
- e Ie
- e &* +4
- le *
- T.a e O .* e se se #4 et> R. ! N pr. M sl o re est -
.4 O
= dh. z naa ee .e == -e .e .o == -e El Q st a.e 9 8 N, == .* .
taal >= see era- =* O I O t O O u g
O O o o *O c O O 'o
.e O O Cr. u 1u3 4- G. taA 5 O 5 8 9 .8 0 t it 4 a !B 0 t t 8
== 2* Cr. .Ai E. J 8 t ha s tas j tad naa tad tad ad ans ind nad te. e u., e .e O. L.ad . _aJ o ~ O M, s.aa h,e,s o 01 a. ,c. - M n naa l L.3 & *C E e 9
- e e e i e. e. e ie et e ;e es e e e et* tt e 3=. e *** O O O W3 == p%8 N f%s N M M M{ M et er er cl n.a er e- O s ca zg,4 a e. w we we og J ia ue e pat- . .* == == .e == == .e y c )c een A Z# O I o la o O O O O O le O
8 O
5 s1 le O O c c e
O a
q == m .2. et 4 0 O e e 9 19 D 8 a e le
/g O oe me .E e' Q t= B e B Lad taJ taJ &aJ nnJ lina lad lad i inJ ind w kJ taa lad tJ T' d:r v%, u 'a *= 2 ee e e ens e e #**' P= sp 4 4. sr == r=* es m == '
=
3
.4 cg as eo E
== t oa 8 e o r4 hO e
.e
== M ie M
M e
e e ie es art e
wt o *e art m e
e o
Q
>= > .J l I I I e c a g
l
== .e l
== e.
l
== .e l
.e
.e s
O 3 O $ o O O O O O O O O O O O 'c O O O O E Ip B B 18 4 5 14 4 e 4 8 te & 8 e3
- 8 Baa laJ b~ 14J LaJ ta.A nn4 laa la it . aaJ naJ laA la.8 laJ nae 4 P9 8 f%s 8% (V O* W *O hrt fJe N 4di i O o ee 4tl O 4, g o e e e Io e e le e 4e e. o o e O == N set er e art art e e re one P= aus O W*
O f C
i.
O Q
O I
O O O L.O O O
O I
O O O O
O O
i o
o O
O e=
O e=
e O 8 8 la e a re 8 0 is
- e. e. *. t e. .e.
ea ned ns a na.8 leJ - tea taJ lad
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--- - - 16 ~ H R 0-MgH 5.5E-o n- 170g-04 v.9E-05 5.3E-05 a.3r -05 ~ 3.5E-05 2.it-05 ' 2.4E-052.lE-05 1.aE-05 6.3E-04 1.2E-04 7.8E-05 6.lE-05 4.9E-05 a.0E-05 3.3E-05 2.a[-05 2.4L-05 2.lE-05 20 HR 0 HIH 24 hk 0 HIN 7.lE=0s 1.3E-04 8.7E-05 6.7E-05 5.4E.05 a.5E*05 3.7E-05 3.2E-05 2.af.05 2.4E-05 1 <
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. . . . . . .._ . . ... . . . _ _ . . . ... NHOLE BODY Dost (PEast Page 18 of 26 t ST. LuCIE Et1[HGENCY PLAN OVERLAND Dl5PER$10N EA3Qu!LL STABILITY FLA66E3 A $ 8 HIN05 PEED =5 HPH DISTANCE (HILEB) 2.00 3.00 4.00 5.00 6.00 7.00 8.0c 9.00 10.00 T itf E I.00
. . . . . . . , .. _-...... . ---- . . -....__ ........e.-.... .. --. . ..---. .---.-
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1.5E-05 1.0E-05 7.at-06 5.5E-06 4.0E-06 2.3E-06 3.2E-06 6.3E-07 9
. $ llH. 9 *till ..__ . $ .0E-05 s 9.5E-05 1.8E-05 1.2E-05 9.4E-06 7.tE-06 5,5E-06 4.2E?06 3.2E-06 2.2E-06 1,21-06 2 HR 30 HIH .
3 HR 0 HIH 1.lE-04 2.lf-05 1.4E-05' l.lE-05 8.8E-06 6.9E-06 5.4E-06 4.2E=0h 3.3t-06 2.7E-06
_ l.8E-09 3.9E-05.. 2.3E-05 .l.et-05 1.5E-05 1.2E-05 9.9E 06 4.3E-06 7.IE-04 6.lE-06
._..... 6 HR. ._0..HIH_
1.7E-05 8.qE-05 1.!E-05 9.4E-06 8.0E-06 7.0E-06 7 HR 0 Hill J.0E-04 3.0E-05 2.6E-05 2.tE-05
~
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14 HH 0 HIN 3.lE-04 5.oE-05 4.0E-05 3.2E-05 2.6E-05 2.2E-05 8.8E-C5 1.5E-05 1.3t-05 8.2E-05 0 HPl 3.4E-04 6.3E-05 4.4E-05 3.4E-05 2.8E-05 2.3E-05 2.0E-05 1.7E-05 1.5t-05 1.3E-05 16 HR
. ... 20 Hli ___0.HIH 1.9E?09_.7.2E-05_..q.9E-05_ 3.9E-05._3.2E-05.. 2.7E-05 2.2E-05 .t.9Er05 1.7E-05 1.5E-05 24 HR 0 MIN 4.3E-04 7.9E-05 5.5E-05 4.3E-05 3.5E-05 2.9E-05 2.5E-05 2.lE-05 1.4E-05 t.7E-05 l
l l _ _ _ . _ - - .. . . . . . . .
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I f ,f TABLE D-12 { { { '
... _ _ . .. ._ .. _ _., .. ._ ._ _ _ ._ _ _...... t*0LE 80DY DOSE (REH) . . .-
. Page 19 of 26 ST, LUEIE EME8GErlEV PLAN OVEBLAND DJ5PER330tl ..
. . . . . . . - _PA60UILL $7A811.!TY CLASSES A & B _.. . ....... . . . .
HJHOSPEEDep tifH i 9 D1)7AHEE (HILES) 4.00 2.00 3.00 4.00 5.00 6.00 7.00 4.00 9.00 10.00 i
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' 2 HR 30 MIN 6 lE-05 1.2E-05 8.7E-06 7.0E-06 5.6E-06 4.6E-06 3.7E-06 3.0E-06 2.5E-06 2.lt-06 3 HR 0 MIN 7.0E-05 1.4E-05 9.aE-06 7.9E-06 6.4E-06 5,3E-06 4.4E-06 3.8E-06 3.2E-06 2.FE-06
. . . _ 6 HR .. 9.11}H_ _1.tE-04._2.2L-05.__1.6E-05 ..l.2E-05..t.0E-05 .0.6E-06 7.2E-06 .6.1E-06 5.3E-06 4.7E-06 7 HR O.N{H l.3E-04 2.qE-05 t,7E-04 1.4E-05 1,lE-05 9.5E-06 a.0E-06 6.cE-06 5.9E-06 5.2E-06
~
to HR 0 HIN l.6E-04 3.0E-05 2.lE-05 1.7E-05 't.4E-05 1.2E-05 3 0E-05 4.7E-06' 7.6E-06 6.it-06
, 12 H8 .._.0 HIH _ __1.8E-09. ).4E-05.._2.4E-05. 1.9E-05 1.6E-05. 1.3E-05 .t.tE-05 .9.7E-06. a.5E-06 7.5E-06 14 HR 0 HIH 2.0E-04 3.7E-05 2.6E-05 2.tr 05 L.7E-05 1.4E-05 1,2E-05 1.tE-05 9.3'E-06 a.2E-06 16 HR 0 HIH 2.lE-04 4.0E-05 2.aE-05 2.2E-05 1.8E-05 1.6E-05 1.3E-05 1.tE-05 1.0E-05 6.9E-06 t .
! ..._ ... 29 H8 (L t11H_._2. 9 E-9 9_.9.5 E- 0 5 _3. 2 E - Q S _. 2.5 E- 0 5. 2. l E-0 5. 1. e E-05. 1.5 E-0 5 _1.3 E-0 5._1. I E-0 5 1. 0E-0 5 4 ~
24 HH 0 MlH 2.7E-04 5.0E-05 3.5E-05 2.0E-05 2.3E-05 1,9E-05 1.6E-05 1.4E-05 1.3E-05 1.lE-05 -
i 8
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[AdlE D -13 NHOLE BODY 008E (hell)
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DVEHi4ND 018P[R$10H I
PA30UILL StaplLITY Cl.AE8E8 C & D HJNDSPEEDel HPil 013JANEE (HILES) j
' 1,00 2.00 3.00 4.00 5.00 6.00 -
7.00 8.00 9.00 10.00 J }llE ...... ...... ...... ...... ...... ...... ...... ...... ......
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t I,lE-04 0 O, c. O. 4 O, 4 O, 0.
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l.6E-03 6.5E=0i 3.4E-04 1, 9 E - 0,4 l.lE-04 a.4E-05 1.4E-05 0 4 O.
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,! 7 HR 0 MIN 2.6E-03 l.lE-03 6.3E-04 4.l[-04 2.9E-04 2.lE-04 1.6E-04 1.2E-04 9.6E-05 7.8E-05
~~~ ~ ~ 19 ' H M 0 HIN 371E-03 1-3E-037.4E604 4.9E;0F374EE04 2 5Ee64 1.9E;04 1;5E-~0Fl!2E;04-~9;7E;05-9 HIH 3.4E-03 1.4E-03 8.lE-04 5.3E-04 3,1E-04 2.8E-04 2,lE-04 1,6E-04 1,3E-04 ),j E 1[ HR '
0 NIN 3.7E-03 1.5E-03 8.7E.04 5.7E-04 4.oE-04 3.0E-04 2.3E-n4 1.8E-04 1.4E-04 3 2E-04 44 HR 4s0E-D3776E- 03 972Ea04 6 TIE;D4773Es04 3 2E;04~~2;4E;04 1.9E'O4~~ l.5E 0Fl!3E;04----
~~~~~l6"HR O' HIN 4.4E*03 1.8E-03 1.0E-03 6.7E-04 4.8E-04 1.6E-04 2.7E-04 2.2E-04 1,7p0 4 1.4E-04 20 HR 0 HIN i . u -0, l.lE-03 ..,E-04 5.2E-04 3. -04 s.0E.04 2.4E-04 1. 04 1.6E.04 24 eR 0 ,,N 4,,50, a .
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Page 2I of 26 I TABLE D-14 PHOL.L #a9.Y 003E IREH) ,
ST, Lucir (NERGEHr~ PLAN
~
f DVERLhlD bl8Pr ' ,1 0}J PAsuull'L STAMILITY ELASSES C & D i
MIN 0$PEEDe5 NPil j
DISTallCE (HILES) l IlllE I.00 2.00 3,09 4.00 5.00 6.00- T.00 8.00 9.00 10.00
$2 HIN I,3E-04 0 0, 0, 0, 0, 0 O. 0 O.
30 HIM 119E'04 qi4E-05 0, 47 0 O. O. 0, 6, 6 45 HIN 3.4E-04 9.6E-05 3.2L-05 0. O. c. O. O. O. c.
I liR 0 HIH 5.0E-04 4.1E-04 6,5E-05 2.5E-05 0 c.
~
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. 2 HR 0 HIH a.aE-04 3.7E-04 2.lE-04 1.1E-04 2.4E-05 5.6E-05 3.0E-05 1.5E-65 7,lE-06 0,,
2 HR 30 HIH 1.0E-03 4.4E-04 2.6E-04 1,6E-04 7.7E-05 5.4E-05 3.8E-05 1.3E-05 1.lf-04 2.4E-05
, ^*-'3'HR 0 HIN lilE-03 4;8f;04 2".9E'O4 l!9E;01-l.lE;04~~9.~7ELO5 69ELOS 5!0Ee05 3.7E;05 2.8E;05 6 HR 0 HIN 1.5E-05 6.5E-04 3.8E-04 2.6E-04 1.8F-04 1.'4E-04 8.lE-04 8.4E-05 6.8E-05
! 5.6E-0{
~~~lC'HR'~ '0'HIH 1.9E-03-"5;)Ed44 4.8E'04 3.2E;04 2;3E;04 1;7E-04 l;3E;04 !!!E'04" 8'.7E-05 7.~3E-05 12 HR 0 HlH 2.lE-On 8.8E-04 5.2E-04 3.5E-04 2.5E-04 1.4E-04 1,5E-09 1,2E-04 9,5E 05 7,9E-05 I 14 HR 0, HIN 2.3g-03 9.4E-04 5.5E-04 3.7E-04 2.7E-04 2.0E-04 1.6E-04 1.2E-04 1.0E-04 a.5E-05
~l6 HR 0 MIN 2 aE-01'~170EE03 5i9E;04 3~4r;04 2780'64 CIE;64 G7E;047.3E;0F-~l.lE,04 9'. ! E;0 5 20 HR 0 HIN 2.7C=0) 1.!E-03 6.5E-04 4.3E.04 3.!E.04 3.4E=04 1.DE-04 1.5E*04 1.2E=04 1.0E=00 24 HR 0 HIN 3.0E-03 1.2E-03 7.0E-04 4.7E-04 3.4E-04 2.6E-04 2.0E.04 1.6E-04 1.3t-04 1 IE-04
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Page 22 of 26 Hat 0LE Undy D,05E (EEAQ 31, LUCif CHERLENCY FLAN i
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PASQUILL StaplLITY CLa6SES C 40
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10 HIH . ~1s&E?04- 5i1E605" 2s0E 2;50-0J 0 A s-* 07" 6 .-- -
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i t o HR-- 0 HIH 1;2E-03 5;2E-04 3i1E-Gi- 2;lE;04-~~l.5E;04 172E;04 9.2E;057;4Ee05-~6.lE-05--~571E-05 12 HR 0 HIH 1.3E-03 5.6E-04 3.4E-04 2.1E-04 8.7E-04 3.3E-94 9,9,E-05 8,0E-05 $,6E-05 5,}E.-05 14 HR 0 HIN 1.4E-03 6.0E-04 3.6E-04 2.aE.04 8 aE-04 3.aE-04 1.lE-04 a.5E-05 7.0E-05 5.9E-05 3 6 HR u H'J N 1 5 E = 03 674 Ee 0 9'-- 3; 8 Ee 0 4~ 776 E; 0 4 l!9 ET0 4-- i~4 F 0 4 l!! tT0 4 9.~0 E - 057 74 C40 5-~672 E'- 05 20 HR 0 HIH 1.7E-03 7.lE-04' 4.2E-0c 2.nE-04 2.0E-04 1.6E-04 1.2E.04 9.8E-05 8.lE-05 6.9E-05 24 H8 0 MIN },9E-0} 7,7E-pj 495E-04 3,oE*04 2.2E-04 t.lE-04 1.3E-04 1.lE-04 8.4E-05 7.4E-05 i
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PLANT OVERLAY - 22 1/2* SECTOR Figure D-1 h ,
s
. - e m Page 1 of 13 s ,
a
. FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 s EMERGENCY PLAN IMPLDENTING PROCEDURE
- 3100026E, REV. 6
~
a *
1.0 TITLE
CRITERIA JOR AND CONDUCT.0F EVACUATIONS
~
2.0 APPROVAL
ReviewedbyFac'111tykc.viewGroup_ July 25, 1975 Approved by K. N._ .Iartis Plant lianager July 24, 1975
'levision 5 [ ieve by Facd g.],/ '~ ity Review V.P. Group March 201,f & 25,198 Approved by /
( Pwr. Res.Agige/, _ Ic /
Pe ds' ion 6 R 'Tewed b ' Pc i'd Review Group /M a y 2. 8 19 9 I ApproveA by M I* V.P. Pwr. Res. A nx 2, 19P/
s i -
3.0 'St' OPE :
3.1 Purpose -
_, This procedt.re provides criteria for determining if evacuation of, a local ar aa an-site or the Owner Controlled Area should be carried Out., It provides instructions fer effecting an ordered, rapid,aod safe.?vacoptiom of a local area or the Owner Controlled Arta in order to.stevent or minimize radiation exposure to persoinel. 12 aim provides instr 2ctions for personnel account-ability.
b2 -
Disc.ssion' 3.2.1 Acqurste classifiertion of emergencies that =ay occur at che Platt i e, n.w.asary,to enable the Nuclear Plant Superiis'r to rtie~the, proper corrective action and to
- knov.when to initiate _f.it E=ergency Plans. For those emergencies int,,1ving high radiation and/or the release of radioactive sateri.1 to the environnent, it is necessary
,l ___ to provf.Je theduelear Plant Supervisor (Energency Coordinator) s ' with guidelines, that'calil enable him to know when to order x- a local arta evacuation or evacuation of the Owner Controlled
.s ' Area. ~
~
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J 'g g g _ - .
. . . e Page 2 of 13 i FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
's #3100026E, REV. 6-i 4
j 3.0 SCOPE: (Continued)
<t
,f 3.2 Discussion (Continued 4 ..
<! 3.2.2 A local area evacuation or evacuation of the Owner
, Controlled Area may be necessitated by the Occurrence of any of several events where evacuation of personnel
. would be necessary to minimize their exposure to radiation. An Owner Controlled Area evacuation will be conducted for any Site Area Emergency or General Emergency.
3.3 Authority
This procedure implements the St. Lucie Unit #1 Emergency Plan.
3.4 Definitions
3.4.1 Assembly Area 1.
"l The location to which evacuation personnel report. In a local evacuation, personnel evacuate and assemble in
, a focation designated by the Emergency Coordinator. In an evacuation of the Owner Controlled Area, evacuating FPL personnel from the Protected Area go to the Site
~
Assembly Station on Highway A1A near the north entrance to plant p'roperty, while non-FPL personnel and FPL personnel from outside the Protected Area assemble at J.C. Public Park on Highway A1A, 7 1/2 miles north of the plant. If necessary, other assembly areas can be specified by the Emergency Coordinator.
3.4.2 Escort
! An individual specifically assigned to accompany other
- persons who are required by the Security Plan or Health Physics Manual to be escorted.
4 3.4.3 Loc-L Area Evacuation An evacuation of some portion of, but not all of, the Owner Controlled Area. It may include evacuation of a
,, room, building, group of buildings, generating station
- [ area, or other portion of the Owner Controlled Area.
II
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. 1 Page 3 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. &
3.0 SCOPE
(Continued) i
3.4 Definitions
(Continued)
{. 3.4.4 Owner Controlled Area That portion of FPL property surrounding and including i the plant which is subject to limited access and control l
as deemed appropriate by FPL (indicated by the dotted
, line on the attached Florida Power & Light property plan, i Figure 1 of this procedure).
3.4.5 Owner Controlled Area Evacuation 8
The evacuation from the Owner Controlled Area of all personnel except those required to place the plant in a safe condition, the emergency teams, and the guards necessary to fulfill their evacuation responsibilities.
3.4.6 Radiation Control Point Located in the Auxiliary Building, it is likely to be used as an assembly area during a local evacuation.
4.0 Precautions
4.1 Every effort shall be made to minimize personnel exposure to radiation.
4.2 Personnel who have been in the area of the emergency shall remain in a group, and shall not mix with the other personnel in the l .
Radiation Control Point or other assembly area until they have been monitored for possible contamination, unless they are injured.
- Injured personnel shall be treated as discussed in E-Plan Imple- l menting Procedure 3100021E, Duties of the Emergency Coordinator.
4.3 Except as discussed in 4.2 above, perse.nnel reporting to the Radiation Control Point or other assembly area shall group according to departmente in order to facilitate personnel accountability and monitoring.
4.4 When reporting to the assembly area, take the most direct route possible, but do not use any route or area that has been declared part of the emergency area, or that could result in excessive individual exposure or injury.
4.5 If an area or building is evacuated, any records regarding the persons in the area shall be removed and taken to the assembly area.
Page 4 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. 6' i
4.0 Precautions
(Continued) 4.6 Health Physics personnel exiting the RAB as necessitated
- by an energency condition of possible radiological nature shall pick up suitable portable radiation monitoring equipment j which would be required for re-entry monitoring.
5.0 Responsibilities
5.1 The Nuclear Plant Supervisor is responsible for:
5.1.1 Classifying any emergency that may occur at Unit #1.
5.1.2 Initiating the Emergency Plans when appropriate.
5.1.3 Initiating the evacuation of any area in which the criteria for evacuation, as expressed in steps 8.1 8.2 are met.
5.1.4 .
Providing protective action recommendations to off-site /R6 authorities per Table 1 in 3100021E(Duties of Emer. Coordinator).
5.2 The Nuclear Plant Supervisor shall act as Emergency Coordinator.
5.3 The Emergency Coordinator is responsible for advising the Security Team Leader of a local evacuation or an Owner Controlled Area evacuation. This notification will be by the alarm or the PA system. Information needed by the Security Force to properly fulfill their responsibilities during the evacuation shall be provided to the Security Team Leader by the Emergency Coordinator.
, (See E-Plan Implementing Procedure 3100021E, Duties of Emergency.
- t Coordinator).
'I' 5.4 The Security Guard Force is under the supervision of the Plant Security Supervisor. He serves as the Primary Security Team
, Leader. The Security Force Shift Supervisor is the Interim Security Team Leader.
5.5 The r'esponsibilities of individuals acting as escorts are contained in Sections 5.12 and 8.4.5 of this procedure.
5.6 All personnel permanently or temporarily assigned to St. Lucie plant shall familiarize themselves with:
5.6.1 The instructions given in this procedure.
5.6.2 The access routes to the work location to which they are assigned.
Page 5 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. 6
5.0 Responsibilities
5.6 (Continued) 5.6.3 The locations of the evacuation assembly areas:
- a. The Radiat!on Control Point in the Auxiliary Building.
- b. The Site Assembly Station.
- c. The J. C. Public Park on Route A1A, north of the plant site.
l
. 5.7 It shall be the responsibility of each supervisor and depart-l ment foreman not involved in the emergency response to report to the assembly area to assist in accounting for all personnel under his supervision.
5.8 Security Department Responsibilities are defined in Security Procedure 0006123.
5.9 The Control Point Guard shall maintain accurate records of all personnel entering or leaving the controlled area and make them available when required.
5.10 The Main Gate Guard shall maintain accurate records of all ,
personnel entering or leaving the Generating Station Area and make them available when required.
5.11 The Assembly Area Supervisor shall be responsible for personnel accounting at assembly area and liason between these personnel and the Emergency Coordinator.
5.12 Tour Guides are assigned to escort groups of visitors during tours of the plant site. In an emergency, Tour Guides are responsible for personnel accountability of their respective groups and the evacuation of their group to the Site Assembly Station in cooperation with the Security Force.
5.13 Unit 2 Responsibilities are defined in ASP 5.0.
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, . ._- m _ . _ _ __ __.. .__ _. _ _ _ . __ _ _ . . _
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Page 6 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. 6 6.0
References:
i
! t 6.1 St. Lucie Plant Radiological Emergency Plan.
}
6.2 St. Lucie Plant Security Plan.
6.3 E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator.
i 7.0 Records and Notifications:
7.1 A list of all persons assembled at J.C. Public Park shall be t'
prepared by a member of the Plant Staff who will travel to that location with evacuees.
1 7.2 Records showing that all personnel in the area affected by the emergency were accounted for shall be kept as part of the t
records of the emergency and recorded by the Emergency Coordinator.
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Page 7 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. 6
8.0 Instructions
8.1 Criteria for Local Area Evacuation If an incident involves a high radiation ff. eld or has caused the release of radioactive material to the environ-ment, the need to evacuate the affected area shall be determined in accordance with the following criteria:
I Evacuate the affected local area in which any of the following conditions occur:
8.1.1 Area Radiation Monitor Alarm.
l 8.1.2 Containment Evacuation Alarm.
8.1.3 Unevaluated direct radiation dose rate reading in excess of 100 mrem / hour.
8.1.4 Unevaluated airborne radioactivity concentration in excess of 1 X 10-9 micro C1/cc.
8.1.5 Removable radioactive surface contamination in an unposted area in excess of 1000 dpm/100 cm2 beta-gammn over an area of 100 ft2, 8.1.6 Removable radioactive surface contamination in an unposted area in excess of 50 dpm/100cm2 alpha over an area of 100 ft'.
8.1.7 The Emergency Coordinator determines that a situation exists for which local evacuation is appropriate.
8.2 Criteria for Owner Controlled Area Evacuation The Owner Controlled Area shall be evacuated in the following circumstances:
- 1. Site Area Emergency,
' 2. General Emergency,
- 3. If the Emergency Coordinator determines that the entire Protected Area should be evacuated,
- 4. Any other situation in which the Emergency Coordinator determines that evacuation is appropriate.
a Page 8 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. 6
8.0 Instructions
(Continued) 8.3 Evacuation Preparedness 8.3.1 All visitors shall have adequate transportation available on-site to evacuate all members of their respective groups.
8.3.2 Escorts shall maintain control of groups or individuals to which they are assigned to enable all members of the i groups to be located, notified and evacuated.
8.4 Local Area Evacuation Laplementation
}
8.4.1 When the Emergency Coordinator (Nuclear Plant Supervisor)
>; determines that a local evacuation is necessary, he shall, in following Emergency Procedure Duties of the Emergency Coordinator, announce an evacuation using the PA system, i
giving the area affected, the assembly area and other instructions as required.
8.4.2 All personnel in the evacuated area shall stop work, turn off notentially hazardous equipment, such as cutting torches, and leave the area by the same route taken to enter the area, unless otherwise instructed by the
- Emergency Coordinator.
!; 8.4.3 All personnel in the evacuated area shall report to the i
Radiation Control Point in the Auxiliary Building for
- j- monitoring and accountability.
i 8.4.4 The Radiation Monitor Team shall monitor evacuated personnel for contamination, (for areas where contamination may be present) .
8.4.5 Injured personnel shall be treated as discussed in E-Plan Implenenting Procedure 3100021E, Duties of Emergency Coordinator. If an injured person is evacuated from the plant site, the person's TLD, selfreading dosimeter, identification badge, and keycard should be removed and given to the First
. Aid and Personnel Decontamination Team Leader.
8.4.6 The Control Point Guard shall make available to the Emergency Coordinator his records showing the personnel who are in the Security Control.ed Area.
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Page 9 of 13 4
FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. 6
, 8.0 Instructions: (Continued) 8.4 Local Area Evacuation Implementation (Continued)
> > 8.4.7 The Emergency Coordinator and department supervisors and foremen having personnel working in the evacuated area shall verify that all personnel in the evacuated area are accounted for.
8.4.8 The Emergency Coordinator shall initiate a search for the personnel who have not been accounted for.
8.5 Owner Controlled Area Evacuation Implementation 8.5.1 When the Emergency Coordinator (Nuclear Plant Supervisor) determines that an evacuation of the Owner Controlled Area is necessary, he will, in the following Emergency 1 Procedure Duties of the Emergency Coordinator, order an evacuation using the PA system and the evacuation alarn..
8.5.2 All personnel in the evacuated area shall stop work, turn off potentially hazardous equipment, such as cutting torches, and leave the area. All personnel not needed to place Unit #1 in a safe condition and not on an emergency team or otherwise required on site, shall evacuate to the appropriate Assembly Area. Emergency Teamsshall report to the t.dministrative Building for assignment.
8.5.3 Injured personnel shall be treated as discussed in E-Plan
! Implementing Procedure 3100021E, Duties of Emergency Coodinator. If an injured person is evacuated from the plant site, the person's TLD, selfreading dosimeter, identification badge, and keycard should be removed and given to the First Air and Personnel Decontamination Team Leader.
8.5.4 Personnel shall remove protective clothing prior to leaving the Radiation Controlled Area.
8.5.5 Proceed to the Main Guard Station by the most direct route, unless an alternate route is specified by the Emergency Coordinator.
! 8.5.6 Each person shall then proceed to the Site Assembly 'Area I
(see Figure 2).
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, Page 10 of 13 t
FLORIDA POWER & LIGHT COMPANY EMERGENCY PIM IMPLEMENTING PROCEDURE
- 3100026E, REV. 6
8.0 Instructions
(Continued) 8.5 (Continued) 8.5.7 Assemble by department for accounting and monitoring, and remain at the assembly area until given instruc-tions by the Assembly Area Supervisor.
8.5.8 If the conditions associated with the emergency are such that the site assembly station area is untenable, the Emergency Coordinator shall direct all personnel to report to the J. C. Public Park and specify the route to be followed.
8.5.9 The department supervisors and foremen shall account for their personnel and report the results to the Assembly Area Supervisor.
i 8.5.10 The Assembly Area Supervisor shall assure that all personnel are monitored for contamination prior to leaving the Assembly Area.
8.5.11 The Assembly Area Supervisor, the Security Force Shift Supervisor and the department supervisors and foreman shall examine all the personnel records available to determine if any personnel are unaccounted for.
8.5.12
- The Emergency Coordinator shall initiate a search for the personnel who have not been accounted for.
e 8.6 Security Force Evacuation Implementation 8.6.1 Upon notification of an evacuation, the Security Force Shif t Supervisor (Interim Security Team Leader) shall advise by radio all other guards on duty that an evacuation
{ is in progress. The Security Force will proceed with the
! evacuation of persons and with personnel accountability l activities.
i 8.6.2 The Control Point Guard and the Main Gate Guard shall immediately review logs and badge records to determine what persons are in the affected area. These guards will be prepared to brief the Emergency Coordinator. The i, Control Point Guard shall verify that all personnel have j evacuated the area and report to the Security Team Leader 1
for further instructions. The Control Point Guard shall T
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, Page 11 of 13 FLORIDA POWER & LIGHT COMPANY -
EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. 6
, 8.0 Instructions: (Continued) 8.6 (Continued) 8.6.2 go to the Main Gate with his personnel records and await instructions from the Security Team Leader.
8.6.3 The Security Team shall:
- 1. Sweep the plant site to verify that all personnel have evacuated.
- 2. Notify any Special Guards on duty.
- 3. Perform additional duties as specified in the Security Guard Force Post and Force Orders.
8.6.4 The Security Team Leader, after completion of sweeps by members of the Security Team shall instruct guards concerning special assignments which may be required as a result of the evacuation. He shall advise the Off-Site Emergency Security Manager of any circumstances which require his attention.
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Page 12 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100026E, REV. 6 FIGURE 1 St. Lucie Plant Owner Controlled Area t
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Page 13 of 13 FLORIDA POWER & LIGtC COMPANY EMERGENCY PLAN IMPLEMENTING f?OCEDURE
- 3100026E, REV. 6 FIGURE 2 i Site Assembly Area l
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