ML20050A193
| ML20050A193 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/02/1982 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17212B474 | List: |
| References | |
| PROC-820202-01, NUDOCS 8203310408 | |
| Download: ML20050A193 (100) | |
Text
6 4 Page 1 of 29 FLORIDA POWER & LIGHT COMPANY 1 ST. LUCIE UNIT #1 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E REVISION 11
1.0 Title
Duties And Responsibilities Of The Emergency Coordinator l
2.0 Approval
_ , _ Reviewed by Plant Nuclear Safety Committee July 25, 5 19_7,5,
_ _ . _ _ _ Approved by K. N. HarrisPlant Manager July 29, 5 19J_5, Rev.11ReviewedbyFRG//f 8 I , 1[N8 % , I b 3 !/ 2. , /[18 19
. . - . Approved by dhh y Director Nuc Energy 14 19[L
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 e=ergency 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 prompt classification of /R11 the emergency (in accordance with E-Plan Implementing Procedure 3100022E, Classifications of Emergencies) and notifications of designated off-site authorities as well as FPL's Off-Site Emergency Organization (see Figure 1 for notification flow) .
8203310408 820329 PDR ADOCK 05000335 F PDR E.E NNE -
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Pago 2 of 29
, E -;' L A N IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR l
4.0 Precautions
(continued) 4.2 Tha Emergency Coordinator can delegate his responsibilities at his s
discretion with the exception of the decision to notify state and local authorities and the content of that no tific atio n. When the TSC is operational, the Emergency Coordinator can delegate all off-site communications to the TSC Supervisor. , , , ,
4.3 During exercises, drills or tests, ALL MESSAGES shall begin and end with "THIS IS A DRILL MESSAGE" or "THIS IS AN EXERCISE MESSAGE" .
4.4 Protective action recommendations to state and local authorities CANNOT be delegated by the Emergency Coordinator, however, these recommendations become the responsibility of the Recovery Manager when the Interim Energency Operating Facility is manned and operational . /R11 3.0 Re spo nsib ilitie s: C 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.
5.1.3 If. no Senior Reactor Operator is available, any other Licensed Operator. /R11 5.2 The Emergency Coordinator shall only grant permission for watch relief, including his own, when it is safe in his j udgement 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 af ter activating the TSC and preferably before calling the NRC.
5.5 The Emergency Coordinator is responsible for providing protective action recommendations to off-site authorities. This responsibility cannot be delegated, but becomes the responsibility of the Recovery Manager when the Interim Emergency Operations Facility is manned and o perational . /R11
Page 3 of 29 E. PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11
' DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
- 6.0
References:
6.1 St. Lucie Plant Radiological E:nergency Plan 6.2 E-Plan Implementing Procedures, as follows:
EPIP-3100022E - Classification of E:nergencies.
m.
EPIP-3100026E - Criteria for and Conduct of Evacuations.
EPIP-3100033E - Radiation Release and Dose Projection. /R11
7.0 Records
All significant infor: nation, events, and actions taken during the emergency period shall be recorded as directed by the Emergency Coordinato r.
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Page 4 of 29
. E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSI3ILITIES OF THE EMERGENCY COORDINATOR
8.0 Instructions
8.1 Classification Im;aediately upon becoming aware of an abnormal condition, the Nuclear Plant Supervisor shall classify the condition in accordance .
with the criteria given in E-Plan Implementing Procedure 3100022E, Classification of Emergencies. If the classification is, UNUSUAL EVEE, ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, the Nuclear Plant Supervisor shall declare an emergency and become the Emergency Coordinator. The Emergency Coordinator shall, until relieved, remain in the Control Room at all times during emergency situations that require Emergency Plan implementation unless, in 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 Coordina:.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 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 DiERGENCY If a SITE AREA EMERGENCY is declared , the Emergency Coordinator shall complete the actions specified in the attached SITE AREA EMERCENCY CHECKLIST. These actions include required off-site notifications, on-site protective actions, and activation of on-site support centers.
8.6 GENERAL EMERGENCY If a GENERAL EMERGENCY is declared, the Emergency Coordinator shall complete the actions specified in the attached GENERAL EMERGENCY CHECKLIST. These actions include required off-site notifications, on-site protective actions, and activation of on-site support centers.
l Page 5 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11
' DUTIES AND RESPONSI3ILITIES OF THE EMERGE NC Y COORDINATOR
8.0 Instructions
(continued) 8.7 MEDICAL EMERCENCIES The attached MEDICAL EMERGENCY CHECKLIST shall be followed in the ,,
event of injury to plant personnel or visitors. The MEDICAL NOTIFICATION FORM attached to the Checklist shall be prepared for eaca victim and shall, if possible, accompany the victim to off-site 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 then to the Emergency Control Officer when they establish contact and assume responsibilities.
8.9 0FF-SITE PROTECTIVE ACTI0li RECOMMENDATIONS The Emergency Coordinator is responsible for providing protective action recommendations to off-site authorities as indicated on Pages 25 through 29, "Cuidelines for Protective Action Recommendations to Of f-site Authorities" . When the Emergency Control Officer has indicated that the Interim Emergency Operations Facility is manned and operational, the Recovery Manager can relieve the Emergency Coordinator of this responsibility. /Ril e
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Page 6 of 29 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 11 l
DUTIES AND RESPONSI3ILITIES OF THE EMERGENCY COORDINATOR '
UNUSUAL EVENT CHECKLIST l ACTIONS TO BE TAKEN 3Y EMERGENCY COORDINATOR OR HIS DESIGNEE IN THE EVENT OF AN UNUSUAL EVENT ,
t
- 1. Order initial corrective action per Emergency Operating Procedures.
Fire / Explosion - see attached FIRE / EXPLOSION CHECKLIST Medical - see attached MEDICAL EMERGENCY CHECKLIST
- 2. Mobilize taterim Emergency Teams to respond as necessary.
- 3. Ccomence preparation of the attached State of Florida Fixed Nuclear Facility Notification Message Form and EMERGENCY INFORMATION CHECKLIST excluding off-site dose proj ections. /R11
- 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 Operat. ions Supervisor .
Technical Department Supervisor Emergency Control Officer (or Nuclear Energy Duty.
Officer) /R11
- 5. Within 15 minutes of classifying the emergency:
5.1 NAWAS Announcement:
" 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, UNUSUAL EVENT, repeat UNUSUAL EVENT."
Time
" Acknowledge, over.'
(ALTERNATE METHOD) If NAWAS is unavailable-telephone State Warning Point at PHONE NO. 1-904-488-1320 or Florida Marine Patrol-Alternate State Warning Point 1-904-488-5757.
State Warning Point will call via Phone to validate the notification. Af ter validation, transfer the information on the State of Florida Fixed Nuclear Facility Notification Message Form via NAWAS or ALTERNATE ROUTE.
State Warning Point Message Validation Time /R11
Pcgo 7 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 <
DUTIES AND RESPONSIBILITIES OF THE EMERGE NCY COORDINATOR i
UNUSUAL EVENT CHECKLIST (continued)
$.2 Notify, by telephone, the State Radiological Duty Officer at Radiological Health Services in Orlando at 1-299-0580. (they have a beeper service for full time coverage) When the Duty Officer is contacted, transfer the information on the State of Florida Fixed Nuclear Facility Notification Message Form and the Escrgency Information Checklist. /R11
- 6. Prepare attached SIGNIFICANT EVENT REPORT (if time permits) and notify NRC via hot-line (within one hour)
- 7. Reassess the Emergency Classification and update the State of Florida Fixed Nuclear Facility Notification Message Form apu Emergency Information Checklist. /Rll e
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Pcgo 8 of 29 E-PLAN IMPLEMENTINC PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSIBILITIES OF THE EMERGZNCY 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 6' Procedur e s.
Fire / Explosion - see attached FIRE / EXPLOSION CHECKLIST Medical - see attached MEDICAL EMERGENCY CHECKLIST
- 2. Notify personnel of the e:nergency condition over the Unic
- 1 PA system, giving location, class, and type of e nergency.
_ 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 Teans to respond as necessarf.
- 5. Commence preparation of the attached State of Florida Fixed Nuclear Facility Notification Message Form and EMERGENCY INFORMATION CHECKLIST including off-site dose projections -
using E-Plan Implementing ?rocedure 3100033E, Radiation Release and Dose Projection. /R11
- 6. Relay information to the Duty Call Supervisor (see NPS Bulletin Poard for scheduled supervisor and telephone number). Order him to notify the following:
Plant Manager Operations Superintendent Operations Supervisor Technical Department Supervisor Emergency Control Officer (or Nuclear Energy Duty Officer) , /R11 Other Depart:nent Supervisors (Primary Team Leaders)
(ALTERNATE METHOD if Duty Call Supervisor is unavailable-Notify Emergency Control Of ficer.
Pcgo 9 of 29 l l
E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 '
DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ALERT CHECKLIST (continued)
- 7. Notify the following within 15 minutes of classifying the ,
emergency: wI 7.1 NAWAS ANNOUNCEMENT: /R11
" 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, ALERT EMERGENCY, repeat ALERT EMERGENCY."
Time
" Acknowledge, over."
(ALTERNATE METHOD) if NAWAS is unavailable-telephone State Warning Point at PHONE NO. 1-904-488-1320 or Florida Marine Patrol-Alternate State Warning Point 1-904-488-5757.
State Warning Point will call via Phone to validate
, the notification. Af ter validation, transfer the information on the State of Florida Fixed Nuclear
. Facility rocification Message Form via NAWAS or ALTERNATE ROITTE.
State Warning Point Message Validation Time ./R11 7.2 Notify, by telephone the State Radiological Duty "
Officer at Radiological Health Services in Orlando at 1-299-0580. (they have a beeper service for full time coverage) When the Duty Officer is contacted, transfer the information on the State of Florida Fixed Nuclear Facility Notification Message Form and the Emergency Information Checklist. /R11
- 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 Tean Leader that all personnel are accounted for (if local evacuation was conducted) .
'0.
. 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.
Pcgo 10 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSI3ILITIES OF THE EMERGENCY COORDINATOR ALERT CHECKLIST (continued)
- 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 Depart:nent representative arrives.
- 13. Reassess the Emergency Classification and update the State of Florida Fixed Nuclear Facility Notification Message Form and EMERGENCY INFORMATION CHECKLIST with Technical Support Center Supervisor. /R11
- 14. Relinquish responsibilities for communications with off-site support agencies when the Emergency Control Officer notifies the Emergency Coordinator that he accepts these responsibilitie s.
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Pcgo 11 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SITE AREA EMERGENCY CHECKLIST ACTIONS TO BE TAKEN BY EMERGENCY COORDINATOR OR HIS DESIGNEE IN THE EVE!Tr OF SITE AREA EMERGENCY.
- 1. Order initial corrective action per Emergency Operating Procedur es.
- 2. Notify personnel of the emergency condition over the PA system (connect all units), giving location, class, and type cf 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 Evacuatiwns.
- 4. Sound Site Evacuation Alarm.
- 5. Repeat PA anncuncement.
- 6. Order Security Tean Leader to evacuate Cuner 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 State of Florida Fixed Nuclear Facility Notification Message Form and EMERGENCY INFORMATION CHECKLIST, including off-site dose proj ection using E-Plan Implementing Procedure 3100033E, Radiation Release and Dose Projection. Fire / Explosion and Medical Checklist are attached if required. /R11 -
- 9. Relay information to the Duty Call Supervisor (see NPS Bulletin Board for scheduled supervisor and telephone number). Order him to notify the following:
, Plant Manager Operations Superintendent Operations Supervisor Technical Department Supervisor Emergency Control Officer (or Nuclear Energy Duty Officer) /Rll Other Department Supervisors (Primary Team i Leaders)
( ALTERNATE METHOD If Duty Call Supervisor is unavailable-notify Emergency Control Officer.
Pago 12 of 29 j E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 ,
DUTIES AND RESPONSI3ILITIES OF THE EMERGENCY COORDINATOR SITE AREA EMERGENCY CHECKLIST (continued)
- 10. Notify the following within 15 minutes of classifying the emergency:
I m-m 10.1 NAWAS Announcement:
" 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, SITE AREA EMERGENCY, repeat SITE AREA DiERGENCY." /R11 Time _ . _ _
" Acknowledge, over."
(ALTERNATE METHOD if NAWAS is unavailable-telephone State Warning Point at PHONE NO. 1-904-488-1320 or Florida Marine Patrol-Alternate State Warning Point 1-904-488-5757.
State Warning Point will call via Phone to validate the notification. Af ter validation, transfer the information on the State of Flor.ida Fixed Nuclear Facility Notification Message Form via NAWAS or ALTERNATE ROUTE.
State Warning Point' Message Validation Time /R11 10.2 Notify, by telephone the State Radiological Duty Officer at Radiological Health Services in Orlando at 1-299-0580. (they have a beeper service for full time ,
coverage) When the Duty Officerf is contacted, transfer the information on the State of Florida Fixed Nuclear Facility Notification Message Form and the Emergency Information Checklist. /R11
- 11. When LGR system is activated by offsite organizations, contact St. Lucie County Disaster Preparedness, inform them of off site dose projections and that site evacuation has started, location of assembly area (s), evacuation route ( s) . Notify them of any wind changes, and when evacuation is completed. /R11
- 12. Prepare attached SIGNIFICANT EVENT REPORT (if time permits) and notify NRC via hot-line (within one hour) .
(To be done by TSC if properly staffed.)
- 13. Verify from Security Team Leader that owner Controlled Evacuation (including Unit #2 construction site) is complete and that all personnel are accounted for.
Page 13 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 f DUTIES AND RESPONSI3ILIfIES OF THE EMERGENCY COORDINATOR SITE AREA EMERGENCY CHECKLIST (continued)
- 14. Reassess corrective and protective actions. Verify activities underway, reassign personnel and teams as necessary. /R11
- 15. Activate the Technical Support Center and the Operational Support Center.
- 16. Brief the Technical Support Center Supervisor on events. Order him to update state aryl county periodically and to refine dose projections when the Chemistry Department representative arrives.
- 17. Reassess the Emergency Classification and update the State of Florida Fixed Nuclear Facility Notification Message Form and EMERGENCY INFORMATION CHECKLIST with the Technical Support Center Suparvisor. /RJ 1
- 18. Relinquish responsibilities for c:mmunications with off-site support agencies when the Emergency Control Officer notifies the Emergency Coordinator that he accepts the responsibilities.
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Pago 14 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSI3ILITIES OF THE EMERGENCY COORDINATOR GENERAL EMERGENCY CHECKLIST ACTIONS TO BE TAKEN BY EMERGENCY COORDINATOR OR HIS DESIGNEE IN THE EVENT OF GENERAL EMERGE!CY 6l
- 1. Order initial corrective action per Emergency Operating Procedur e s.
- 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. Order Security Tean Leader to evacuate Owner Controlled Area and to report personnel accountability as soon a possible. -
l . .
- 7. - Mobilize other Interim Emergency Teams to respond as -
necessary.
l 1 8. Complete State of Florida Fixed Nuclear Facility l Notification Message Form and EMERGENCY INFORMATION CHECKLIST including off-site dose proj ections using E-Plan '
Implementing Procedure 3100033E, Radiation Release and Dose Proj ec ~ ~.on. /R11 t
~
- 9. Relay information to the Duty Call Supervisor (see NPS Bulletin Board for scheduled supervisor and telephone number). Order him to notify the following:
l Plant Manager !
l Operations Superintendent j Operations Supervisor 1 Technical Department Supervisor l Emergency Control Officer (or Nuclear Energy Duty Officer) /R11 Other Department Supervisors (Primary Team Leaders)
ALTERNATE METHOD If Duty Call Supervisor is unavailable -
Notify Emergency Control Officer.
Pcgo 15 o f 29 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 11 r DUTIES AND RESPONSI3ILITIES OF THE EMERGENCY COORDINATOR CENERAL EMERGENCY CHECKLIST (continued)
- 10. Notify the following within 15 minutes of classifying the emergency: , ,
.R11 iw, 10.1 NAWAS Announcement:
" State Warning Point Tallahassee, this is St. Lucie One" (State Warning Point will d i ve a go-ahead.)
" State Warning Point Tallahassee, this is St. Lucie One, we have a GENERAL EMERGENCY, repeat GENERAL EMERGENCY. /R11
( ALTERNATE METHOD If NAWAS is unavailable, telephone State Warning Point at PHONE NO. 1-904-488-1320 or Florida Marine Patrol-Alternate State Warning Point 1- j 904-488-5757. '
State Warning Point will call via Phone to validate the notification. Af ter validation, transfer the information on the State of Florida Fixed Nuclear Facility Notificatiop Message Form via NAWAS or l ALTERNATE ROUTE.
) -
)
j State Warning Point Acknowledgement Time l j
10.2 Notify, by telephone the State Radiological Duty
, officer at Radiological Health Services in Orlando at
,1-299-0580. (they have a beeper service for full time coverage) When the Duty Officer is contacted, transfer the information on the State of Florida Fixed -
Nuclear Facility Notification Message Form and the Emergency Information Checklist.
- 11. When LGR is activated by off site organizations, contact St.
Lucie County Disaster Preparedness, inform them of of f-site dose projections, recommended protective actions and that site evacuation has started, location of assembly area (s),
evacuation route (s) . Notify them of any wind changes, and when evacuation is completed. /R11
- 12. Prepare attached SIGNIFICANT EVENT REPORT (if time permits) and notify NRC via hot-line (within one hour) .
(To be done by TSC if properly staffed.)
- 13. Verify from Security Team Leader that Owner Controlled Evacuatica (including Unit #2 construction site) is complete and that all personnel are accounted for.
Pige 16 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSI3ILITIES OF THE EMERGENCY COORDINATOR GENERAL EMERGENCY CHECKLIST (continued)
- 14. Reassess corrective and protective actions. Verify ,
activities underway, reassign personnel and teans as necessary. /R11
- 15. Activate the Technical Support Center and the Operational Support Center.
- 16. Brief the Technical Support Center Supervisor on events. Order him to update state and county periodically and to refine dose projections when the Chemistry Depart:nent representative arrives. (EOF will perfor:n these tasks when operational) .
- 17. Reassess the E:nergency Classification and update the State of Florida Fixed Nuclear Facility Notification Message Form and EMERGENCY INFORMATION CHECKLIST with the Technical Support Center Supervisor. /R11
- 18. Relinquish responsibilities for communications with off-site support agencies when the Emergency Control Officer notifies the Emergency Coordinator that he accepts the responsibilitie s . .
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Pcge 17 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 1
STATE OF FLORIDA FIXED NUCLEAR FACILITY NOTIFICATION MESSAGE FORM Date and time of message { l
- 1. SITE 2. ACCIDENT CLASSIFICATION 3. UNIT NUMBER (S)
B_1. St. Lucie Al Unusual Event A. One (1)
- C Turkey Point B Alert B Two (2)
] Site Area Emergency ] Three (3)
D_l General Emergency D Four (4)
- 4. TIME AND DATE OF INCIDENT / EVENT: TIME DATE
- 5. __
INCIDENT INVOLVES: _ _ .
- 6. SITUATION INVOLVED: 7. TYPE OF RELEASE IS:
A: No Release A' Radioactive Gaseous
]. Potential (possible) release Imminent (probable) release
]
C Non-Radioactive Gaseous Radioactive Liquid CL ,
D_
. A release is occurring D Non-Radioactive Liquid E_! A release that occurred, but stopped E No n-Ap plicable 8.
RECOMMENDED PROTECTION ACTIONS:
l Al For Information only - (Unusual Event or Alert) l[ (Prepare for possible Alert or Site action involving Area' Emergency) , the public, to include notification.
l]l Notify public to take the following protective actions. (Site Area or General Emergency)
NO ACTION SHELTER EVACUATE D H 0-2 Mile radius (Gaseous Releas'e)
E I 2-5 Miles for sectors (Gaseous.
Release)
[l @ @ 5-10 Miles for sectors Release)
(Gaseous
(( @
Discontinue use of potentially affected water in Miles
@l Locations
- 9. RELEASE IS:
A Continuing - Expected duration or magnitude I B_I Terminated - Approximate Duration or Magnitude
- 10. REPORT OF GASEOUS RELEASE IS: @ Ground Level
- 11. WIND SPEED: Miles per hour NOTE: USE NOT APPLICA3LE (N/A) WHERE APPROPRIATE.
/all
Page 18 of 29 l l
E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 11 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
- 12. WIND DIRECTION DATA (CHECK ONE READ ACROSS) i WIND FROM DEGREES WIND TOWARD SECTORS A7FECTED
_A. N 349-11 S HJK B NNE 12-33 SSW JKL
] NE 34-56 SW KLM .'
D_ ENE 57-78 WSW LMN E E 79-101 W MNP F ESE 102-123 WNW NPQ G_ SE 124-146 NW PQR H SSE 147-168 NNW 0RA J_ S 169-191 N RAB K, SSW 192-213 NNE ABC L SW 214-236 NE BCD M WSW 237-258 ENE CDE N W 259-281 E DEF P WNW 282-303 ESE EFG 5 NW 304-326 SE FGH R_ NNW 327-348 SSE GHJ
- 13. CURRENT OUTSIDE TEMPERATURE: Ql OF
- 14. WEATHER CONDITIONS: (Rain, Snow, Sleet, Etc.): .
- 15. TDf?ERATURE DIFFERENCE (DELTA T): @l oF Elevation of Temp. Difference Measurement:
Stability Class ,(If Known): .
- 16. RELEASE DETECTED BY:
3l Visual B Sample Results Are:
3: Instrumentation Location Release Rate (Ci/sec)
- 17. ACCIDENT RELATED INJURIES: @l NO @l YES Number of Injuries
- 18. OTHER INFORMATION:
- 19. MESSAGE REPORTED BY:
Name Organizatio n Telephone (Outside 1)
- 20. MESSAGE RECEIVED BY:
Your Name Time Date CONTINUE TO NEXT PACE FOR:
- 1. Plant Duty Call Supervisor
- 2. Emergency Control Of ficer/ Recovery Manager / Nuclear Energy Duty Officer
- 3. DHRS Radiological Duty Of ficer NOTE: USE NOT APPLICABLE (N/A) WHERE APPROPRIATE /R11 l
Page 19 of 29 1
E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 .'
DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR '
l EMERGENCY INFORMATION CHECKLIST ADDENDUM TO STATE OF FLORIDA FIXED NUCLEAR FACILITY NOTIFICATION MESSAGE FORM
- 1. Date / / and Time of Message ,
- 2. Assessment of the Emergency (including potential for escalation to higher class ,
- 3. Basic Description of the Event
- 4. Estimate of Radipactive Material Released (Gaseous):
- Noble Gases: Source Term: -
C1/Sec
~
Total Release: Ci Radioiodines: Source Ters: Ci/Sec Total Release: Ci ,
- 5. Estimate of Projected Offsite Dose Rates:
DISTANCE l THYROID (mres/ hr) i WHOLE BODY (mrem / hr) 1 mile (site boundary) 2 miles ,
5 miles 10 miles
/R11 l
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Pego 20 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR i FIRE OR EXPLOSION EMERGENCY CHECKLIST TUdE P.A. Announcment of location and extent of fire.
Sound Fire Alar:n.
Activate the Fire Brigade and other appropriate emergency tems in accordance with Fire Emergencies EPIP 3100025E - PA announcement.
St. Lucie County - Fort Pierce Fire District PHONE No. 911.
Return to appropriate UNUSUAL EVENT ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY checklist.
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Pcgo 21 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSI3ILITIES OF THE EMERGENCY COORDINATOR MEDICAL EMERGENCY CHECKLI TIME m'
De termine:
Name of Victis Employer (if not FPL)
Nature and Extent of Inj ury Location _.
Is victim contaminated?
Activate First Aid and Personnel Decontaination Team (Notify Chemistry Supervisor).
Notify:
Health Physics Plant Manager Operations Superintendent
- When determined, notify Castain of Guard where to direct ,,
anbulance, etc.
Determine mode of transportation based on nature and extent of inj uries . (Ensure victim's TLD, sMfreader, ID badge and key card are retained on site) .
- a. Medical treatment for serious inj ary: ,
AMBULANCE PHONE NO. 911
- b. Medical treatment for minor injuries:
FPL Venicle/ Private Vehicle Send all victims to LAWNWOOD MEDICAL CENTER PHONE NO. 461-4000 Radioactively contaminated victims:
Notify REEF PHONE No. 1-673-2183 If Plant Manager not available, notify Duty Call Supervisor and Health Physics Duty Call Superviso&See Emergency Roster for Off-site notifications.
Complete attached Medical Notification form to accompany victim.
Page 22 of 29 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 11 J DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR i 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 ;
following information, if it is available: l4
- 1. Name and security badge number of the casualty Name Number
- 2. Ntaber of casualties being transported
- 3. Types of inj uries involved and body part:
- a. Fractures
- b. Burns ,
- c. Hemorrhaging
- d. Other
- e. Ambulatory: Yes No
- 4. Radiation contmiination status:
- a. Type of instrument used .
- b. BEFORE Decontaination AFTER Decontanination Body Part C/M Distance C/M Distance
, 1.
2.
3' _
4.
- c. Radioisotopes involved
- d. Decontaination procedures used
- 5. Type of transporting vehicle
- 6. Time of departure from plant _
1
Page 23 of 29 l
E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 11 DUTIES AND RESPONSI3ILITIES OF THE EMERGE NCY COORDINATOR SIGNIFICANT EVENT REPORT
( for NRC Notification)
Date Time ,
m.--
Facility N,ame Florida Power & Light St. Lucie Unit #1 Caller Name
- 1. Description of Event Classification of Event Reactor Systems Status ,
Pressure Te:npe rature Power level Flow ECCS Operating / Operable (Pumps on)
PZR or RX Level Cooling Mode Any Radioactive Release or Increased Release?
Path Stopped? Release Rate Monitored? .
Steam Plant Status: S/G Levels Equip. Failures Feedwater Source / Flow Electrical Dist. Status: Normal Off-site Power Sources Available?
Major Busses / Loads Lost Safeguards Busses Power Source ~
D/G Running? Lo aded?
Pe r so nnel Casual tie s / Co n t amina tio n?
- 2. Consequences of Event:
Actual and Potential Safety Haz.? ids:
Tech. Spec. Violations?
State Notified? Press Release Planned?
- 3. Cause of Event:
Correceive Actions taken:
Planned: ,
Pcge 24 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RE3PONSI3ILITIES OF THE EMERGENCY COORDINATOR EMERGENCY C00RDINATCR ;
L l' l DUTY CALL i EMERGENCY CONTROL OFFICER I FPL i
r SUPERVISOR g-
- OR ---+ OFFSITE EMERGENCY l ALT. E.C.O. ; RADIOLOGICAL DUTY OFFICER ORGANIZATION L-_____J ADDITIONAL PIANT SUPPORT INTERIM l EMERGENCY TEAM TEAMMEMBERSl
= EMERGENCY 9 LEADERS l _
TEAMS STATE OF FLORIDA
- BUREAU OF DISASTER PREPAREDNESS
, ST. LUCIE/ MARTIN COUNTIES A 0FFICE OF DISASTER .--- .
l PREPAREDNESS STATE OF FLORIDA
-e-, DEFr. OF HEALTH & , ,
) REHABILITATIVE SERVICES l
-=; LOCAL SUPPORT
- 1. FIRE / AMBULANCE; ST.
LUCIE COUNTY - FORT PIERCE FIRE DISTRICT
- Via LGR for Site Area and General Emergency Status During Unusual and Alert BDP will notify the counties.
ST. LUCIE PLANT INITIAL NOTIFICATION FLOW FIGURE 1 /R11
Ptge 25 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 i DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR i PROTECTIVE ACTION RECOMMENDATIONS <
i FPL is required to provide county and state goverruental authorities with [
recommendations for protective action to be taken by the public during h radiological emergencies at the St. Lucie Nuclear Power Plant. I i
The responsible authorities are the State Bureau of Disaster Preparedness O
(BDP) and St. Lucia and Martin County Offices of Disaster Preparedness.
Due to the large political and legal ramifications of these recommendations and the potential impact on FPL, the following format and content should be used:
- 1. If the emergency has been classified as a GENERAL EMERGENCY and NO OFFSITE dose estimates or field survey results are available, refer to figure A-1 to evaluate offsite protective action recommendations.
- 2. If the emergency has been classified, and the offsite doses are LESS THAN 0.5 Rem whole body or 1 Rem to the thyroid at I mile over the projected duration of the release, no protective action is recommended. This should be reported to BDP and other outside agencies who inquire as:
" Based on our current assessment of all the information now av,ailable to us, Florida Power & Light recommends that you consider taking the following protective actions (PA) - N0ffE.
. This recoramendation may change in the future, but we cannot
. now say when it may change or what it may change.to."
- 3. If the emergency has been classified and offsite dose information is available (from any credible source), use the dose information to enter the appropriate estimated offsite table in Figure A-2 (PA with offsite dose estimates for greater than or equal to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration) or Figure A-3 (PA with off site dose estimates for less than 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration) . The -
appropriate recommendations can then be made. For example, a release has .
occurred at the St. Lucie Plant with a projected duration of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the wind direction is from the NNE and the projected offsite integrated (2 hr) thyroid dose is 10 Rem at I mile, 2 Ren at 2 miles, and less than 1 Rem at 5 miles. Referring to Figure A-2 (PA with off site dose estimates for greater than or equal to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration) the following recommendation should be made:
" Based on our current assessment of all the information now available to us, Florida Power & Light Company recommends that you consider taking the following protective actions:
- 1. Evacuate all personnel between a 0 and 2 miles radius from the plant.
- 11. Shelter all personnel between a 2 and 5 mile radius from i the plant who are in sectors J, K & L (refer to State of I Florida Fixed Nuclear Facility Notification Message Form, 1 Page 17 Entry 12) 111. No protective action is recommended between a 5 arei 10 mile radius from the plant /R11 '
1
Pega 26 of 29 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 11 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR PROTECTIVE ACTION RECOMMENDATIONS .
r (continued) '
t
- 3. (continued)
This recommendation may change in the future, but we cannot now say when it may change or what it may change to."
- 4. For other emergency conditions which may occur, enter the table for those conditions, determine the recommended protective actions and formulate the appropriate message in the above format and transmit it to BDP.
/R11 4
e 8 e
e e
, . -l Pago 27 of 29 i
E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 11
, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ;
[
FIGURE A-1 (
PROTECTIVE ACTION RECCNMENDATIONS BASED ON PLANT CONDITIONS DISTANCE FROM PIANT/RECOMMENDAT70N* .
l 0-2 MILES I 2-5 MILES I 5-10 mil.ES l GENERAL EMERCENCY7 NO l N 1 N l N l YES i
CONTAINMENT HIGH RANGE NO MONITOR READING 7 l S(CR) { S( CW) l N l
> 1.47 105 R/ hr
! l l
.
- e
,733 LOSS OF C0tTIAINMENT NO INTEGRITY 7 ) E(CR) l E(DW) + } E(DW)+l . i 1
'l YES l E(CR) i E(CR i E(DW) + l
- LEGEND OF ABBREVIATIONS N - No protective action recommended S - Sheltering recommended E - Evacuation recommended DW - Downwind sectio (+ 2 adjoining sectors F RS - Remaining sectors CR - Complete circle around plant at specified distance
/R11
Pcge 28 of 29 E-PLAN IMPLEMENTING PROCEDURE No. 3100021E, REV. 11 r DUTIES AND RE S PO NS IB I LITIE S OF THE EMERGENCY COORDINATOR FIGURE A-2 PROTECTIVE ACTION RECCMMENDATIONS BASED ON ACTUAL RELEASE (CREATER THAN OR EQUAL TO 2 ROUR DURATION) WITH OFFSITE DOSE ESTIMATES (used in preference to Figure A-1) b&
WHOLE BODY OR THYROID DOSE l0-2MILCSi 2-5 MILES f5-10 MILES l DOSE (RDi) l (RD1)
< 0.5 < 1.0 ;! N I N l N l _
> 0.5 '
~
> 1.0 lut .
but _l S(CR) i S(DW) l S(DW) l
< 5.0
< 1.0 i
> 1.0 > 5.0 but but j~
< 5.0 < 25.0 S(RS) S(RS)
> 5.0 > 25.0 J E(CR) l E(CR) l E(DW) + l S(RS)
NOTE:
If the duration of the release is petjected to be less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, usa Figure A-3.
- LEGEND OF ABBREVIATIONS N - No protective action recommended S - Sheltering recommended E - Evacuation recommended DW - Downwind section + 2 adjoining sectors l RS - Remaining sectors CL - Complete circle around plant at specified distance
/Rll
Page 29 of 29 E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REV. 11 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE A-3 PROTECTIVE ACTION RECOCENDATIONS 3ASED ON ACTUAL RELEASE (LESS THAN 2 HOUR DURATION) WITH OFFSITE DOSE ESTIMATES (used in preference to Figure A-1) ,
&t WHOLE BODY OR THYROID DOSE l0-2 MILES i 2-5 MILES l5-10 MILES l DOSE (RDi) l (R*24)
< 0.5~ < 1.0 J N i N { N l
~
> 0.5 > 1.0 but Tut _l S(CR) ! S(DW) l S(DW) l
< 1.0 < 5.0
~
> 1.0 > 5.0 .
but Tut j* S(CR)
~
l S(CR) + l S(CR) l
< 5.0 1 < 25.0
> 5.0 > 25.0 J E(CR) i E(DW) i E(DW) + l ,
S(RS) S(RS)
NOTE:
If the duration of the release is projected to be less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, uco Figure A-3.
- LEGEND OF ABBREVIATIONS N - No protective action recommended S - Sheltering recommended E - Evacuation recommended DW - Downwind section + 2 adjoining sectors RS - Remaining secters CR - Complete circle around plant ac specified distance l /R11.
l l
Pega 1 of 20
[
]
FLORIDA PO'4Ek & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN D@LEMENTING PROCEDURE I/3100022E, REV. 10 IW l.0 TITLE:
CLASSIFICATION OF EMERGENCIES
2.0 APPROVAL
Reviewed by Facility Review Group August 8, 19 17 Approved by K. N. Harris Plant Manager An esis e 19_I3 . __
Revision R by Faci}iey Review Group S' 3'8e ' '-: + 7 f 19 h Approved by //pviewep/A
//M/ M b V.P. Pwr. Res. _ Ndd 2419[
by Revision 9 R Approved by_
ewe ds Facil).ty Mr V.P. Review Pwr. Res.Group h
M a >2. a, 19 f19 F/
P/
Revision 10 Rev v df,by F5G /) M usu W 29 1982.
Approved by #4,//#M/ Dir. , Nucl. Energy E./ 1982.
/ . .
3.0 SCOPE
3.1 Purpose This procedure provides instructions on the classi-fication of emergencies at St. Lucie Plant.
3.2 Discussion ,
In order of increasing seriousness, these are:
Unusual event Alert .
Site area emergency l General emergency A gradation is provided to assure fuller response preparations for more serious conditions.
3.3 Authority This procedure implements the St. Lucie Plant Emergency Plan.
s Page 2 of 20 FI.ORIDA PC'a*ER & LIGHT COMPAFf I l ST. LUCII M.A.fY UNIT NO. 1 EMERGENCY PLAN IMPLWENTING PROCI:XTRE
- 310002:1, REV.10 wi
3.0 SCOPE
(Continued) 3.4 Definitions 3.4.1 Unusual Event - This classification is represented by Off-normal events or conditions at the plant for which no sig-alficant degradation of the level of safety of the plant has occurred or is expected. Any releases of radioactive sacerial which may have occurred or which may be expected are sinor and censeitute no appreciable health hazard.
3.4.2 Alert - This classification 's represented by events which involve an actual or potential substantial degrada-tion of the level of safee)- of the planc ecmbined with a potential for limited uncontrolled releases of radioactivity from the plant.
3.4.3 Site Area Emertenev - This classification is composed of events which involve actual or likely sajor failures of plant functioca needed for protection of the public combined with a potential for significant uncontrolled releases of radioactivity from ,the plant.
3.4.4 General Emergenev - This classification is composed of events which involve actual or d- d"ent substantial core degradation and potential loss of containment integrity ceabined with a likelihood of significant uncontrolled releases of radioactivity from the plant.
4.0 Precautions -
4.1 Conflicting Information
'4 hen apparently conflicting information is available, the condition shall be classified at the sost serious level indicated.
4.2 Judgmental Decision If, in the judgment of the Nuclear Plant Supervisor (E=ergency Coordinator), a situation is sore serious chan indicated by ,
instrument ceadings or other parameters, the e=argency condition i shall be classified at the nore serious level.
l
t i Pege 3 of 20 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PIANT UNIT NO.1 EMERGENCY PLAN D9LEMENTING PROCEDURE (3100022E, REV. 10 ml 5.0 Responsibilities 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 fascist 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.
5.2.3 If an emergency has been declared the Nuclear Plant
- Supervisor shall become the Emergency Coordinator and retain,this position until relieved. ,
6.0
References:
6.1 St. Lucie Plant Radiological Emergency Plan 6.2 E-Plan Implementing Procedure 3100029E, Duties of Individual
- Discovering Emergency Condition ,
6.3 E-Plan Laplementing Procedure 3100021E, Duties of Emergency Coodinator 7.0 Records and Notification The basis for classifying an emergency condition shall be recorded.
1
i 1 Pcg2 4 of 20 [
FLORIDA POWER & LIGHT COMPANY
, ST LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE
- 3100022E, REV. 10 mme
8.0 Instructions
8.1 The Nuclear Plant Supervisor shall initially classify a situation as soon as possible after becoming aware of the situation. The classification shall be made on the basis of readily available observations and/or calculations and should not rely on sampling and laboratory analysis.
NOTE: Within 15 minutes after the initial classification, the state and/or local agencies listed in the appropriate check list in EPIP 3100031E shall be notified. /R10 8.2 If subsequent Laformation of a more detailed nature (e.g.
sampling results) becomes available after the initial classi-fication has been made, the event shall be reclassified by the Emergency Coordinator if appropriate.
8.3 The Nuclear Plant Supervisor shall classify events in accordance with the attached Classification Tables. The event shall be classified by matching the actual situation to the one most closely approximating it in the tables.
8.4 Classification Tables are provided for the following categories:
- 1) Primary Depressurization
. Miscellaneous
- Abnormal Primary Loak Rate Abnormal Primary / Secondary Leak Rate Loss of Secondary Coolant
- 4) Accident Involving Fuel
~
Fuel Element Failure Fuel Handling
- 2) Abnormal Radiation, Contamination of Effluent Release Values Uncontrolled Effluent Release High Radiation Levels in Plant
- 3) Fires Lasting More Than 10 Minutes
- 8) Degradation of Control Capabilities Engineered Safety Features Loss of Containment Integrity Loss of Alarms
, t -
Pego 5 of 20 *
=
FLORIDA POWER & LIGHT COMPANY .-
ST. LUCIE PLANT UNIT NO. 1
' EMERGENCY PLAN IMPLEMENTING PROCEDURE I- l
- 3100022E, REV. 10
8.0 Instructions
8.4 (Continued)
- 9) Hazards to Station Operation Aircraft Toxic or Flammable Gas Onsite Explosion Missile Turbine Failure
- 7) Electrical Malfunctions l Loss of Power
- 10) Security
- 5) Natural Emergencies Earthquake
. Hurricane
- Tornado Water Level Abnormal
- 6) Miscellaneous Events Contaminated Injury Abnormal Temperature
- Abnormal Shutdown .
I i
1
-1 w - _ _ _ _ _ _ _ _ - _ _ _ _ . _ _ _ ._. -
Page 6 et 20 l'kIMARY taEPRESSURIZATloN Page I of 4
'N,N.
gygg.g C4. ASS UNUSUAL EVEstt AI.ENT SITE AMEA t}tERGENCY CENERA!. tJstEL t'NCY
%~
MiSCElIANEOtlS A) UngianucJ ,1,nia bt M of ECCS >
4.ume of 2 ut 1 i i e Mme ga uJu( t (Emergency Core Coul bg Sgute_m,)
- l,arrier ult h miens tal f us loss
- 1. ECCS pumps runnlag me indt- of the al. l s J cat =J t.y amatus maps. AND,
- 2. ECCS h=4 Jus la.ulattuu valven (Any suu ut slae fulluulug tus.Ji-open am ludicated ty valva puntatuu luJ t ta t ions lights.
- stuna esist meJ th.e s tal t J 8 e.
GH
- laminent.)
b) Sathy or sellei valve imits 8. Couftsmed fuel St.J Jamage.
Eu clame_ 2. Cout t amed thCA
- 1. Reactor tuuleus mystem (RCS} 3. Conf 8sm=J tuntalemmeset inte-
- m. Indicattuu ut flou .
grity 4.seest.ed mud s ne.ut its thauush premmurider , restused.
smilef valves em tuJ1-cat =J un the acuumale velwe fluu muuttur ANil I.. NCS psummune drope au 4
It4M3 est i. .
- 2. M.stu Steam System
- m. Unusuit Jerremue f u ps amaus taer piemmuse maal level ultle decreamlug Tava Atgl ,
- b. Abaussmal Jsup la mie. men genusatus psemuure au lema t haea 500 pale, AND
- c. Visum! us auditale ver t f t-cattua. us necem relief litstug.
ACflON 1. Complete actluum i1steJ uni
- 1. Compleam me;tauun listwJ un slee UNUSUAL EVENT CllECKLlW.
CENkkAL EMERGk'NCY CitECELIST.
I
F Page 7 el 20 PalHANY DEPRESSUMlZATlawa St. net 2 of 4
- 08 ASS gyg g.' ' s, UNUSUAL kVt.NT A!Lki
' SITE AREA EMERGLNCY CLNLEAL LHENGLNCY ABNt*HAl. PMINANY WCS leaka,ge_gsamie[_stemn alloueJ kCS leak gester than *)O gg m - IAM:A, great er tisen cas=cis1d ItAK _RA,TE _ lifectualcal Specif acer tone gasmary to armonpl.ese A setemme 1644 octusscJ os 8m in
- 4. RCS water traventory balanos @gla p.mpo psussens seeultlag tua Asplicates (1) Changing /letJown mismetcle (I) Unusual decrease in pass-
- 1. greater i gams unidentitled backed up by kCS water. IW.A Dume Omiculdtlun LPir leakage. mustaer level anJ pressure 3100ul)E AppenJia a wuskel.eet 4*R_. luventusy balmace indicatang witt constant T(eve). AND ,
- 2. gameser than 10 gae adesiti- > 50 CPH mnJ < !)2 gge valuem in sacene of I k/HR fieJ !==kage, 41 (2) Makeup rate grestes El ma (ulaule teoJy) ur mis sategrateJ leakage. AA sepacity of 3 changing (2) Contalement or plant vent Jose of SR (tlaysutJ) og 8 lumpectfun <= vents any NCS peeps (1) gpe) AND amJimatun procem e.outtur cann t e t sunent Belgte smuge sadiatlun psomuure bouseJes y leakage. (3) Contalsment premause *2 ,ou t gor y ester s taan or equ.a t tu re.Jiseg above jiosmal. puis, ur containment 3.47 a 10 N/lis (pu.a IMA asJamtion monitors i s>Il- ,,,,,ggas , g,, g , e g. a stNx) ./l.
case above nosmal v.elueen. g g cyggg g,,,p,.,g, gy ) K(ION 4. Cumplete aulune llancJ on 1. Complete m.sluna listed un 1. Complete actions limacJ also UNUSHAL EVENT CllECEL8ST. 1. Com. plea s ac t eueim lauted on AB.ERT CHECKl.lST un SITE AREA EHEkCLNCY GLNERAl. tNENGEta:Y CllECEl.lST CalECEl.lST
/NIO
tage 8 ut 20
- PRINAkV DEPkESSilklZATIDN St.e= t 3 of 4
\' CLASS
~
EVENT UNUSUAL. EVLitT ALERT SITE ANEA EMLRGENCY CENk1AL l.HLkCLNCY ABNONHAl. fillhAu{ RCS puj SEC 3.cahage Create d h gytJ gsome falluse of one steam RaplJ f ailure of stemas _ To SEQWibAuY l CPM. generator ts. lee wigli loss of LEAK RATE generator tut es wit h a los. g . offq)te_ power (w/l charming pg_, of f-alm Lower (> cha'5 P1 l'E 8 I. RCS Water lavesitor y balance gggyL capacity) Indicates:
- 1. Unusual decreasu'in premiurizes (1) Unusual Jecsemma i p.em-A. Ogsater llaan I CFH psessure and level witti muriser preneure and levst un8dentified leakaga AND ce,un t ant T ave., followed ley; witta constant f(ave), AND B. BluwJuwn psoce m moultors 2. Alauve nosamal or increasing (2) Above anosmal reaJange on '
anJ cunJensats als ejector steam generator teluwJow.a and redission psos.ema monitura psuceme moonitor remJing :undensats mit elector ra dia. fur useam generator 1,1cw-alove nusmal us tun psuceus awailto se Jings, down anJ condensata air lucreamtag. gi elector, AND
- 3. l.ome of slie 6.9 EU ment.4.16 (3) Isas of al.e in.9 kW anJ KV I,ummes (IAl, R&2, IBI, 182) 4. 3 6 kV l>umsen (I Al, I A2, 04 IBl. IB2), AND kac h ilure .f usuam generm5or (4) Simultaneous unusual tulies j> chargh.g pg ypacityL lacsemme in one atuaan genesator 'as psemmune and I. Unusual des:roase Isa psenanut taes level.
psummune said level, with cueistant Tav . AN,,N
- 2. Simultan.oos unusu.st increase en one steam gdierator's psensure and level fullowed ley;
- 3. AI,ove noramal steam genierator telowdown anJ mir ejector radiat loan psocgmu men.4 ltor reaJings.
ACTION .
- 1. Complete actions listed un 1 Complete actions listed paa
- 1. Complete actions !!sted the UNUSUAL. LVENT CilECKLIST. 'i AB.EkT CllECKl.lST . usi SITE AREA EHkRCENCY Cl4ECKLIST.
O
,pp!MAkY l>tykESSukl2ATIOtt #E" * ** 8 j Sheet 4 uf 4 N* ClASL EVLNr '~ ~. UNUSUAL. LVtNT ALI.RT SITF \kEA EMLRCENCY CENERAl. EMEkCENCY
- _ - _ . .l l
Ipg oF SkdWDAk) MsM A geressustration of Major eseme leek with greater Halor mteam leek wit h greates umIANT_ merunder u lJe with no primary _ than 10 gge primary /mecosularn than 50 nie y degry/secunJary _ so accos.Jery tembe. leak reta leak rate anJ (nel Jama n lay - Jated I. Unusual Jacrease in preneuriae 4. Unusual decrease tu pressurises pasmuurs anJ Inval with psensure ased level, witti 1. Unusual decseamee lie decreaming T.ve ANil Jocreaming Tavee _A_ Nil; presmustser psensuse and level with Jocreaming T e ,v,
- 2. Simultaneuum ubanosmal Jrup in 2. Abnusmal Jtop la main stems ANDL Halse Stoman es steam or asens generator presmuss generatur paennute to less tu < 500 pela, ANDj 2. Abemusmal daup in main stemas aloess 500 pale. es steam generatos premmure
- 3. Steam generator blowdown and to < 500 pale, M g cussJensate mir ejector radiation psoceum anontture 3. Steam generatur bluwJuwen auJ lamilcate above normal, (OR, cueideensate mir ejectus known ps! mec leak ut i 10 smJtetton process monitusu ,
gam) . Indicats above sosmal, (OM, kauswa pr l-sec leak ol 2 50 gge) .
- 4. Fuel Jamage um laJicated by last kamewn prismas y sample.
ACTIOrd 8. Complete actluna limted osa 1. Cumplete actlueim listed osa 1. Cumplete actions listed gl.a ONU:auAl. t'VEtif CllECKl.!ST. All'kT CllECKl.lST. een SITE AkEA k.NESCENCY
. Cilk CE LIST.
IP o
F. age tu ut 20 ACCIDEPTT INVul.VING FUEL j Cl. ASS " EVLa(T UNUSUAL EVtJIf ALERT l SITE AMEA EMkitGENCY CLNLkAL LMkkULNCY FULL kl.kMhttf {uel Jeamage inJ acet tuan Fall uke Severe loss of f uel cloJJts.g. yCe Jamages ult h Inade.guagm. A 8"I#888 IW'8 I
- Ing d h coolant guma tallure _ "C' a a at 0d in
- 4. LetJ;=ss ludans process muuttur
~
lea. ling to gross inel failure cooll s JetesmineJ 1.y L I# F8**df*** 8 8**I L IS*g ins atmas 8pituwad by loca Nee calcialetion
- n. Cua(ismaal kCS m.esaple lewitcattug (1) 1.madown audina psucem. (I) kCS l-134 activity ~> EF!F ll000)iE AppenJia a uus k-
- 1. t:oolant estivity geentes 275 uCt/al, munstur eles=m,ANM al.a. : valuem in ea .=me6 ut i N/Ilu tien al.e Tesh Spec limit sur (2) RCS temperature witteln 20" (uholet.udy) os men Intessated ludius sepike Figure 3. 4 - 1.A Ni]
(2) kCS l-131 octivity 3 ut T(mat) AH3 Jose of SR (aliyaold) or 211 oCS/al (3) loop Ar 244F
- 2. Coulant activity geester ti.mu ,
contatument litri. s.agge s .adiat lun IDD/E uct/ gree specific act. 8 muuttur > l.47 m 80 N/fle
, (punt EUCA moni tua m allMMS ma /hs FUFL ll. ANial. LNG ACCIDFNT Fuel I.anJiang g Jent wl. i c h _ if ClistkN luules abled Halor el smaste to spent fuel _
teautta in the telease of rmJio- in cuntainment or f el Handling activity tu contalument or Fuel BallJing /8 tit' llanJIIng BullJM_ (1) Step incavame in it.e (l) Utrect lufosmattuu tros iust se.Jings uf radiation leanJling livsma.aniel !saill-sating tiat an-larmJlat=J munitorm in slaa plant veut ' fuel ammembly 1.4m been annJ/or Isa al.= f uel 16.anJI tug tsullding. Ayg Jamaged muJ gam bubbles are (2) Damage to neose al n one escaping AND__ (2) Ammoclated area or psucess luut musembly 43 ( 3) Uncuvering ut amore alia i 4.ne amanttor cleannelm are apent inel ammembly in II.e ala.mtug. opent fuel pit.
.s-ACTauN
- 1. Cumplete actions listeal un 1. Cumplete actlpus 18mte.1 8. 4'umplete actions limacJ 1. Cumplete arttuns limacJ un gl.o UNUSHAl. EVEt4T CllLCEl.lST. un Al.I'kT CllECEl.lST un SITE AREA LHENGLNCY CENEkAl. LHEkGt.fa:V Clit1El.lSt.
. CalECKl.IST O
O _ABNOkttA1. RADI ATION u nattfAMINATION Ou PagI 11 ut 20 EFFIDENT kil EASE val.11ES Cl. ASS UNUSUAL EVENT ALERT kV t.itt SITE AREA t)tEkCt.NCY w CENEk.AL t}ttkCENCY a UNOaN{kul.l ED kadiological effluent Tech. Syen A telemme tems occurseJ*ur is in A solemme leam occurred or im EFFLUENT BEllASE I.imite esceeJ4J progsman tlast la 10 timum Elim A salmass hee ucsuste r 8m h Isa psugseman re= ult inag Isas la progream temulting In;
- 1. Plant affluent muuttor(s) 7.S. limit (ma shown I.y sample / LOCA laoue Calculottua Ertr h
exceed alare metpotut(s) musvey) 3100033E Appendia B workslect IDCA laome Calculottuu 6. PIP followuJ 1y
- 3100031E Appendia 5 wuskal. css
- 2. Confirmed munlysis results for valuem in exce== of 50 HN/Ilu waluem See exces= ut I m/uu gancous or it.gu!J relemme (whole teudy) 250 HR/ila (wieolm 1.udy) or een liitegtered (thyru!J) for 1/2 Isour Ok Jose ut 5 R (thysuidl..
e,Inicle ence=Je Tea:halcul Spect-fication limism. 500 Hit /lin (wholm I.ualy) 2500 coursinment blyle smugu emJiation MH/HM (thyrold) for two mies at munitor > l.47 a 105 It/he ele site leuusedry. or Cont s t eement liigh stange (Pont I or 2 Mosaltur eitkkJ ms/he if CllMkN leioper.'le) Mediatsun Moultur >7.3 m 103 k/ha
<nto Hil;at NADI ATION l EVER.S IN PI AN't til 5It EmJ1stlosa levels or liigli airl.utum contaisituma loon whicle lanJicates a severe degradettuu in the control of radioactive motorials (1) InstalleJ tmJintion musI4tus-lug stations lpJia' ate el.uosas. ally liigli s ediat ion levels Ok, (2) lustalled mast is ne part icu-Inte or toJiue activity , y smani t=4 m indicate abuurmelly higli levels. AND_
(1) Levutu > 4000 times suernal are conflamed by erem surveys mee.8/ur mainlystis ut grab mamples. ACTIOta
- 1. Ot*mplete actions llbted t. Cumplete actions listed
"" 1. Cumplete ac t ion = S tut tJ u.a RN 11 1. E I IL I S '
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-xT N E SN SE N
O V hH I NE t T L A
, _ _ _ _ . _ _ _ . . _ . . --- --- -~ ~-
I t i * > , I l Page 15 ut 20 11AZAkDS TO STATION Ol'EkAYlON CLASS EVENT llNUSUAl. EVEftf ALEkT SITE AkEA EHLkGENCY CEhEkAl. DitkCtNCY AlkCRAFT V8muel ag g l88 E i'I un-site ur 'ofunusuas aircraf tfjicFelf Creal' A ' ' I " ' "I' ""' I " " d ***g i sig Aircraft crash on site plant etsuctures. metivity owes facility, Jamaging vital plant s y n t eses ut utsuctures. ONSITE EXPLOSION Visual or muJau inJ4cattua of Damage to factitty by maplustose mas empluuluss seeds us on-sit e. 'amage su mate shutJuun ' ut.le:la af f ects plant upuset tun. equipment fsum almellem us
, emplosion Tuxtc Ok FlAH- --
HABlE CAS Indicatiusa (winual ur utleeswlse) Entry of Eualc or flmummable . . . _ _ _ of a secar or use-mits tuale us goes vastu aretam poteest f ally Alarm $suficatlun in sucelwed flammable gas asleams. eaan Dutoctu-Clelug og tualc or affecting plant upeastlun. timem.ble gas 1.m. Jillumed 1 , into vital meeam. HISSilES - Visual or anJ1ble t amilcut tues of staatte Impact on plant IAsmage su mate shutduun equip-stauctures. neut fium alumiles or emplumaun. THkblNE FAllHRE -_ Visual anJacalgun that the - . _ . _ _ _ . tusblue caesing has been penetssted by bloding. ACTIOtt ._
- 1. Cameplete actions !!sted un 1. Cuamplate actione listed the UNUSUAL EVENT CHECKLIST. un AI.ERT CilECKLIST.
I. Cumplete actfune Ilmted
! un SITE AREA EHEkCENCY CalECELIST.
I I O e 9 e
l _ E ECimlCAl. HAIJUNCTlW4 " "' g.g UNUSUAL. EVEffr Alt.RT
- SI1E Akt.A IJtkMCENCY GENERAL titLNCENCY I s . _ __. _ _
latSS or etMtra lose ut uit-stem power ur lose of one-sit e AC_ g>ower capabilit1 fuse of offelte e ver anJ lose beam uf of f et te gunner and of all unatte AC power _ loss of onelse AC power - I. Tushtsee generater ts agewitte __15
> stoutes plant startup transfusmere I. Tus bisam genesator trips vasta plant startup trana- 1. Turbine gene otor trips i.navailable for services OR. formers noss-functional, ,AND;
- 2. Ioms of voltage un botta IA) witta plant startup
_AND lb) 4.16 KV t,umman tur 2. transfusmere eunavailable Fallume of t.utti emergency for anervice. Ay; amare al.ana 15 secosiJa. illemet gensa4turas to stest or mynclisuniae 2. Sustained falluss ut boat. ou emessency Jtemet ges es - o tura su maast ur synclruntre fur > ti 1.ums o f a l l unm i t e l_aC g= sue r minutes. . I)rup isa A and a llc bus om voltages to < 70 volts. l_.uam ut all vital unmite DC mer for > 15 minutne l Sumasined drop in A and B
" DC Luz voltages to 70 vJc f aa t
> 15 minutes.
i Apg 1. Cumplete act iuns lista:J uit 1. Complute actions listed I. Complete actfuna Itated UtalSUAL LVEffr CHECELIST. un ALERT CitECKLIST. ua SITE AREA ENEMCENCY CllECKLIST. t
. . . . . -~ --
- _ _ _ .. ' l e
S6'CUK11Y DsEkCENCIES '8* # clash (VENT llNUSUAl. EVENT Ag.ggy SITE AREA iMEkCLNCY CENERAl. DethCENCY A mecastSty mie:s t laam beens calleJ _. by sle secutity lurce du ses- A secur ity emes geancy less leceu cetted 4.y slie security fora:e as A security essergency lia m puume tu une or muse of al.e 8tema prugreened to !!ae pulsit slaa t A muccennful takeuweg ut t ing listcJ 1.eLuu. JeflueJ la tl.e Safegua:Ja plant luctuding abe Control Couttugesacy Plan. takeover of the plant la paubable Ruum has occuss=J.
- 1. Bomb tbsmat
- 2. At t ac k s lag em t
- 3. C8vil distusbance
- 4. Prosected esed lutrumluu S. Sabotage etsemapt
- 6. lutessaal distusbance 1
- 7. Vitel asca intsualuu
- 8. Security lusce mtsike .
ACflON 1. Cuemplete dctluun limacJ un UNUSUAL. EVt'NT ClitfELIST. 1. Cmaplete actluus list ski, uu l. Cuenplete acttussu llescal usa Al.LkT CllECKl.lST. 1. Cuesspletes ac t lualm listed una SLTE AREA LMERGENCY CHEt:K-LIST. CENLKAL LNERGENCY CUECKl.IST
-l 0
e
s NATURAL thERGENCIES Page to ut 20 CSASS EVENT " *
~ "
~FANTINMIAKE An eartlequehe has occaeramJ am An eas tleagueke occuss wtnista indicat.J un eartl.quaks force An eartl>guake occurs wtaicle muntaus SMi-42-II (punt acc8Jant restatorm >osE (0.Sg) op HOAA registesu >SSE un NOAA melmeic melmeic equil eent. equipment panel) and m uiesuciated on RTGS 106 (SM and $46).
_ld)M NICAHE Mutilicat tues by PBAA (Weatleess _ - . . - Busumu) shat 4 iurricane watcla Hutilicattuen by al.e Westlaer Busemas of alie appsuesh of a Not tilcatlose by ties Westl.er im Isa ellect. Bureau of al.a approscle et a heatricana,wltle winda e.y to design baalm (J20 mph) levalm 16usricaner with wishls
- Jemigia i
- 1. amin (120 mph) levolm TuMNAlma Nutilicat tun ley NOAA (Westi.or .
Any tornaJu utsiking incility -- Buseau) that a susnedu wettle In las af f ec t. WATEk LEVEL. - ---.~. l SG yema iluuJ at low wates, F luu.L. Iow water, lautricane . _ _ . _ _ - . . _ , 1.us t leanet me.t ge 43 uthe:r ut,anussinal Fluab,lowwages,liussica.ies A11HOKMAR. wates level a;unJittuna maarger, OR, utlies' at.nusmal water murge a3 ut heir at. anus siwa t w.iteet level conditions cauem the atuam Jrminage nymtem to be emceeJed. level cosaJittuna cause vital
- 1. Hutification ley NOAA (Westlaus- equ alment to fall.
Bureau) 4844 mineurendt water luvul cosmittions are etapact eJ ur mse occuring, or i
- 2. Visual matardige by stettun a possunnel th,4t water levelm as er apps **echlug usuam dralnage nymsem capacity.
~ ~ ~
AJ3 ton 1. Cumpiste actions 18 stud un 4. Completen actions 18stvJ the IJNOSilAl. EVLNf CalECfl.lST. un AI.EkT CilECKl.lST
- 1. Complete actions listed on SITE AREA EMEkCENCY CalECKLIST i .
e
HISCEISAN&2RIS EVtNTS "'" ' "' Sheet i of 2 l EVENT UNUSUAL EVEstt A11MT SITE AREA t.NEkCt.NCf Ch24ERAL l'inNGENt:V ARteHuht. . Al,s.us u l cuo h..t temperdture __- IE.T$kA.IUNEl M L/SE..E'***ureg elenonm.at fuel t'RESStjuE, temperature w
- 4. Sul.cuuling energin sauniger imlicmase tems than 20 F mut -
coutans. 1 ' 2. liigt. cat loot les temperature to lumn aluna 20"F tielow al.a mesuant aan aesapmaatuam.1
- 3. Plant incore ti.camucouplem indicate atenusmat fust 4 tempesasusum.
1 41sNTAMI NATFil Any runtamtmated individual im _ _ _. _ . . INIURT tamesmposted utt-mile to a 9 1.umplaal fus tscassent of injutten. l I ACTLON _.
- 3. Complete act iuuu listmJ osa ..
llam UNUhuAl. EVENT CilECKl.IST.
. R I
l
i Page 20 of 20 NISCEIIJLNEutf5 EVt.NTS St.eet 2 of 2 UNUSUAL EVENT Al.ERT
$418 AREA RJtENGk.NCY CENERAL EftEkCENCY artil% CONU LT tust$ l. A plant minatJoun la te. guised flee Teclasical Suppoat Center 1. Ylee Emes sency Centerm one mum
. B EQU I R l4W'. IN- ty Technical Specificattune; ,A_ND/Og Near Site Emergency An event resulttug lu encatation CNEASED AWARE- ok, activatwJ; AND, of flee Emergency Closelfication NES_S_
Operattuus Facility are scatwated ,
- 2. Honitoriseg Teams ese
- 2. The silent s e me.ut Juws: under for utt.es it.an Jellt purpomme, to Ceuesal Emergency witte abaun nel, conJi t tuus (e.g. , mutilliamJ; AND, macceJtug co lJoua sates or 3. A precautionary public !=elnent Substmat tel Cas e Damage muJ potential fos setemme ut palmery system pipe cracks sutgigcattuu la made cou-Image amounts of saJtuactivity aim found Jutlag operation). '
cesning an abnosmal pinut au n short pertoJ uf time; mucle condittun tur utt.cr El.an amt Js i t t gaerposes.
- 4. IDCA vitle smalusm et ECCS.
- 2. Lume of Secundssy lleet Stuk. .
- 3. SustatucJ maat ion blackout witta lone of seconJery leemt mink.
j 4. listluse ut contatument lien t s emovat mysteam las slie later stages of mu maclJent tumult-ing in luem ut cont lemient. 1 ACf!Ott 1. Complete actions listed ou 1. Complete actfuus listed ti.e Ute)SUAL kVENT CilECEl.lST. I. Cumplete act iones listed 1. Cusi.pleter mettuum timacJ un Al.ENT CitECEl.IST. un SITE AkEA EHtNCENCY usa CENERA1. ENEkCENCY CilECEI.lST. Cl!ECKl.lST. e
l Page 1 of 11 1 FLORIDA POWER & LIGHT CCMPANY ST. LUCIE UNIT #1 E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E l REVISION 21 t
1.0 Title
. ON-SITE DERGENCY ORGANIZATION AND ROSTER
2.0 Approval
Reviewed by Facility Review Grour July 25, 5 19J_5, Approved by K. N. Harris Plant Manager July 29, 5 19J_5, Revision 21 Reviewed by F R G Tana w 'l 7.- 1921
- Approved by MEd*h- Director Nuc. Eng. f/ 19 1 u
3.0 Scope
. 3.1 Purpose C;-.: ~
This procedure describes the members and duties of the On-Site Emergency Organization (see Figure 1-). , 3.2 ,D,i scussio n During the period immediately following the declaration of an emergency, the shift operating staff constitutes the immediate response organizatit.,a, i.e., the Interim Emergency Teams. Emergency
- requirements take immediate precedence over normal operating responsibilities (as detemined by Emergency Procedures or at the direction of the Emergency Coordinator). Subsequent to the immediate response actions and notifications, off-duty plant staff will begin artiving to form the Primary Emergency Teams and to staff (1 the Technical Support Center. The On-Site Emergency Organization A. ' reports to and supports the Emergency Coordinator.
3.3 Authority This procedure implements the St. Lucie Plant Radiological Emergency Plan. -
Page 2 of 11 i E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 , EMERGENCY ROSTER I
3.0 Scope
(continued) 3.4 Definitions J. 3.4.1 Emergency Coordinator Responsible for notifying off-sit s uchorities, both inside and outside the Company and has feil authority and responsibility for on-site emergency response actions. This function is performed by the Nuclear Plant Supervisor. His (, normal alternate is the Watch Engineer. The Operations L- Euperintendent, the Operations Supervisor or Operations Duty Call Supervisor can assume this function at their discretion following the proper turnover procedure. 3.4.2 Interim Emergency Tosas The Interim Emergency Teams are composed of members chosen from plant shif t personnel. All are qualified in procedures and practices required for the performances of their duties as tema leaders or members. 3.4.3 Primary Emergency Temne
, The Primary Emergency Teams are composed of first line C4 management personnel and others Vho normally work a regular .
Monday through Friday day shif t schedule. 3.4.4 Technical Support Center Supervisor . The person who supervises the personnel and manages the technical support activities in the Technical Support Center. This function is performed by one of the following: - Primary: Technical Supervisor I Alternates Off-duty Shif t Technical Advisors /R21 3.4.5 Operations Duty Call Supervisor An on-call supervisor assigned on a rotating basis from the l plant management staff with responsibility for assistiog the l Emergency Coordinator in notifving off-duty plant staff and the company's off-site emerge. :y organization in the event of an emergency. 3.4.6 operations Support Center Supervisor The person who supervises the personnel and manages the maintenance and operations support activities from the l Operations Support Center. This function is performed by one '
. of the following:
! Primary: Assistant Superintendent-Mechanical-Nuclear ! Alternate 1: Maintenance Support Supervisor Alternste 2: Maintenance Training Supervisor
. Alternate 3: Manpower Supervisor /R21.
s.. . _ .. . . . . - .. . . .
. l Par:e 3 of 11 l l
E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 ' EMERGENCY ROSTER 4.0 Precautions : 4.1 T!It Interim Teams should take action regardless of the fact that the ,
. l Primary Emergency Tema members may be present.
Members of an Interim Emergency Tema may consider themselves relieved only upon the specific instructions of a recognized l superior or the Primary Emergency Tean Leader. Merely knowing that j a superior or a Primary Emergency Team Leader is present does not I constitute a release from emergency duties and responsibilities. I 4.2 At their own option, and with the concurrence of the Emergency Coordinator, Primary Emergency Team Leader of that tean may relieve l their counterpart on the Interim Emergency Teams. 5.0 Re sponsibilities
- l 5.1 Emergency Direction and Control l
The Emergency Coordinator shall be responsible for direction and control, as described in E-Plan Implementing Procedurc 3100021E, Duties of Emergency Coordinator. 5.2 Notification and Communication The Emergency Coordinator shall be responsible for notification a 1 - communications as described in E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator. The Duty Call Supervisor shall be responsible for initial notification assistance. 5.3 Radiation Team The Health Physics Supervisor shall be the Primary Radiation Tean
- Le ader. He shall direct the actions of the Health Physics technicians under the orders of the Emergency Coordinator. The Senior Health Physics representative on site is designated as the Interim Radiation Team Leader with support from Nuclear Operators.
5.4 Plant System Engineerirg The Shift Technical Advisor shall provide the initial technical l support necessary for repair or corrective action and shall be primarily responsible for accident assessment. 5.5 Fire Tema . The Nuclear Watch Engineer is the Fire Tema, Leader. This position is manned continuously, but, if he is not available, the Turbine Operator acts as his alternate. The St. Lucie County - Ft. Pierce Fire District may respond to fires on-site, if requested. C i
Page 4 of 11 E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 EMERGENCY ROSTER 5.0 Responsibilities : (continued) 5.6 First Aid /Decontanination Tean i The Chemistry Supervisor shall be the Primary Team Leader with a Chemistry Technician as his alternate. A Nuclear Operator, trained in first aid and personnel decontamination, shall be the Interim Team Leader. If no Chemistry Department personnel are orr site, any trained employee could act as a First Aid / Decontamination Team member until primary team members can be called in. h 5.7 Security Tean The Plant Security Supervisor shall be the Primary Security Tean Leader with the Security Force Shift Supervisor ac his alternate. The Security Force Shift Supervisor shall act as the Interim Security Tean Leader. Personnel control and accountability are the responsibility of the Security Tema. The Security Tean Leader shall be responsible for notifying the Emergency Coordinator of unaccounted for personnel dotification of occupants in the Owner Controlled Area Shall take place during the security search. 5.8 Rescue Operations Rescue Operations shal*1 involve the First Aid / Decontamination, Team h and the Radiation Tean as necessary. Under the control of the Radiation Tean Leader, entry to potentially hazardous areas shall be ande by the First Aid / Decontamination Team with assistance from the
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Radiation Tenn. Upon notification of the injury, both teans shall respond per the Emergency Coordinator's instructions. 5.9 Re-Entry Tean Re-entry teams shall be formed as necessary in accordance with E-Plan Implanenting Procedure 3100027E, Re-Entry. 5.10 Recovery and Restoration Tean
- ' Recovery and Restoration Operations shall involve all emergency teans as necessary. Tean members shall be assigned from available plant staff.
5.11 Technical Support Center Staff 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 Coordicator of off-site communications to the state and local agencies, NRC and the FPL Off-Site Emergency Organization. The TSC staff shall provide technical support as requested by the Emergency Coordinator and
- f. shall direct itself toward determining current and projected plant
(, scatus and providing in-depth diagnostic and engineering assistance, ar. required . (Y
1 J l 1 Page 5 of 11 J E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 1 EMERGENCY ROSTER
5.0 Responsibilities
(continued) 5.12 odorations Support Center Staff aw The OSC will be the reporting area (Maintenance Office in Service Building) and activity control / management location for available/ called-in operators, Maintenance personnel, HJ personnel, Chemistry personnel and other plant support personnel as needed and available. Their activities will ha supervised by the OSC Supervisor at the request of the Emergency Coordinator and TSC
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C7 site will be the interim OSC Supervisor. /R21 5.13 Emergency Roster The QC Supervisor shall be responsible for periodic verification and updating of the Emergency Roster. Personnel on the Roster shall notify the OC Supervisor when a change pertinent to information appearing on the roster occurs. 6.0
References:
6.1 St. Lucie Plant Radiological Emergency Plan 6.2 E. Plan Implementing Procedure 3100021E, Duties of the Emergency h , Coordinator'. . 6.3 E. Plan Implementir6 Procedure 3100027E, Re-Entry. 7.0- Records: . The Emergency Coordinator shall maintain records as described in E-Plan Implementing Procedure 3100021E, Duties of the Emergency Coordinator. -
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Page 6 of 11 E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 l EMERGENCY ROSTER
8.0 Instructions
8.1 Ukn declaration of aa emergency, the Interim Team Leaders shall contact the Emergency Coordinator to determine the immediate response teams needed. 8.2 The Emergency Coordinator shall notify the Duty call Supervisor to inform necessary plant management and Primary Team Leaders to report to the Technical Support Center for assfgrurent if necessary. 8.3 The Technical Support Center Supervisor shall assist the Emergency h' - Coordinator in assigning personnel to the Technical Support Center or the Operations Support Center. 8.4 Department heads or their designated alternates shall report to the l Technical Support Center where they shall, if necessary, relieve the Interim Tema Leaders, and assume their responsibilities as Primary Team Leaders; or staff the Technical Support Center as directed by the Emergency Coordinator. 3.5 Appendix A is the Call List to assist the Emergency Coordinator in l l initial notification of the Duty Call Supervisor. {
, 8.6 Appendix B is the List of Local Outside Agencies. .
h 8.7 Appendix C is the Duty Call Supervisor'.s Call List. The Duty Call Supervisor shall contact these people when directed by the Emergency Coordinator to do so. e e e*
_s. o . - . Page 7 of 11 E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 EMERGENCY ROSTER (. Emergency Coordinator Nuclear Plant Supervisor 1name (Watch Engineer) Interim (Shift primary Emergency Team) EME2GENCY TEAMS Emergency Tean Health Physics Health Physics (? Representative (Nuclear Operator) RADIATION Supervisor (Health Physics Technician) Nuclear Watch Engineer Nuclear Watch Engineer (Nuclear Turbine Operatog) FIRE (Nuclear Turbine Operator) Nuclear Operater FIRST AID & (Auxiliary Equip. PERSONNEL Chemistry Supervisor Operator) DECONTAMINATION (Chemistry Technician) Security Force Plant Security Supervisor h Shift Supervisor (Response from leader) SECURITY (Assistant Plant Security Supervisor) - Generating Station Reactor Supervisor Area Guard ASSEMBLY AREA (Engineer, Reactor (Outside Patrol) SUPERVISOR Eng. Dept.) RECOVERY AND All Teans and RESTORATION FPL Resources RE-ENTRY TEAMS (FORMED AS REQUIRED DURING EMERGENCY) {.. Shift "echnical Advisor TECHNICAL SUPPORT Technical Supervisor (Off duty STA) Special Crew Supervisor OPERATIONS SUPPORT Asst. Supt. Mechnical (when on site) (Staff Supervisors) /R21 , FIGURE 1
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Page 8 of 11 l l E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 l l EMERGENCY ROSTER I I EMERGENCT ROSTER
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h/f . // Z9~82-Plant Managey / Date Dtn'Y CALL SUPERVISORS MAINTENANCE DUTY OPERATIONS DUTY H. P. DUTY CALL CALL SUPERVISOR CALL SUPERVISOR SUPERVISOR O T. A. Dillard D. A. Sager C. M. Creen C. F. Leppla J. A. Spodick H. F. Buchanan /R21 R. W. Marr B. W. Mike 11 q H. M. Mercer M. B. Vincent R. L. Hayes R. M. McCullers
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M. G. Craig P. L. Fincher /R21 C. L. Wilson N. G. Roos 'f
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' Plant Mana f / Date APPENDLT B LOCAL OITISIDE AGENCIES:
FHONE SERVICE NAME OFFICE EMERGENCY FIRE For additional assistance St. Lucie County-(? if required on fires with radioactive material involved Ft. Pierce Fire dist. 911 Sa:ne NON-RADIOLOGICAL INJURIES 'i' Lawnvood Medical Center M
,W'See Treatment - all hours Hospital admission Dr. J. N. Sims .
. , . - ', Sme Ambulance - all h6ura St. Lucie County - 'I' '
Ft. Pierce Fire dist. 911 Same RADIOLOGICAL INJURIES h ". Transportation - all hrs. St. Lucie County - Ft.* Pierce Fire dist. 911 Same . Interim treatment .'. facility - all hours Lawnvood Medical Center Same Primary treatment , f acility - all hours REEP , Same - Mount Sinai Hospital '
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PHONE SERVICE NAME OFFICE EMERGENCY Local Law Enforcement St. Lucie County Sheriff 911 Fedsral Bureau of Same Inve stig ation .
..o j Florida Highway / .
Patrol . 911 ,
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Explosive Ordnance 66th Ordnance Det. USA .
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Disposal Patrick Air Force Base SITE EXT. OFFICE HOME USNRC Resident Inspectors S. Elrod 410 464-7822 H. Bibb 411 464-7822
'_.8 * . . . . . Page 11 of 11 E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 EMERGENCY ROSTER f* [
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Plant Mana g t /-299z i : Date /R2 ! APPENDIX C ! Team Leaders & Alternates (continued) l PHONE TITLE NAME HOME EMERC'.NCY Emergency First Aid & Personnel R. J. Frechette decon. teaci leader Alternate B. W. Kelsey , I Emergency security team leader J. G. West 4 - Alternate G. A. Longhouser Interim security team leader Capt. of the Guard Alternate Sr. CRT Operator Assembly area supervisor C. A. Pell Alternate M. S. Dryden Technical Support Center Supervisor R. R. Jennings Alternate TSC Supv. (STA) C. S. Cashell G. E. Walling Ops Support Center Supv. T. A. Dillard Alternate 1 C. L. Wilson Alternate 2 D. J. St. John (1)
. C. *.,-- Alternate 3 D. L. Newberry .
, Additional personnel who may be requested by the Duty Call Supervisor or Emergency Coordinator are as follows:
Additional Contacts PSL #1 Control Room Nuclear Plant Supervisor O. D. Hayes Nuclear Plant Supervisor L. W. Pearce Nuclear Plant Supervisor N. D. West ( f {. Nuclear Plant Supervisor C. L. Burton ! Nuclear Plant Supervisor F. G. Davis Nuclear Plant Supervisor M. G. Altermatt I & C Supervisor C. F. Leppla - Quality Control Supervisor N. G. Roos - Mainte. nance Superintendent J. E. Eowers { Training Supervisor P. L. Fincher r Ebasco Corp. PSL #2 /R21 Y
Page 10 of 11 E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REV. 21 EMERGENCY ROSTER {
' Plant Manager #
[MkM /[~ M 82 ' Date APPENDIX C ; i DUT!ffl.L SUPERVISOR'S CALL LIST PHONE TITLE , NAME HOME OFFICE Emer. Recovery & Restoration C. M. Vethy team leader - Plant Manager Alternate: Ops. Superintendent J. H. Barrow Emergency Control Officer J. W. Williams ALTERNATES
, Asst. Vice Pres. Power Res. J. R. Bensen Manager Nuclear Energy C. O. Woody Radiolog,ical Duty Officers -
Amst. Mgr. Nuclear Energy K. *i. Harris . Mgr. of Pur. Res. H. N. Paduano Nuclear Services Pwr. Res. Sec. Supv. Plant R. J. Acosta - Pwr. Res. Specialist D. K. James Power Res. Supervisor J. L. Danek h Systems Operations Power ePer Coordinator l TEAM LEADERS & ALTERNATES Emergency radiation taas H. F. Buchanan - le ader Alternate emergency H. M. Mercer radiaion team leader Alternate emergency G. M. Green or radiation team leader R. M. McCullers Plant Fire Protection W. J. Barrow Coordinator
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Pego 1 of 13 FLORD A PCWER & LIGHT COMPANY ' 1 f' ' ST. LUCIE PLANT UNIT NO. 1 EMERGENCY PLAN DfPLEMENTING PROCEDURE i !
#3100026E, RE7. 7 '
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1.0 TITLE
CRITER11 FOR AND CCNDUCT' 0F E7ACUATIONS i
2.0 APPROVAL
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" i Reviewed by Facility Review Group July 25, 1975 Approved by K. N. Harris Plant Manager July 24, 1975 Revision 5 $ evesi by Fac *cy Raview Group March 20 & 25,19 L Approved by /MI#M V.P. Pwr. Res. h M igr/ }
l Revision 6 ed b Ta Review Group in ay 2. J 19 9l f Approved by _/ 7.P. Pwr. Res. _lu a 2, 19f/ l Revision 7 Re dgby 1982. F M Fa
/ ~qil4d Review Group h u n .-f./2f l
Approved by M Dir., Nuci. Energy 1982. '
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. 3.0 SCOPE: * '
3.1 Purpose This procedure provides criteria for determining if evacuation , f of a local area on-site or the owner Controlled Area should be ' carried out. It provides instructions for effecting an ordered, 'I rapid and safa evacuation of a local area or the Owner Controlled Area in order to prevent or minimize radiation exposure to l personnel. It also provides instructions for personnel account- ; ability. l 3.2 Discussion ! 3.2.1 Accurate classification of emergencias that nay occur ; at the Plant is necessary to enable the Nuclear Plant Supervisor to take the proper corrective action and to ~ know when to initiate the Emergency Plans. For those emergencias involving high radiation and/or the release " of radioactive material to the environment, it is necessary to provide the Nuclear Plant Supervisor (Emergency Coordinator) ' with guidelines that will enable him to kncv when to order , a local area evacuation or evacuation of the Owner Controlled { Area. i f
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_es * . . Page 2 of 13 FLORIDA P0k'ER & LIGIC COMPANY EMERGENCY PLAN IMPLEMENTING PP9CEDURE ( #3100026E, REV. 7 b l
3.0 SCOPE
(Continued) 3.2 Discussion (Continued 3.2.2 A local area evacuacion or evacuation of the Owner Controlled Area nay be necessitated by the Occurrence of any of several events where evacuation of personnel would be necessary to minimize their exposure to C_, radiation. An Owner Controlled Area evacuation will be condveted for any Site Area Emergency or General Emergency.
3.3 Authority
This proce.ure implements the St. Lucie Unic #1 Emergency Plan.
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3.4 Definitions
3.4.1 Assembly Area The location to which evacuation personnel report. In , a local evacuation, personnel evacuate and assemble in , C:," a location designated by the Emergency Coordinator. In an evacuation of the Owner Controlled Area, hvacuating FPL personnel from the Protected Area go to the Site
- Assembly Station on Highway A1A near the north entrance to plant property, while non-FPL personnel and FPL personnel from outside the Protected Area assemble at 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 (1, persons who are required by the Security Plan or Health L- Physics Manual to be escorted. 3.4.3 Local Area Evacuation An evacuation of some portion of, but not all of, the Owner Controlled Area. It may include evacuation of a room, building, group of buildings, generating station area, or other portion of the Owner Controlled Area.
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#3100026E, REV. 7 ; {
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3.0 SCOIE
(Continued) a'
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3.4 Definitions
(Continued) 3.4.4 Owner Controlled Area That portion of FPL property surrounding and including the plant which is subject to limited access and control as deemed appropriate by FPL (indicated by the dotted line on the attached Florida Power & Light property plan, k: ., Figure 1 of this procedure). 3.4.5 Owner Controlled Area Evacuation The avacuation from the Owner Controlled Area of all personnel except those required to place the plau: in a safe condition, the emergency teams, and the guards necessary to fulfill their evacuation responsibilities. 3.4.6 Radiation Control Point Located in tne 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 mrde to : din 1mize 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
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Radiation Control Point or other assembly area until they have been monitored for possible contamination, unless they are injured. Injured personnel shall be treated as discussed in E-Plan Imple-menting Procedure 3100021E, Duties of the Emergency Coordinator. 4.3 Except as discussed in 4.2 above, personnel reporting to the (, Radiation Control Point or other assembly area shall group V according to departments in order to facilitate personnel accountability and monitoring. 4.4 When reporting to the assembly area, take the most direct route ; possible, but do not use any route or area that has been declared j part of the emergency area, or that could result in excessive l individual exposure or injury. 4.5 If an area or building is evacua:ed, any records regarding the persons in the area shall be temoved and taken to the assembly area.
a3 . _ _ . . Pegs 4 of 13 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE J h -
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4.0 Prdsautions
(Continued) = 4.6 Health Physics personnel exiting the RAB as necessitated by an emergency condition of possible radiological nature : shall pick up suitable portable radiation monitoring equipment ! which would be required for re-entry monitoring.
5.0 Resoonsibilities
(- 5.1 The Nuclear Plant Supervisor is responsible for: 5.1.1 Classifying any emergency that may occur at Unit #1. I 5.1.2 Initiating the Emergency Plans when appropriate. l 5.1.3 Initiating the evscuation of any area in which the critaria for evacuation, as expressed in steps 8.1 8.2 are met. i 5.1.4 Providing protective action recommendations to off-site /R6 l authorities per Table 1 in ' 100021E(Duties a of Emer. Coordinator). j 5.2 The Nuclear Plant Supervisor shall act as Emergency Coordinator. 5.3 The Emergency Coordinator is responsible for advising the h
- Security Team Leader of a local evacuation *or an Owner Controlled Area evacuation. This notifier.. ion vill be by the alarm or the PA system. Information needed by the Security Force to properly t fulfill their responsibilities during the evacuation shall be
- l provided to the Security Team Leader by the Emergency Coordinator. {
(See E-Plan Implementing Procedure 3100021E, Duties of Emergency ' Coordinator). l 5.4 The Security Guard Force is under the supervision of the Tant ! Security Supervisor. He serves as the Primary Security Team l Leader. The Security Force Shift Supervisor is the Interim Security Team Leader. l t 5.5 The responsibilities of individuals acting as escorts are contained
? in Sections 5.12 and 8.4.5 of this procedure.
5.6 All personnel permanently or temporarily assigned to St. Lucie plant shall familiarize themselves with: 5.6.1 The instructions given in this procedure. -I 5.6.2 The access routes to the work legation to which they l are assigned. '
Pegs 5 of 13 . l FLORIDA POWER & LIGHT COMPANY f EMERGENCY PLAN IMPLEMENTING PROCEDURE {
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{ 5.0 Re sonsibilities: iw 5.6 (Continued) 5.6.3 The locations of the evacuation assembly areas:
- a. The Radiation Control Point in the Auxiliary Building.
h b. The Site Assembly Station.
- c. The J. C. Public Park on Route A1A, north of the ,
plant site. j 5.7 It shall be the responsibility of each supervisor and depart- $ I ment foreman not involved in the emergency response to report l to the assembly area to assist in accounting for all personnel l under his supervision. I ( 5.8 Security Department Responsibilities are defined in Security Procedure 0006123. 5.9 The Control Point Guard shall maintain' accurate records of all h 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 l tours of the plant site. In an emergency, Tour Guides are l
. responsible for personnel accountability of their respective I groups and the evacuation of their group to the Site Assembly Station in cooperation with the Security Force. l 5.13 Unit 2 Responsibilities are defined in ASP 5.0.
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Page 6 of 13 FLORIDA POWER & LIGHT COMPANY j
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#3100026E, REV. 7 I
b 4 m. 6.0
References:
6.1 St. Lucie Plant Radiological Emergency Plan. 6.2 St. Lucie Plant Security Plan. l (' 6.3 E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator. 7.0 Records and Notifications: 7.1 A list of all persons assembled at J.C. Public Park shall be prepared by a member of the Plant Staff who will travel to that location with evacuees. , 7.2 Records showing that all personnel in the area affected by the emergency were accounted for shall be kept as part of the records of the emergency and recorded by the Emergency Coordinator. (2) . o O e*
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Page 7 of 13 j l FLORIDA POWER & LIGHT COMPANY (: EMERGENCY PLAN IMPLEMENTING PROCEDURE
#3100026E, REV. 7 Er
8.0 Instructions
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8.1 Criteria for Local Area Evacuarion If an incident involves a high radiation field or has caused the release of radioactive material to the environ-ment, the need to evacuate the affected area shall be determined in accordance with the following criteria: O Evacutte the affected local arc 3,in which any of the following conditions occur:
, 8.1.1 Area Radiation Monitor Alarm.
8.1.2 Containment Evacuation Alarm. 8.1.3 Unevaluated direct radiation dose rate reading in excess of 100 mrem / hour. 8.1.4 Unevaluated airLorne radioactivity concentration in excess of 1 X 10'9 micro C1/ce. e h . 8.1.5. Removable radioactive surface contamination in an unposted area in excess of 1000 dpm/100 cm2 beta-gsama over an
. area of 100 ft2, 8.1.6 Removable r: dioactive surface con.: amination in an unposted area in excess of 50 dpm/100cm2 alpha over an area of 100 fc 2, 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 evacusted,
- 4. Any other situation in which the Emergency Coordinator determines that evacuation is appropriate.
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rN Page 8 of 13 - h,o m FLORIDA POWER & LIG'dT COMPANY I I { EMERGENCY PLAN IMPLEMENTING PROCEDURE j ' i
#3100026E, REV. 7 f(f' 0
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8.0 Instructions
(Continued) w 8.3 Evacuation Preparedness 8.3.1 All visitors shall have adequate transportation available on-site to evacuate all members of tk.eir respective groups. 8.3.2 Escorts shall maintain control of groups or individuals (-l to which they are assigned to enable all members of the groups to be located, notified and evacuated. 8.4 Local Area Evacuation Implementation 8.4.1 When the Emergency Coordinator (Nuclear Plant Supervisor) determines that a local evacuation is necessary, he shall, in following Emergency Procedure Duties of the Emergency Coordinator, announce an evacuation using the PA system, giving the area affected, the assembly area and other instructions as required. h . 8.4.2 All personnel in the evacuated area shall stop work, turn off potentially hazardous
- equipment, such as cutting torcher, and leave the area by the same route taken"to enter the area, unless otherwise instructed by the Emergency Coordinator.
8.4.3 All personnel in the evacuated area shall report to the Radiation Control Point in the Auxiliary Building for . monitoring and accountability. 8.4.4 The Radiation Monitor Team shall monitor evacuated , personnel for contamination, (for areas where contamination may be present). h 8.4.5 Injured personnel shall be treated as discussed in E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator. If an injured person is evacuated from the plant site, the person's TLD, selfreading dosimater, identification badge, and keycard should be removed and given to the First Aid and Personnel Decontamination Team Leader. , 8.4.6 The Control Point Guard shall make available to the Emergency Coordinator his records showing the personnel who ' are in the Security Controlled Area.
- o . _ _ _ Page 9 of 13 1 FLORIDA POWER & LIGHT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE
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8.0. Instructions
(Continued) b 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 accounced for. C- the personnel who have not been accounted for. 8.5 Owner Controlled Area Evacuation Implementation 8.5.1 When the Emergency Coordinator (Nuclear Plant Supervisor) determines that an evacuation of the Owner Controlled Area is necessary, he will, in the following Emergency Procedure Duties of the Emergency Coordinator, order an evacuation using the PA system and the evacuation alarm. 8.5.2 All personnel in the evacuated area shall stop work, turn off potentially hazardous equipment, such as cutting torches, and leave the area. All personnel not peeded to place Unit #1 in a safe condition and not on an C."~,, emergency team or otherwise required.on site, shall . evacuate to the appropriate Assatnbly Area. Emergency Teamsshall report to the Administrative Building for assignment. 8.5.3 Injured personnel shall be treated as discussed in E-Plan Implementing Proce. dure 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 Ptoceed 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 shala , hen proceed to the Site Assembly Area - (me Figure 2) .
i 1 . s Page 10 of 13
7' FLORIDA POWER & LIGHT COMPANY (!
(' EMERGENCY PLAN IMPLEMENTING PROCEE*JRE
#3100026E, REV. 7 [ f fj
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8.0 Instructions
(Continued) . 8.5 (Continued) ' l 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. 1 l ' ("T 8.5.8 If the conditions associated with the emergency are l such that the site assembly station area is untenable, l the Emergency Coordinator shall direct all personnel to report to the J. C. Public Park and specify the rotte to be followed. 8.5.9 The department supervisors and foremen shall account l for their personnel and report the results to the Assembly Area Supervisor. 8.5.10 The Assembly Area Supervisor shall assure that all personnel are monitored for contamin,ation prior to 1eaving the Assembly Area. G 8.5.11iheAssemblyAreaSupervisor,theSecurityEorceShift Supervisor and the department supervisors and foreman shall namine all the personnel records available to determine if any personnel are unaccounted for. 8.5.12 The Emergency Coordinator shall initiate a search for the personnel who have not been accounted for.
- 8.6 Security Force Evacuation Implementation 8.6.1 Upon notification of an evacuation, the Security Force Shif c Supervisor (Interim Security Team Leader) shall i' advise by radio all other guards on duty that an evacuation is in progress. The Security Force will proceed with the evacuation of persons and with personnel accountability activities.
8.6.2 The Control Point Guard and the Main Gate Guard shall immediately review logs and badge records to determine - what persons are in the affected area. These guards will be prepared to brief the Emergency Coordinator. The
- Control Point Guard shall verify that all personnel have evacuated the area and report to the Security Team Leader for further instructions. The Control Point Guard shall
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. Page 11 of 13 FLORIDA POWER & LIGdT COMPANY EMERGENCY PLAN IMPLEMENTING PROCEDURE C6 #3100026E, REV.7 ~
8.0 Inhtructions
(Cone.inued) 3.6 (Continued) 8.6.2 go to the Main Gate with his personnel records and avait instructions from the Security Team Leader. 8.6.3 The Security Team shall:
- 1. Sweep the plant site te 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 E=ergency Security, Manager of any circumstances Calch require his attention. .
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Pags 1 of 10 FLORIDA POWER & LIGHT COMPANY ST LUCIE UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E REVISION 2
1.0 Title
ON-SITE SUPPORT CENTERS M
2.0 Approval
Reviewed by F uility Revie Group 'I17ec$ ' J E L f
~ 19 2 [
Approved by _ Mgd,n / V. P. Power ResourcerNdff/r yf,,19 // Reviewed by FRG . /) 171o v., w SL ;L 1982.
' Approved by BZ 4'a h> ie s- / / Director *NED J'- / 1982.
U 4-~
3.0 Scope
3.1 Purpose This procedure provides guidelines and responsibilities for activatica 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 Disc 6ssion , The activities of plant management, technical, and engineering support personnel are an important part of the overall rite response to an accident, and nust be properly defined and logisticall; 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 asse=ble 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.
~ , , Pagn 2 of 10 EMERGENCY PLAN DiPLEMENTING PROCEDURE NO. 3100032E, REV 2 ON-SITE SUPPORT CENTERS I
i 3.0 Scoot (cont): Ji ! 1 1 3.3 Description ;6-=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 Coctunications Equipment The Control Room contains necessary telephone and public address systams for communications within and outside the plant. The Control Room also contains NAWAS and Local Government Radio for cocmunications with state and county agencies. Use of these systems is described in the Appendix.
- The TSC contdins necessary tc? cphones to ce=municate 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 Emergency Plan.
4.0 Precautions
4.1 The TSC and OSC shall be activated upon the direction of the Emergency Coordinator or his designated alternate only. 4.2 Radiological conditions in the on-site Technical and Operational Support Center shall be monitored when required to be in use. Radfacion levels in the TSC shculd be menitored using available l (control room) portable instruments, in addition, Health Physics l Department shall provide an NMC portable monitor to the Technical l Support Center for radioiodine monitoring. This monitor can also l be used for =onitoring the control room. l 4.3 The E=ergency Coordinator shall recommend a suitable location other than the designated areas if radiological conditions warrant such actions. l l l l
Paga 3 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 2 ON-SITE SUPPORT CENTERS 5.0 Responsib111 ties: 5.1 The Emergency Coordinator is responsible for activating the , TSC, activating the OSC, and arranging for staffing through """ the Duty Call Supervisor. 5.2 The TSC Supervisor will be the most senior person available to remain at the TSC of the following: , Primary: Technical Supervisor Alternate Off duty Shift Technical Advisor (See 3100023E, Emergency Roster) /R2 He is responsible for supervising TSC activities, reporting to the Emergency Coordinator, and communicatin'g with tha Emergency Operations Facility. 5.3 Each department head or designated alternate is responsible for reporting to the TSC when called. 5.4 Those reporting to the Operational Support Center are responsible for being prepared to carry out support functions designated by the Emergency Coo *rdinator. 5.5 The Emergency Coordinator has the overall responsibility for the conduct of energency operations and activities and should work closely with the TSC to ensure all information is used in making accident recovery decisions. 5.6 The QC department is responsible for ensuring that records, . documents, and prints are maintained in the TSC or are available for i=nediate use in the Document Control vault. 6.0
References:
6.1 St Lucie Plant Radiological Emergency Plar 6.2 E-Plan Implementing Procedure 3100021, Duties of the Emergency Coordiantor.
7.0 Records
A record of actions taken at the ISC shall be maint _ned by the TSC Supervisor.
Pags 4 of 10 l EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E,Rzy 2 ON-SITE SUPPORT CENTERS L 8.0 Instructions: ;
. L 8.1 Activation ,
I l ' The Emergency Coordinator shall activate the TSC and the OSC for an emergency condition classified as Alert, Site Area Emergency, or General Emergency. 8.2 Staffing The Emer;;ency Coordinator shall arrange for staf.2.ng through the Duty Call Supervisor, Table 3 identifies the TSC staffing requirements. 8.3 Use of the Technical Support Center The TSC shall be used to provide plant management and technical support to plant operations personnel during emergency conditions. A primary task shall be to relieve the Emergency Coordinator of off-site communications to the state and local agencies, NRC and the FPL Off-Site Emergency Organization. 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-depth diagnostic and engineering assistance, as required. 8.4 Use of the Operational Support Cent'er The Emergency Coordinator shall assign available plant staff not - needed in the TSC or Control Room to the OSC. The OSC Supervisor (Assistant Superintendent Mechanical Maintenance or designated , alternate) shall maintain cor:munications with the TSC and report as directed by the Emergency Coordinator or TSC Supervisor. /R2 8.5 Deactivation It is the responsibility of the Emergency Coordinator or his designee to deactivate and secure the TSC and OSC when the emergency condition no longer exists. 8.6 Alternate OSC l In the event that the CSC becomes untenable, the E=ergetcy Coordinator shall designate an alternate location.
Page 5 of 10 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100832E, REV 2 ON-SITE SUPPORT CENTERS l l TABLE 1 i
, i
'3 RADIOLOGICAL EMERGENCY EQUIPMENT , i -
ST LUCIE PLANT 3 -l
~
CONTROL ROOM STORAGE LOCKER E - (ALSO FOR TSC USE) & ===
- 1. Coveralls
- 2. Hood
- 3. Gloves
- 4. Shoe Covers
- 5. Self Contained Breathing Apparatus
- 6. Full Face Respirators and Filters
- 7. Pocket Dosimeters
- 8. Dosimeter Chargers
- 9. TLD's 10~. Portable Count Rate Instrumentation
- 11. Porr.able Dose Rate Instrumentation
- 12. Contamination Smears
- 13. Envelopes 14 Radiation Tape / Rope
.5. Radiological Signs
- 16. Industrial First Aid Kit
- 17. Step-Off Pads
- 18. Plastic Bags l
Pags 6 of 10 l EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 2 C'i-SITE SUPPORT CENTERS TABLE 2 EMERGENCY DATA, DRAWINGS AND DOCUMENTS MAINTAINED AT THE TSC ' ST LUCIE PLANT .,
- 1. Plant Technical Specifications
- 2. Plant Operaciag Procedures
- 3. Emergency Operating Procedures
- 4. Emergency Plan and Implementing Procedures
- 5. Final Safety Analysis Report
- 6. Drawings, Schematics and Diagrams l
l l l
Pagt 7 of 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 2 ON-SITE SUPPORT CENTERS TABLE 3 r 1 TECHNICAL SUPPORT CENTER STAFFING ST LUCIE PLANT Ll TSC Supervisor Primary: Technical Supervisor Alternate Off duty STA (per 3100023E, E=ergency Roster) /R2 Operations Representative (Off duty Duty Call Supervisor or NPS) /R2 l
)
Health Physics Supervisor j Chemistry Supervisor Reactor Engineering Supervisor Maintenance Superintendent Quality Control Supervisor Support Staff as determined by these supervisors l l
. 1
Pags 8 of 10 ! l EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REV 2 V ON-SITE SUPPORT CE.IERS l , APPENDIX P I CCMMUNICATIONS EQUIPMEN'- i ) . 1 NmA : A. Use of the NAWAS System
- 1. The NARAS is used for announcing the initial warning to the State Warning Point at the Bureau of Disaster Preparedness (SDP) and St Lucie Disaster Preparedness Coordinator of a SITE AREA or GENERAL EMERGENCY.
- 2. The NAWAS is a direct, protected telephone land line with the handset installed in the Control Room.
- 3. Picking up the handset from its cradle activates a response at the State Warning Point and St Lucie and Martin County Disaster Preparedness Offices. The Nuclear Plant Supervisor (Emergency Coordinator) will advise the personnel on the other end of the system, in a coded message, of the conditions at the plant. He then places the handset back on its cradle, as this is the only use for it during an emergency. His message will activate the required state and local emergency teams. .
- 4. The procedure for reporting an emergency via NAWAS is su=marized
, in E-Plan Implementing Procedure 3100021E, Duties of Emergency Coordinator, and described in detail below.
A. In the event of a. SITE AREA EMERGENCY or GENERAL EMERGENCY incident, the following reporting procedure will be used: (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 3100021E, Duties of Emergency Coordinator.
/R1 (3) The following code name will be used to identify the /g1 geographical location of the St Lucie Plant:
St Lucie Plant ST. LUCIE OHL
Page 9 of 10 EMERGENCY PIAN IMPLEENTING PROCEDURE No. 3100032E, REV 2 ON-SITE SUPPORT CENTERS APPENDIX (cont) t d f A. Use of the NAWAS System (cont) 3 L:
- 5. Classifications The classes of Radiological Emergencies are described in E-Plan Implementing Procedure 3100022E, Classification of Emergencies.
- 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 SECIORS 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)
- 1. The LGR is used, unless inoperative or unavailable, for maintain'ing
- 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.
- 2. The LGR control unit is installed in the Control Room.
C. Use of the ENS (OPX) Telephone Network
- 1. Within one hour of the time that the Emergency Plan or any part of the Emergency Plan is implemented the NRC shall be notified and an open, continuous communications channel established using the NRC ENS circuit (red phone). The Nuclear Plant Supervisor (Emergency Coordinator) shall be responsible for assuring that this notification is made.
- 2. To initiate a signal to the NRC Operations Center, remove the handset from the receiver. .
- 3. When the NRC Duty Officer answers, identify yourself as " Florida Power & Light, St Lucie Plant".
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- Page 10 of 10
_w EMERGENCY PLAN IMPLEMENTING PROCEUDRE NO. 3100032E, REV 2 ON-SITE SUPPORT CENTERS l APPENDIX (cont) C. Use of the ENS (OPX) Telephone Network (cont) Iw
- 4. Make the notification.
- 5. Maintain the line open and manne.d until allowed to ter=inate the call by the NRC Duty Officer.
1 e l 1 i l l l h . . . _ . _ . _ _ _ _ . _
i r Page 1 of 28 6 FLORIDA PCWER & LIGHT CCMPANT ST. LUCIE PIANT UNIT NO. 1 E-PLAN DiPLIMENTING PROCEDURE NO. 3100033E RE7ISION 4 L.0 Ti tle : Off Site Dose Ca.lculations - 2.0 Review and Aoproval: Reviewed by Facility Review Group March 20 and 25,1981 Approved by A. D. Schmidt 7.P. Power Resources March 26, 19H Revision 4 Revie* d by F R G U~n.,,a u u 2 1988 Approved by
^
h Director Nuc Energy I-Z 19[E U b *
3.0 Scope
3.1 Purcose
3.1.1 This procedure provides a method for estimating whole b*ody and thyroid dose rates and integrated whole body and thyroid dose for the area surround 1::g the plant out to ten siles. 3.1.2 This procedure provides a seched of compari::g dose results, - release races, and radiation levels in contai=nent to hergency Classifications Guidelines. /14
3.2 Discussion
3.2.1 The bergency Coordinator, his designee, or the Chemistry Depart:nent representative will estimate thyroid and whole body dose races for off-site locations using this procedure whenever releases occur during an emergency. 3.2.2 The mergency Coordinator, his designee, or the Chemistry Depart:sent representative will use the thyroid and whole body dose rate estimaces to calculate integrated dose during the duration of the event. 3.3 Aut hority: This procedure implements the St. Lucie Plant Radiological mergency Plan.
l . P.ege 2 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 7 0FF-SITE DOSE CALCULATIONS
4.0 Precautions
Sw No ne 5.0 Resno nsibilities: The Faergency Coordinator or his designee has the responsibility for directing that thyroid and whole body dose rate esti: nates and integrated thyroid and Wole body doses are calculated following an accident Wich involves a release of radioactivity. The Chemist.7 Depart:nent representative shall make the estisaces upon arrivicg at the scene at the direction of the Emergency Coordinator. 6.0
References:
6.1 St. Lucie Plant Radiological Emergency Plan 6.2 St. Lucie Plant Radiation Protection Manual 6.3 "3ases for Accident Dose Calculations for St. Lucie Nuclear Power Plant". (3ases prepared by 9fM Associates of Waltham, Massachuse tts) . /R4 ' 7.0 Records and Notification: , , s . Decafled records of me.teorciogichl enditions used to estimate dose races, the escinated thyroid and
- hole, body dose rates and the int'egrated thyroid and Wole body deses shall be kept on the accached worksheets.
As deemed appropriate by the E:nergency Coord1:ator, the off-site authorities shall be notified of:
- 1. Meteorological conditions (wind speed, wind direction, stability,
- and precipitacian). .
- 2. Proj ected thyroid and sole body dose rates and integrated thyroid and whole body dose at 1, 2, 5, and 10 miles, including sectors affected, and ,
- 3. Whether default values or actual seasurements were used for dose estimates.
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1 . . l l Page 3 of 28 i i l FLORIDA POKER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS 8.0 Instrue:1ons: lw 8.1 Upon :he ini:1ation of an event which has resulted or could result in release of radioactive saterial, the Contai:= lent High Range Radiation Monitors (if Inoperable use POST LCCA) reading should be coupared to Table 3-Ac:1on Guidelines for event classification. The thyroid and whole body dose rates in areas surrounding the plant shall be estimated using the instrumentation presented as follows: /R4 Note: 'Jhen available the TSC and/or EOF ""RS-80 Model III Computer programmed by EMM Associates in accordance with :he bases of Reference 6.3 say be used for dose calculations. /R4 8.1.1 Determine the temperature difference between the 200 foot
- enperature sensor reading and the 32.8 foot temperature sensor reading frem the meteorological tower (i.e. 200 foot reading sinus 32.8 foot reading) . This value shall be an average for at least the most recent fifteen sinute period.
Record :his value on Table 1. 8.1.2 Determine the average wind speed over at least the most recent fif teen minute period using the output of the '.ind speed sensor at the lower level on the meteorclogical tower. Record on Table 1. If the icwer level sensor value-
, is not available, use the upper level sensor value and note on Table 1.
8.1.3 Determine the stabili:7 class from the temperature difference reading and the wind speed class from the wind speed reading by using the relations in Table 1. Circle stability class and wind speed group on Table 1. Table 12 provides a more detailed explanation of Stability Class. /.R4 Note: If temperature differences data and/or wind speed data from the seteorological tower are not available, then thio information cust be obtained frem another source. The first choice of backup data is the National 'Jeatner Service Class A Observation Station at ' Jest Pals 3each. This office should be contacted to obtain an estimate of atmospheric stability (which the observer at the station can determine frem surf ace observations) and/or wind speed. If data is obtained fran the WS at Palm Beach, this f act should be coced on Table 1. If for some reason the data cannot be obtained then the following default table shall be used: DEFAULT TA3LE Time of Day St abill: r 'Jind Saeed Day D 4.5 mph Night F 2.2 mph If either the stabili:7 or wind speed def aul: value is used , record :he fact that a def ault value has been used by writing (defaul: value) after the ent:7 on Table 1.
Page 4 of 28 FLORIDA POWER & LIGHT COMPANY ST. L UCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS-
8.0 Instructions
(continued) 8.1.4 Deter:nine the average wind direction value over at least the - most recent fif teen sinute period from the wind direction sensor at the lower level of the seteorological tower. Record this value on Table 1. If the lower level value is not available, use the upper level sensor value and note this on Table 1. If neither sensor output is available, record "ALL" for wind direction on Table 1. If wind direction data is obtained frun a device indicati=g a direction greater than 360 degrees, subtract 360 from the reading. /R4 8.1.5 Determine the sum of Noble Gas C1/see from the site by editing the 10 minute average file of the affected release points shown below. Each affected low range channel or the medium or high range channel (if in ALERT or HIGH ALAICf STATUS) should be edited to obtain the value. Each gas channel prints out C1/ce, but no math conversion need be made. ( C1/cc x 1.0 = C1/sec). Internal conversion f actors are already incorporated to obtain C1/ sec directly for normal vent exhaust flows. The Steam Line A & 3 indicate R/hr but internal conversion factors are yielding C1/see i.e., (2/hr=C1/ sec) /R4 8.1.5.1 On Eberline Control terminal A (or 3) input the following sequence by Depressing,in order: Keyboard Keysvitch "0N" with key EIST MIN
- IZZX Channel No. 0101 'as example /R4 ENTER A print out of the last 23 - 10 sinute average -
values for the Channel No. will print out. The last value at the bottom of the column is the current instantaneous value. Use the next-to-last for the 10 min. average. /R4 CHANNEL ND13ERS FOR A30VI CHANNEL NO. INPUT Release Point i Units I Low Rarse i Meti . Range l High Range Plant Vent I C1/ see 1 0105 1 0107 1 OLO9 ICCS-A I C1/ see i 0205 0207 ECCS-3 1 1 02u9 i C1/ sec I 0305 1 0307 1 0309 i Fuel 31dg i C1/ see 1 0405 0407 1 i 0409 Steam Line A i C1/ sec I 0501 Steam Line 3 I C1/ see 1 0502 /R4 Note: If Effluent Monitors are inoperable, proceed to Step S.1.8.
i P. age 5 of 28 [ FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 j E-PLAN IMPLEMENTING PROCEDURE 3100033E, RE7ISION 4 ' 0FF-SITE DOSE CALCULATIONS
8.0 Instructions
(continued) 8.1 (continued) ; I" 8.1.5 (continued) 8.1.5.2 The highest upscale channel of low, medium, high channels shall be used on each release point because it will be more accurate, and a Lesser Range Detector can go into 100: Dead Time (where it say be indicating between 0 and 0.3% of normal C1/see range if in 100% Dead Time coadition) . The Seeam Dump Monitors only have one range available. /R4 8.1.5.3 The C1/see values obtained shall be adjusted for flow changes in the vent (s) if different than normal where Normal flows are defined as: Plant vent EVE 10A (or 10B) running ECCS-A HVE 9A running ECCS 3 HVE 9B running Fuel Bldg , EVE 15 & E7E 17 hoth running
, If different than above, each vent relea.se point shall be adiusted as per the possible ccabinations shown on figures given below with the C1/sec Multiplication Factor. /R4 Plant vent Figure 8.1.5.3-1 Fuel Blds Figure 8.1.5.3-2 Corrected C1/sec = C1/see x Multiplication Factor for the appropriate Exhaust Fan combination from above Figures. /R4 l
1 l l
Pcgo 6 of 28 ' FLORIDA POWER & LIGHT COMPANY ST. LUCII PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS FIGURE 3.1.5.3-1 Plant 7ent Flow Multiplication Factors for j Possible vent Exhaust Fan Ccabinations Multiply C1/see by Two RAB Exhaust EVE 10A & 10B running 2.0 /R4 RA3 Exhaust HVE 10A (or B) & Cont. Purge RVE 1.22 RAB Exhaust EVE 10A (or 3) & one shield Bldg. Exhaust EVE 6A (or 63) 1.06 RAB Exhaust EVE 10A (or B) & two shield Bldg. Exhaust EVE 6A & 6B 1.13 Zero RAB Exhaust EVE 10A (or 3) & one shield Bldg. Exhaust EVE 6A (or 63) 0.06 Zero RAB Exhaust HVE 10A (or 3) & two shield Bldg. Exhaust EVE 6A & 63 0.13 O e g o'
Pago 7 of 28 FLORfDA POWER S L2GRT COMPANY ST. LUCII PLANT UNIT NO. 1 i E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 j ' 0FF-SITE DOSE CALCULATIONS l FIGURE 8.1.5.3-2 , Fuel 31dg. 7ent Flow Multiplication Factors " for Possible Vent Exhaust Fan Combination Muttiply C1/see by Fan Room Exhaust EVE 17 alone 0.34 Fan Room Exhaust EVE 17 & one Fuel Fool Sweep HVE 16A (or 163) 1.00 Fan Room Exhaust HVE 17, Pump Room Exhaust EVE 15, and one Fuel Pool Sweep HVE 16A (or 16B) 1.66 Pump Room Exhaust HVE 15 alone 0.66 Pump Room Exhaust HVE 15, and one Fuel Pool Sweep HVE 16A (or 163) 1.32
. 8 g
a
Pego 8 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCII PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS l
3.0 Instructions
(continued) 8.1 '" (continued) 3.1.6 In the case of a loss of coolant accident the Plant Vent noble gas monitor readings would not account for bypass leakage. For the Plant vent only, the release race of noble gases shall be adjusted by multiply 1::g the value determined in 3.1.5 by 1.14 to account for the bypass leakage and this adjusted value shall be entered on Table 1. /R4 3.1.7 The iodine release rate is initially estimated from the noble gas release rate. To obtain an estimate of the iodine release rate, multiply the noble gas release race determined from 8.1.5, or 8.1.6 in the case of a LOCA, by the f actor for the applicable accident type: Gas Iodine Release Accident T7ee Monitor Rate Factor Steam Line 3reak Plant Vent 1.4 Fuel Handli g Fuel Bldg. 0.06 Cask Drop Fuel 31dg. 1.54 LOCA Plant Vent 0.014 LOCA ECCS 0.014 S/G Tube Rupture Stean L1::A a 1,243_4
- S/G Tube Rdpture Plant 7ent b 1.24E-6
. . a denotes Safeties dir*ect to atmosphere b denotes Main Stean.co Condenser Dumps and Air Ej ector Exhaust aligned to Plant 7ent /R4 Enter the f actor used and the product of this f actor and the noble gas release race on Table 1 in the space provided for
- estimated iodine release race.
3.1.8 If the effluent monitors are inoperable and a LCCA has occurred, an estimate of the potential release sates for noble gas and iodine can be sade usi::g the readings on the Contal:1 ment Eigh Range Radiation Monitors. Graph 8.1.8 comparts monitor R/hr vs. Core Fraction Airborne (C7) usi::g elapsed time-lines from Reactor Trip. Reactor Trip Line is cM. Estinata Dose as follows : 3.1.3.1 If the highest CHRRM channel indicates less than 10 R/hr, the Offsics Dose Rate is negligible. Do no t proceed any further. 3.1.3.2 On the vertical axis, find the R/hr on Graph 3.1.8 for the R/hr observed on the highest CERRM channel. /R4
Page 9 of :S F t.0 RI D A POWER 6 LIGHT COMPANY $1. LJCIE PLANT UNIT 'f0. 1 E-PLAs IMPLEMENTING FLOCEDURE 3100033E, RE71SION 4 0FF-51TE DOSE CALOULATIC 'S U2APs 5.1.8 CORE F1 TAC"0M AIlt30ME nm 3RAPH 3.1.3
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- m. a, = x=2 ,_.,. . =. _. 4.__ . W....
,.,2.,J-.= .*
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- t. . . . ...... . . . . . .... . . . . . . . . . . . . . , . . . . . , . . .
10 5 tg 4 tg-3 tg.2 tg.1 tg] C0ltI AtAC".ON A33CRNE (CT)
Pego 10 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 ' ' E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS
3.0 Instructions
(continued) 3.1 (continued) 3.1.8 (continued) 3.1.8.3 Follow the R/hr line to where it intersects the time line representiog the hour from Reactor Trip when the CHRRM reading was obtained. Do not interpolate betvoen lines. On the graph reference, use the locger trip time line of the two under consideration.(Exmple: 2.f 1.5 hours have elapsed since Reactor Trip and C3RRM is observed at t=1.5 hours, the time line t=2 hours is the correct line). RECCRD the hours since Reactor Trip and the time line used on Table 1. 8.1.8.4 From the intersection of the R/hr line and the appropriate time line, project a vertical line downward to the horizontal axis. Obtain the value of Core Fraction Airborne (CF) a unitiess number. This represents the frac:1on of core inventory that is estimated to be airborne inside containnent. Enter the C7 value under the CF column on Table 1 Case III. ,
. 8.1.8.5 From Graph 3.1.8.3, obtain the Reduction Factor (R) by projecting a vertical line,up frem the elapsed time axis in hours to the point where it intersects the curve. Then project a hori:ontal line towards the Reduction Factor axis to obcain the value of (R). Enter this value under the (R) column on Table 1 Case III. -
/R4
Pago 11 of AS FLORIDA P O'JR 5 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IM PL EM E NTING PR oC ED UR E 3100033E, RE7I S IO N ./- 0FF-SITE DOSE CALCULATIONS cu rs s.t.a.3 NOBLE CAS REDUCTION FACTOR l 1.0 ! !!I
\ . .
l 0.8 \ l i
\l i i , , , ,
0.8
; Note:beginning Use the of thevalue of R perloo.
calculation corresponding to t
\ '
l For example, when calculating doses l
,\ - j for the period frem I to 2 hours g 0.7 a value of R= 0.88 snould be used.
l 5 g 0 o- ,
\ '
I I I I l' l I w i i l i I
.5 0.5 I I ' I I s
I i\ l l I I I I I i l I I E 0.4 I I I I I l ' I i4' i l l-g,3 lN l l 1 'l KI I I l- I ; j - I I I I ' 0'2 I I l l I l l l l i[ I I ' 0.1 ' ' ' i '- I : I I - l l l l l . I i i i li , I ' i l : l . l l ! l 0 2 4 6 8 10 12 14 16 18 20 22 24 Time since reactor trip (hrs) 1 I
Pago 12 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT No. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, RE7ISION 4 0FF-SITE DOSE CALCULATIONS 8.0 Instrue:1ons: (continued) 8.1 (continued) l w 8.1.8 (continued) l 8.1.8.6 Perform :he calc.21ations i:witcated on the worksheet and enter the Noble Oas and Iodine Release Rate C1/see values on the Worksheet where indicated. The calculations are shown below for inforsation. Core Fraction Reduction Estimated Airborne I Factor I C1/see (for Step 8.1.'8.4 Step 8.1.8.5 a CF=1.0) C1/ sec = CF I R I 40 Noble Gas i C1/ sec = C7 I 1.0 I 0.6 Iodine with Safeguards OPERA 3LE C1/sec = C7 I 1.0 I 1.6 /R4 Iodine with NO Saf eguards OPERABLE No te: For Iodines (R) shall egual 1.0 1.e., no
. decay credit allowed.
8.1.9 If a LOCA has occurred and :he Contai:nent High Range
- Radiation Monitors and :he ef fluent monitors are not operable, : hen a def ault value shall be applied for both "soble gas and iodine release races. The def ault value shall be determined from che follow 1::q =able based on :he post-LOCA radiation monitor reading: /R4 CAUTION: 1) If the post-LOCA soni: ors are to be used for dose assessment verify the sonitor readings with portable dose-rate instraents prior :o performing the dose assessnents.
- 2) If :he post-LOCA moni:ces are inoperable, obtain a shield building dose-race by using portable dose-race inscrments at the post-LOCA moni:or locations.
With Safeguards W1:hout Safeguards Post LOCA Radiation Noble Gas Iodine Iodine Monitor Reading Release Rata Release Race Release Race sR/ hr. Ci/ see C1/ see C1/ sec 30 :o 90 Negligible Negligible Negligible 60 to 190 2 0.03 0.1 100 :o 1000 10 0.14 0.4
>1000 40 0.6 1.6 /R4 Record :he value on Table 1 and vri:e *(def aul:
value)" af:er the entry.
Page 13 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0F?-SITE DOSE CALCULATIONS
3.0 Instrue
ions: (continued) 8.1 (continued) L 8.1.10 Chemistry Depart:senc Grab Sample results of Noble Gas and Iodine should be substituted for Instrument derived resul:s as they become available. Assay results can be converted to C1/see as shown on Table 11. The results should be entered under Case I corrected C1/sec (Circle entries to 1::dicate grab s aple) for :he affecced release poines. /R4 8.1.11 A series of thyroid and whole body dose race cables are provided as Tables 4 to 10. For each combination of stability and wind speed group, :he thyroid and whole body dose race (arem/ hour) for a one (1) C1/sec release race is precalculated for downwind distances along the plume centerline. The proper :able shall be selected for the stability and wind speed group noted on Table 1. 8.1.12 Determine the dose race estimates as follows:
- 1. The values for thyroid and whole body from the dose race table selected in 3.1.11 above are multiplied
, by chair respective release race in C1/sec recorded,
. oc. Tabl. 1 in scep: ,
8.1.5, 8.1.6', 8.1.8, or 8.1.10 for Noble Gas and ' 8.1.7, 8.1.8 or 3.1.10 for Iodine /R4
- 2. These values are entered in Table 1 at the appropriate distance and in the proper downwind direction. Direction should be recorded as one of
- he 16 principal c:apass directions (e.g.; N, NNE, etc.) . (Take care to assure that the dose race is -
recorded for the downw1::d sa:or as wird direction is recorded f:cm upwind.)
- 3. In order to account for uncertaincy in wied direction measurement and spacial variation in wind direc:1on, the values recorded in scep 2 above, should be entered for :he :vo adj acent downwind sectors as well as the 1::dicated sector.
Page 14 of 28 PLORIDA POWER & LIGHT COMPANT ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 OP7-SITE DOSE CALCULATIONS 3.0 Inscrue:1ons: (concinued) 8.2 The F.mergency Coordinator or his designes shall moni:or release '" races and meteorological condi:1ons to determine how frequently to update che dose race estimates. Dose race estimates shall be updated if any of the following averages change by the amounts indicated below, over a period coc to exceed 30 si~ces: /R4
- 1. Release races increase by more :han 25::
- 2. Wind speed decreases by :vo classes or more
- 3. Atmospheric stability becomes more stable by more chan one class (e.g., stability D :o P)
I 4 Wind direction changes by more chan 22.5o (i.e., plume centerline is more :han one sector away from prior location) . In any case, :he estimates shall be revised at least hourly for the first a bours after the accident unless it is determined that releases of radioactivity have been terminated. 8.3 The Emergency Coordinacor shall track integrated thyroid and whole body dose once each hour for the duration of :he event as follows: 8.3.1 The average :hyroid and whole body dose races shall be determined for each sector fr.ma che Dose Race Worksheets completed for che, hour of interest. 8.3.2 Update the Ctaulative Dose D14tribu:1on Worksheet, Table 2, by adding the thyroid and whole oody dose race determined from 8.3.1 for each applicable sector / distance block to :he integrated dose from event initiation to the present for : hat sector / distance block. /R4 8.3.3 In:egraced doses for see:or/ distance blocks 91:h zero estimated dose race for the curren: hour remain unchanged. Note: In reporting doses and dose races, to conservatively accommodate :he effec:s : hat could conceivably result from a postulated potencial stabilizieg effect of the Indian River, : hose residents in sectors K, L, or M (between SW a::d WNW of :he facility), should be considered :o reside at 1.0 miles. 1 8.4 Projections of doses and dose races should be made on :he basis : hat the most recently estimaced dose races and : heir distribucion will persist fo r :vo hour s . Projecting dose races for periods other :han
- vo hours should be made on an ad hoc basis using best available data on reles:.e race estimates and subsequent meteorological condicions.
i
/R4
f Page 15 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0F?-SITE DOSE CALCULATIONS
8.0 Instructions
(continued) 8.5 The results of Calculated Release Rates, Dese Race, and Integrated - Dose should be compared to applicable Table 3 - ACTION GUIDELINES. The Emergency Coordinato: , if not performing the actual calculations, shall be infor:ned of all dose estimates. The Emergency Coordinator shall eraluate the results and declare a new status as applicable. /R4 G '
- 0 e ,
- e e
e l
i . Page 16 of 28 ;
- FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 '
l E-PLAN IMPLEMENTING PROCEDURI 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS TABLE 1 - DOSE RATE WORKSHEET Calculation for: Date (sheet 1 of 2) Time Ending L
- COtPARE CHRRM R/HR TO TA3LE 3 ACTION CUIDELINES Met. Data Using 15 sinute averages
200 ft. Temp: oF. 32 ft. Wiod Speed: inph 32 ft. Temp: OF. 32 f t. Wind Direc.: Deg. (200 - 30 ft.): Delta T Sub 200 f t. Wi::d Data if 32 f t siss. Met Data F; m : AlA Tower / West Pals 3each Airport / Cef aul t (Circle One) Select the Aperopriate Dose Table for Met Conditions Above (Check Box) Delta ! Deg . F. j Stao. j Do se l Wind Speed Range Groups in non Ranges l Class ! Table 1 0 to 2 1 >2 to 4 i >= to 9 i >9 to 18i>L8 to 36
< -1.6 i A i 4 I i e i 1
-1.6 to < -1. 5 6 3 1 5 I I l t I
-1.5 to < -1.3
- C i 6 I I I i 1
-1.3 to < -0.4 i D#9 I 7 6 I i ff I i
-0 . 4 to < +1.3 i E I 8 I I I I i
+1.3 to < -3.4 i FSS I 9 i i SS I i 1
> or = +3.4 i G t 10 i e i I
~
it-Daytime s SS-Nigacime DEFAULO 7alues if No Met Data Ava11acle TO CALCUI.A*'I NCBLE GAS & IODINE RHJASE RATES: CASE I: Effluent Monitors Available I NCBLE GAS RELEASE RATE i IODINE RELEASE RATE , CHAN j :.frLUENT l INDICATED l FLOW l LCCA l CORRECTED l FACTOR s ACCIDENI TIPEl CORREC'i~~ f < NO I MONITCR I C1/ See I CCRRIC X CORREC = C1/ See I = C1/Sec ~~ 01 plani ~ , 1.14 1.4 E-2 LOCA - VENT 1.0 1.4 EO SO!.LN.3RK. 1.0 1.24 E-6 S/G TU3E RUP
!02- IECCS-A I I 1.0 1 1.0 1 11.4 E-2 LOCA i 03- 1ECOS-3 i i 1.0 i 1.0 I i1.4 E-2 LOCA i 05-01 i St .Line-A I i 1.0 I l.0 1 11.24 E-6 S/G TUBE RU?!
05-02 iSt.Line-3 I i 1.0 6 1.0 l I1.24 E-6 S/G TU3E RUPI 04- JFCEL 3LDG l l l 1.0 l 6.0 E-2 FUEL ENDLINGl l VENT I I I 1.0 1 1.34 E-0 CASK CRCP l Sum of Noois Gas Ci/ Sec= Sum of Iodine Ci/ Sec= CASE II: Actual asasurements of release races available from Chemiscrf Depart:nent. Calculations performed as per Table 11 and results entered (and circled) in the correctec C1/Sec column for Case I above for applicable release pathway for Noble Gas or Iodine. CASE III: Effluent Monitors Out of Commission and a LOCA has occurred. Calculate Release Rates from Contai:xnent High Raoge Radiation Monitors: From Grapa 3.1.dl From Grapn l l Release Highest CHRRM Core Fraction X 3.1.3.3 I Conversion = Rates Readiog (R/hr) Airborne (CF) ! *R" Facto r l Fac to r I (Ci/Sec) Ecurs since 40 Reactor Trip Noble Gas 0.o Hour line 1.0 vich used on Safeguards Craph 3.1.3 , 1.6 1.0 l wi thout Applicable 7 i Safeguards ' Iodine
l l l l Page 17 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS TABLE 1 - DOSE RATE WORKSHEET (sheet 2 of 2) .- CASE IV: If concal:: ment high range radiacion monitors out of commission: WI*H SAFIGUARDS W/0UT SAFEGUARDS, Obtain release races from POST LOCA RAD NOBLE GS IODINE IODINE POST LOCA RADIATION MONITCR MONITOR REL. RAl"E REL. RATE REL. RATE No te: The bypass Laakage is sR/hr C1/sec. Ci/ sec. C1/sec. already a f actor in 30 to 90 iNegligible i Negligible i Negligible these values :o the ~ 60 to 190 i 2 i 0.03 1 0.1 right. 100 to 1000 f 10 1 0.14 1 0.4
> 1000 1 40 l 0.6 i 1.6 CNPARE RELEASE RATE RESULTS TO TABLE 3 ACTION CUIDELINES Whole Body Dose Race for each distance = C1/sec NOBLE GAS X Dose Factor for each distance on the Speed Group Line for the Stab. Class Iodine Dose Race for each distance = Ci/sec IODINE I Dose Factor for each distance on the Speed Group Line for the Stab. Class INTER DOSE RATE RESULTS FOR I DICATED SECTOR & ADJACENT SEC"0R ON EACH SIDE:
- Wind Dir. l Downwind l 3res/ hr Whole 3odv 3 mile ii srem/hr *h7roid @ sile Indicated i Direccion I 1 1 2 3 5 l 10 1i 1 2 1 5 1 10 180 1N ALF51A I I I I II i I l 202.5 i NNE 3RA70 I l I i lI I i l 225 i NE CHARLIE I I I l Ii i i 1 247.5 i ENE DELTA I I I I ii i i 1 270 i E ECEO i i i i ti e i l 292.5 i ESE FO.CR0T I L I i ii i i 1 315 i SE GOLF I i i i il i : :
337.5 i SSE HOTIL i i i i II I I t 000 i S JULIET I I I Ii i t 1 022.5 i SSW KILO I *t i i ii =l 1 045 i SW LIMA I al I i ii *l i 1 067.5 I WSW MIKE I *l i I fI *t i I , ! 090 _C.' NOVEMBER I I i t II i i 1 l 112.5 l JNW PAPA l l l 1 lI ! I i 135 t .NW CUE 3EC i I
,t t Ii 1 i 157.5 i N!M RCHE0 I I 1 i ii i i i
*Ir.dian River Residents assumed :o live at 1 s11e acc evacuacion cricaria shall be based accordingly C2 PARE DOSE RA*E RESULTS TO TABLE 3 AC'* ION GUIDELINES 25 MARKS:
Page la of 23 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0F?-SITE DOSE CALCULATIONS TABLE 2 CUMULATI7E DOSE DISTRI3UTION WORK 3REET
- Time release asstaaed to occur:
Time through which this distribution applies: Met Station i i Whole Body Do sel srem) ii Thyroid Dose (mrem) Wicd Direction ; Downwind IDownwind Distance (miles) I I Downwind Distance (miles) ( As Read) Direction 1 2 5 10 1 2 5 10 i L30 #N ALPHA i i i i ei i i i 202.5 INNE 3RAVO I l l i ii i i i 225 INE CHARLIE I I I i 1I l i I 247.5 IENE DELTA i i i l iI I I I 270 lE ECHO I I I i ll l l 1 292.5 iESE FOXTROT I I I I ei i i I 315 ISE GO LF i I I i ie i I l 337.5 ISSE HOTEL i i i i il I i 1 000 IS JULIET I i i i II I I i 022.5 ISSW CLO I *1 1 I il *1 I i 045 ISW LIMA i *l i i li *l l l - 067.5 IWSW MIKE l- .*l I i iI =l I i 090 (W .NOVB3ERI I I I ii i i i 112.5 IWNW PAPK I i i i eI i l i 135 I!M OUESEC 1 l I i li l I i 157.5 I N!M RCMEO I I I i iI i i i
- Indian River Drive resicents assumed to live i 1 mile and Evacuation criteria shall be based accordingly.
CCMPARE RESULTS TO TABLE 3 ACTICN GUIDELINES Dste and time this worksheet was completed: Date Time Remarks: l I i 1 l
Page 19 of 23 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROC EDUR E 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS TABLE 3 AC"'ICN GUIDELINES mama For the Contai: ment High Range Radiation Monitor (CHRRM) Case Instantaneous Event Classification CHRRM i >1.47 E5 R/ hr i General Faergency CHRSM I I7.3 E3 R/ hr i Site Area Emergency CHRRM I Il0 R/ hr i Negligible As back un to the acove ti POST LOCA RAD MONITCR (or survey meter at same) POST LOCA i >1000 mR/ hr i General Fmergency POST LOCA i < 60 2R/ hr l Negligible For Noble Gas Ralease Rates i.e., C1/sec from the Site Case Instantaneous Situation Gas Rel. Rate l <0.083 C1/ sec IWithin Technical Soecification-No Action Gas Rel. Ratej 20.083 out less j Unusual Event-Tech. Spec. possibly exceeded-I than 0.83 C1/see I see ETS-B & take sceos to reduc race Gas Rel . Race i 10.33 C1/ see I ALERT CLASSIFICATION For Dose R&te Results . Or Duration Cr Duration Case Instantaneous For 2 minutes, of For 1/2 hm"- of Situation If Whole 3ody; 2500 150 Site Area
@ 1 alle is '
N/A sren/hr area /hr Emergency If Whole Bodyl General
@ 1 nile is l>1000aren/hr[i N/A N/A Emergency If rhyroid Site Area 22300 2250
@ 1 sile is N/A srem/hr aren/hr Fmergency For Cumulative Thyroid Integrated Dose If Thyroid Integracea Dose @ 1 mile usi::g >5000 seem then General Emergency actual set data i _ _ _ _ _ _ _ _ _ _ _
. l l
1 4 Page 20 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE P LANT UNIT NO. 1 Z-PLAN IMPLEMENTING PROCEDURE 3100033E, REVIS ION 4 0FF-SITE DOSE CALCULATIONS TA3LE 4 COSE FACTCRS FOR STABILITY CLASS A , j l R.0RIDA poler 48 L:347 C2PW - 77. L!)CIE MJCiNt PGER STATIGi 4CLE 30DY DOSE RR STABILITY GS3 A - (?pEMR), 3ASED W A 1.0 CI/SE2 GIS3Im GTE WDD 7ED DGNIDS DI37ME - MILE 3 (?PM) 1 2 3 4 5 6 7 8 9 to 11 12 0-2 1.340 6.4eE-31 4.43E41 3.40E-01 140E-31 140E-01 3.40E-31 3.40E-01 14CE-01 3.40E-11 140E-01 140E-01 2-4 4.14E-01 2..*2N1 1.54E-)1 1..W31 1.20E-01 1.. W )1 1.. % )1 1.20E-01 1.. W 11 1.20E-01 1.2CE-01 1.. % 31 4-9 2.MIE-01 1.11E41 7.7 !-M 5.79E-M 5.?*E-02 5.7aE-02 5.79E-02 5.7'E-p 5.79E-n 5.79E-02 5.99E-02 5.79E-n
~
9 13 1.04E-01 5.54E-02 134E-72 3.00E-02 106)2 3.00E45 3.00E-32 3.00E-n 3.00E-n LOGE-n ' 3.0CE-1 IS-M 5.20E-M 2.78E-2 1.73H2 1.50E-M 1.50E-72 1.50E42 1.5CE-72 1.50E-02 1.5CE-n 1.50E-n 1.5CE-32 1.5CE-n I'rMCID 30SE FGt STABILITY C.AS3 A - (.9EMR) 3ASED Gi A 1.3 CI/SEC GI53IGi G7E WDC TED 3GNIDE DISTME - Mill 3 (?FH) 1 2 3 4 5 6 7 3 7 10 11 12 0-2 2.79N3 1.4E-03 1.1!I-03 3.4:E 02 3.43E-02 3.4;E-02 3.43M2 3.43E-02 3.43N2 3.43E-02 3.43E-02 3.4:E-72 2-4 7.7@02 5."AE42 170E42 2.3EiH2 2.3lE42 2.3EEH2 2.38E-02 2.3GE-02 2.3lE-02 2.38E42 2.36E-02 2.38E-02 4-9 4.7?E4 2 1 4 Tc-02 1.3:E42 1.4E42 1.uE42 1.uE42 1.M-02 1.W-02 1.uE-n 1.ui-02 1.4E-02 1.uE-02 7-18 2.5 @ 02 1.'AE-02 7.24E4 1 7.1?E41 7.1 9 01 7.!?E41 7.1 5 01 7.17E41 7.1 5 01 7.1 5 01 7.1 5 01 7. iM-01 i 13-% 1.25E42 4.aiE-01 4.43E+01 3.40E41 3.40E 01 140E41 3.60E-01 L40E-01 3.40E-01 140E-01 3.40E-01 3.40E-0
Page 21 of 28 # I PLORIDA POWER 4 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 - E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS TABLE 5 DOSE FACTORS PCR STA3ILITY CLASS 3 , c'LGtD PWER ;ND LIGG C:2FfeY - 37. LUC'E 1X1Eidt POER 3TATim
'KLE 3CCY lCSE FGt 57 ABILITY CAS3 3 - (NE'JNil 3ASE 3 A 1.0 C:/SEC BIssa FATE i
WDC 1PE3 DON'Je DI57;NCE - MILI3 (NH) 1 2 3 4 5 6 7 8 9 to 11 12 0-2 3.90E4 0 2.25E-00 1.11540 8.5EE41 7.0241 6.50E41 6.50E-01 6.50E-01 6.5CE-01 6.50E-01 6.50E-31 6.50E-01 2-4 2.77E40 7.5:5-01 3.;:E-01 1.39E41 1.2531 1..*0E41 1. M -)1 1.M41 1. M -)1 1.20E-)1 1.2CE41 1. M -01 4-9 1.26E+00 174E-01 1.4EE-01 7.44E-2, 6.47E-n 5.795-n 5.75n 5.79E-E 5.??E-n 5.E9E-n 5.79E-n 5.79E-n 9-l8-7.4241 1.38E-31 3..*3E42 4.7:1-E 3.24E-n 100E-n 3.00E-02 3.ccE-n 3.0CE-n 3.0M-n 100E-72 3.00E-n 18-% A715-31 9. CE-02 4.19E-n 2.M-72 1.4:1-02 1.50E-n 1.5M42 1.50E-02 1.50E-72 1.50E-n 1.50E-02 1.50E-02 t THWt0!D JCSE FGt STABILITI CAs3 3 - (Met /Mt). 3ASE 3t A 1.0 C:/SEC BIS 3M FATE VDC PED JCMDC GIST;NCE - MILE 3 (NH) 1 2 3 4 5 6 7 3 7 to 11 12 0-2 2.14E+04 5.41E+03 2.47E*03 2.04E+C3 1.4GE M 3 1. E -03 1.56E43 1. E -03 1.34E43 1.!4E+03 1. M -03 1.54E-03 2-4 7.1.*+03 1.30E+03 3.0:E+02 1.5:E+02 111E+02 2.3EE402 2.38E-02 2.38E 02 2.33EM2 2.38E 02 2.30E-02 2.38E-02 4-8 3.54E+03 7.0:E42 4.02+02 2.L"E 02 1. 5E-02 1.' e02 1.44-02 1.44+02 1.44E-02 1.uE-02 1.44E-02 1. uE-02 7-18 1.78E-03 4.515-02 2.01EW2 1.1:E42 7.74E-01 7.1?E-01 7.19E-01 7.1?E-01 7.1 9 01 7.1 9 01 7.1 5 01 7.19E-01 , 19-% 3'.?0E-02 2.262-02 1.0tE+02 5.44E-01 3.38E-01 3.4M-01 3.50E-01 3.40E-01 3.40E-01 3.40E-01 3.40E-01 3.4M-01 i
Page 22 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 I E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS TABLE 6 DOSE FACTCRS FOR STABILITY CIASS C i I R.GtEA PGEt 461 G'i n CGPtNY - ST. L'I:E 6 PGEt 77ATICN y -_ ~
.H1.E 300Y ISE FGt STABILITY J C' i3 C - (NtEME 3AED CN A 1.3 O!E BIS $!CN FATE WG 3NE3 OGNIDG 3ISTMCE - MILES (MH) 1 2 3 4 5 6 7 8 9 to 11 12 0-2 2.5-01 6 5440 L15-00 2.21E+00 1.31E+00 1.53E40 1. 3 -00 1.27E40 1.27E+00 1.2"E-00 1.27E400 1.:7E-00 2-4 7.!!E-00 2.18E-00 1. 3 -00 6.28E41 4.17E41 3.00E41 2.07E41 2. 3 -01 2.22 41 2. 3 41 2.25-01 2. 3 -31 4-9 3.7540 1.09E40 3.3-31 3.1:1 -31 2.0441 1.50E-)1 1.1 2 -01 7.56E-4 3.59E42 7.30E-n 7.7?E-4 7.7?E-72 7-l3 1.3lE*00 5. G-01 2.4 E-)L 1.W41 1.0 4 -01 7.4?E-02 LW)2 4.7E-02 4.;?E-72 3.70E-n 3.!JE-72 3.00E-n 13-M 9.39E-11 2. ~E-31 1.31E-11 7.3E-n 5.215-4 3.7iE-72 2.32-02 2.h7E- n 2.1542 1.%E-n 1.79E-72 1.55-n UffROID ltSE FUt STABILITY F.1. ASS C - (MtEMM), 3ASED CN A 1.3 CIE BIS 3 ION RATE t!DG -
3MED :DMIDG DISTMCE - MILES (NH) 1 2 3 4 5 6 7 8 9 to 11 12 0-2 L 41E44 1.57E-04 7.56E+03 !.31E 03 4.08E+03 3.4GE-03 3.0 E-03 3.05-03 3.0!E-n 3.05-03 3.3-03 3.0E-03 2-4 1.M44 3.24E*03 2.5:E-03 1.50E-03 1.0E*n 7.19E-02 5.4E*02 !.415402 L41E-02 5.41E42 5.41E-02 !.41142 2-9 9.01E 4 3 2.a:E 4 3 1.26iH33 7.4502 5.00E-02 3.59E-02 2.7:E42 2.:?E42 2.0E 02 1.57E-02 1.57E 02 1.57E-02 9-18 4.31E+03 1.31E c3 6.3*02 3.5-02 2.50E42 1.3tE-02 1.M-n 1.1542 1.02-n 7.06E+01 3.5SE,01 7.72 ,01 13-% 2. 3 403 6.54-02 3.15-02 1.37E42 1.5-02 3.77E-01 6.30E-01 !.7 4 -01 5.15 41 4.48E41 4.:7E-01 3.77E+01
! l
. 1
Page 23 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0F7-SITE DOSE CALCULATIONS i TABI2 7 l DOSE FACTCRS FOR STABILITT C'. ASS D c'LORIDA POG M LIGG C2PANY - 57. '.l.C;E WCLE;A POG STATION MLE 3CDY DOSE Fm STABILITY Q. ASS 3 - t?REMRh 3ASED W 41.3 C:/SEC alSSIm FtiiE EDS MED . 00 MIND 3!$7EE - MLES (NH) 1 j 2 3 4 5 6 7 8 9 to 11 12 0-2 4.4241 1.39601 1.10E41 7.44E40 5.50E+00 4.27&00 3.45E-00 2.3M-00 2. G -00 2.10E*00 1.3:E-00 1.76600 2-4 1.54E41 6.31600 3.48E*00 2.49&c0 1. E +00 1.42+00 1.15-00 9. 5 -01 3.10E-11 6.79E-01 6.1M-01 5.3GE-01 4-9 9.14E*00 3.51E*00 1.7@00 ,1.240 9.64E-01 7.44E-01 5.78E41 4.74E41 4.15601 3.40E-01 3.17EM1 102-01
. 7-13 5.40E+00 1.76E-00 1. 5 -00 7.09&O1.5.11E-01 3.11E-01 3.12 41 2.5A41 2.17E-01 1.36E-31 1.42-01 1.!4iM1 IS-E 2.70E+00 9.3241 141E-01 3.54E-31 2. 5E-01 1.76E-Ot 1.56E-01 1.2?E-01 1.06E-31 7.3E-n 3.1342 7.75E42 UMOID DCSE Fm STABILITY CU43 3 - (?fEMR). 3ASED m A 1.3 C!/SEC BISSIGl RATE EDS 51!E3 DGNIDE 3!STME - MLIS (NH) 1 2 3 4 5 6 7 8 9 to 11 12 0-1 1.11E+05 4.54604 2.65+04 1.79E44 1.22 04 1.0 2 -04 3.2SE-03 6.38E-03 5.n-03 5.02-03 4.uE-03 4.22,03
*-4 3.7E+04 1.51EM4 3.3243 5.7M-03 4.40E*03 142403 2.76603 2.2?E-03 1.74E43 1.4alN3 1. G+03 1.41&c3
' 4-9 2.1?F04 3.41E-c3 4.77&c3 118603 2.31603 1.7 % C3 1. G-03 1.1?E<3 1.00603 9.G-02 7.o0602 7.25-02 M8 1. M 4 4 4.716 03 2.o0& c3 1.7E-03 1.22-03 9.29E-02 7.50E-02 6.!'F02 5.2C&O2 4.44&O2 3.71-02 3.74E-02 i
19-% 6.4tEH:3 2.24E-c3 1.20E*03 3.50E-02 6.12+02 4.M+02 17:E-02 3.09E+02 2.M-02 2..'"E-02 1.?6602 1.37&O2 i
Pago 24 of 28 l FLORIDA POWER & LIGHT COMPANT ST. LUCIE PLANT UNIT NO. I l E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVIS ION 4 0FF-SITE DOSE CALCULATIONS TABLE 3 DOSE FACTORS FOR STA3ILITY CLLSS E iUtIDA PGER Me L:34T C:PP41Y - 37. '1E2 MI:. Eta POWER STATIM iMG.I 30CY 32iE FGt STABILITY CUSS E - UFEMR). 3ASED GI A 1.J CI/EC BISSIm RATE i!De 7ED DGNIDC 31STt4dCE - MII.E3 (NH) 1 2 3 4 5 6 7 3 9 to 11 12 0-2 7.0E,01 1 3114 1 2.10E+01 1.31E41 1.14E+01 9.2E+00 7.7aE,00 6.4'E-00 ! 74E-00 5.07E+00 4.51E-00 4.06E+00 2-4 2.2E-01 1.10E41 6.99E*00 5. G +00 3.37E,00 3.12400 2.5 5 00 2.21&00 .9 2 ,00 1.4 5 00 1.50E+00 1.2E*00 4-9 1.59E+01 4.72+00 4.0 A+00 2.34E+00 2.15-00 1.71E400 1.41E-00 L.1500 1. E -00 3.97E-31 7.9E 41 7.1:E41 9-18 1. 2 41 4.2E+00 2.2E+00 1,5500 1.18E+do 9.0CE-01 7.39E-01 4.06E-01 !.45-01 4.5)1 4.1?E-31 17M41 13-% 5.10000 2. G 4 0 1.1 E+00 7.77E41 5.7241 4.55-31 3.7 E 01 3.laE-31 2.7CE41 2.3"E-31 241E-31 1.37E-01 114YROD 30SE FUt STABILTf CUSS E - (Met /Ht), 3ASED 24 41.3 CI/SEC BIS 3IGI RATE
\tDe PEE 1 DSMiDe DIST!JdCE .1II.E3 (MH) 1 2 3 4 5 6 7 8 9 to 11 12
>2 1.7CE+05 7.94& c4 5.E44 3.41E+04 2.73E-04 2.28E44 1.3 & C4 1.!9E44 1.08604 1..':E-04 1.;6E-04 9.1 5 -03 2-4 5.45-04 2.45-04 1.4EE-04 1.20E44 9.2 E+03 7.4aE 03 6.2'E-03 !.01E-03 4.41E-C3 4.2E-03 3.41E-03 3.2E-03 4-9 131E+04 1.42+04 9.74E403 6.M+03 5.1E+03 4.1CE*03 3."IE-03 2.35-03 2.4E*03 2.15+03 1.71E c3 1.71E403 bi8 2.4E+04 9.715+03 5.42-03 133E+03 2.34E-c3 2.22-c3 1. u -a3 1.32-03 1.01E-03 1.14603 1.31E-03 3.?E02 IS-%
1.2:E+04 4.34iH23 2.31E+03 1.91603 1.42+03 1.12403 9.10602 7.44E 32 6.54602 5.70002 5.G 02 4.4502 < l \
i .
.J' Pago 25 of 28 FLORIDA POWER S LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS TA3LE 9 DOSE FAC CRS FOR STABILITY CLLSS F l l
~
r13tDA PalEt M UWT C3PANY - 37. LUCIE MJCLi/Vt POLER 37ATICN 4G.E 3CDY l0SE FGt STABIUTY CLASS F - OWEPJHt). 3ASED Gi A 1.0 CI/TC BIS 3Im RATE - iiDe ' 3 PED DGNIDS DISTME - MILES (M) 1 2 3 4 5 6 7 8 9 10 11 12 0-2 1.3402 L3lE*01 4.23E+01 3. M 401 2.54E+01 109E 01 1.73E*01 1.54E-01 1.?,l6E+01 1.21E41 1.09E*01 7.3500 ! 2-4 4.1241 2.12-01 1.42 ,01 1.3 5 01 3.44iN0 6.78E40 L7240 3.12-00 4.52,00 4.0500 3.43E+00 130E40
. H 10901 1.41E+01 3.39E+00 6.4cE00 4.?JE400 4.00E 40 3.0:E*00 2.37!-00 2.5 @ 00 2.21E+00 1.78E,00 ~1.7 9 00 H8 1.S 9 01 3.5"E-00 5.21E4 0 3.4 2 ,00 2.73E+00 2.22-00 1.3 5 00 1.5&E-00 1. s -00 1.1 5 00 1.06E+00 9.49E:-31 IS-M 7.46E40 4.2&E40 2.4 @ 00 1.3llE 00 1.2 9 00 1.11E+00 7.17E-01' 7.7?t-01 6.7441 L7"E-01 L2SE-31 4.7241 THYft01D 2lSE FGt 57;BIUTY C. ASS F - OBEM/Ht), 5ASED Of A 1.0 CI/SEC DIS 3Im RA7E L'De PED 23miDe DI57ME - MILE 3 UPt) 1 2 3 4 5 6 7 j 3 7 10 11 12 0-2 2.99E-05 1. G -C5 1.0 5 05 7.4TE+04 6.09E+04 L G 404 4.27E-04 3.7 5 04 3.2 'E-04 2.70E-04 2.41E-04 2.37E,04 2-4 7.76iN4 !.!CE44 3. G 04 2.54E,04 2.32 44 1.4aE44 1.42 ,04 1.0"E-04 1. 8E44 7.47E-03 3.71E-03 7.71E-c3 H 7.42:M M SE-04 2.1 P 04 1.53N4 1.1 5 04 9.41E+2 3.0 4 -03 6.3GE-03 6.0CE43 L7DE43 4.7,".c~-03 4.2?E-03 MS 4.34-04 2.05M4
- 1. 3 -04 3.77E 03 6 asE-03 5.0 2+03 4.40E-03 3.74-03 3.24-03 2.34E-03 2.52-03 2.23E-03
' 9"%
LWA 1.0 2 -04 6. 3 +03 4.29E-03 3. M *03 2.46E-03 2. M -03 1.37E*03 1.42+03 1.42-2
Page 26 of 28 FLORIDA POWER S LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, RE7ISION 4 0FF-SITE DOSE CALCULATIONS TA3LE.10 DOSE FACTORS FOR STABILITY CT. ASS G l R3tIDA PGailt IJC t.IGHT C3PfeY - 37. L.1E!E *K1.!Ait PQEDI 37ATICH i
~
'H1.E 30DY ZSE FGt STA8IL!iY C.;iS3 3 - UftEMR). 3AsiD G8 A 1.0 C:/SID: G133I01 RATE
{ l'C3 51ED DOMfDG 3I37;41CE - MILE 3 OfH) 1 2 3 4 5 6 7 8 9 10 11 12 { 0-2 1.96E42 1.11502 7.?8E 01 6.24E4 1 5.16E-01 4. M +01 13:E41 135E41 3.03N1 2.7541 2.51501 2.31601 2-4 6.5 E 01 3. M +01 2.44 & O1 2.09601 1.72+01 1.46iN1 1.2E+01 1.13E+01- 1.01E+01 9.15-00 3.36iN0 7.49E+00 4-9 5.6 5-41 2.31601 1.57E 01 1.09E+01 1.11E+01 9.14iNo 7.79E400 6.77900 L ?8E+00 5.2E*c0 4.34E+00 4.41E40
. 9-18 3.00E-01 1.4 sin 1 1.C9901 8.33No 6.2500 L14+00 4.3*&C0 3.7240 1 2: & 00 2.91900 2 42400 2.3M+00 19-% 1.54E+01 3.29E+00 5.42400 4.31E+00 114600 2.57F00 2.12+00 1.32-00 1.441HO 1.45 H o 1.31E400 1.19E40 I'rMOID DOSE FUt STABILITY CUSS G - OftEMR). 3ASiD 31 A 1.3 CI/S!C O!!33ICN RATE
'dDe 7tD 30MDS 3!SitJCE - MILI3 (NH) 1 2 3 4 5 6 7 8 9 to 11 12 0-2 4.7QH5 2.47Ec5 1.71E+05 1.5 @ 05 1.24E+05 1. 2 E-05 9.17E4 4 3.12 44 7.2344 6.59E*04 6.02+04 5.54EE-04 l 2-4 1.5M45 3.39E-04 6. M *04 5.01E44 4.12 44 L51604 106iM4 2.71904 2.42-04 2.00lH4 2.01E+04 1.35 H 4 1
I 4-9 1.2E 05 6.74+04 4. M 04 3.34E44 2.46E44 2.0 5 04 1.37&O4 1.43H4 1.44604 1.2SE44 1.14E44 1.04E-04 9 18 7..*,1904 3.?9E-04 2.4 2 -04 1.73H4 1.011H4 1.2 5 04 1.041E*04 3.76i H 3 7.35 H 3 6.78003 6.23E-03 5.7C O U3 i l ts-a 3.37e.04 t. m-04 t.3te04 9. 3s2 7.54eos 6.1790s 5.20E-03 4.M-03 3.7eca 3.49e 03 3.14 os 2.35sa \ READY \ - _ _ _ .
Pego 27 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS ' TA3LE 11 l CHDfISTRY 'IA3 SAMPLE CONVERSION WORKSHEET To obtain C1/sec from Grab Sample Assay Results in u C1/cc: Gross Noble Gas or Iodine I Ve nt Flow I Vo l . Co nve r . I Time Co nv . X Act . Co nv . = Assay Act. u Ci X ft3 X 28317 cc X sin. X Ci = C1/ sec ec min ft) 60 sec. 100 u C1 Normal flow values have been factored into the below constants and C1/sec can be obtained by: u Ci X flow constant I flow correction factor = C1/ see ce for flow correction factor on variable flow vents see Figure 8.1 3 3-1 (Plant Vent) or Figure 8.1.5.3-2 (Fuel 31dg.) , Date [ Gross Flow Flow Correction Noble Gas Iodine Time i Pathway u C1/cc Tvoe Co nstant Facto r C1/see C1/ sec l Plant l t Gas 4.41 E 1 l if ~~ l Vent l l Iodine ly' I ECCS-A Gas 1.0 if l I [ 1.53 E i l I l Iodine 1 fl l ICCS-S l } Gas [ 1.47 E i 1.0 if I i l Iodine I f iFuel 31dg. I I Gas 6.95 E 0 if I Vent l I Iodine I f Time New Noele Gas Tocal=l If Time New Iodine Total = t I l l l 1
l 1 t Pago 28 of 28 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 E-PLAN IMPLEMENTING PROCEDURE 3100033E, REVISION 4 0FF-SITE DOSE CALCULATIONS TABLE 12 l= CIASSIFICATION OF A210SPRERIC STABILITY , 3Y TDfPERATIRZ CHANGE IN HEIGHT Stability Pasquill Temperature Change Classification Categories with Height (07) Extremely unstable A Delta T < -1.6 Moderately unstable 3
-1.6 f Delta T < -1.5 Slightly unseable C -1.5 f Delta T < -1.3 .
Neutral D -1.31 Delta T < -0.4 Slightly stable E -0.4 f Delta T < 1.3 Moderately stable F 1.31 Delta T < 3.4 Extremely stable G 3.4 f Delta T l i l
i l . P ag'e 1 of 10 f . l
- i I FLORIDA POWER 5 LIGHT I' ST. LUCIE PLANT UNIT NO. 1 EMERGENCT FIAN DiPLEMENTING PROCEDURE 3100035E REVISION 1 '"
1.0 Title
Offsite Radiological Monitoring and Dose Assessment 2.0 Review and Acoroval: Revision 0 Reviewed by Facility Review Group July 7 1981 Approved by A. D. Schmidt Vice Pres. Pwr.Res. July 13, 1981 Revision 1 Reviewe yFRG . "fw art., 29 1912. Approved by / a//l /uz. Y Dir., Nuc. Energy 8- L 19 % L/ /\ 3.0 Scooe :
3.1 Purcose
This procedure gives guidelines for assessment of thyroid and whole body doses based on offsite r'adiological sonitoring . 3.2
- Authority: -
This procedure implements the St. Lucie Plant Radiological Emergency Plan.
4.0 Precautions
4.1 The Radiation Tema Leader shall control the exposules of the off-site and on-site out-of-plant monitoring teams within 10 CFR 20 limits unless higher levels are authorized by the Emergency Coordinator or Recovery Manager. These higher limits should be less than 5 Ren whole body and 25 Rem thyriod. 4.2 Field seasurements indicating doses and dose rates that a.e less than those predicted by using plant instrumentation shall not be used to relax recommended protective actions while releases are in progress. 4.3 Field seasurenents indicating doses and dose races greater than those predicted by using planc instrumentation should be used to recommend protective actions as appropriate. /R1
Pcgo 2 of 10 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E, REVISION 1 0FFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT l 4.0 Precautio ns: (continued) 4.4 Doses to personnel in the OSC and Interim EOF shall be maintained :o mm-m the limits of 4.1. /R1 {
5.0 Responsibilities
5.1 The Emergency Coordinator, or his designes, is responsible for ensuring that offsite monitoring is perfomed during plant emergencies which involve the release of radioactive material :o the e nviro nment. 5.2 The Emergency Coordinator is responsible for determining the protective actions that will be recommended to off-si:e agencies. The TSC Supervisor is responsible for notification of off-site agencies of the recommended protective ac:1ons. l 5.3 The Radiation Tema Leader or his designee is responsible for the , activation and direction of offsite moni:oring team (s). /R1 ; 5.4 The Radiation Team Leader is responsible for providing dose projections based upon offsite moni:oring data to the TSC ! Supe rviso r. 5.5 The State of Florida's Department of Heal:h and Rehabilitative .
, Services assumes responsibility for offsi:e monitoricg and dose -
l projections af ter arrival of the Mobile Emargency Radiologicai -
- Laboratory. *he transfer of this responsibility from the plant :o i MIRLE will be made when he State informs the plant that they are :
re ady. /R1 l 3.6 The TSC Supervisor shall infom the appropriate offsite agencies concerning offsite moni:oring data and projec:ed doses until
- relieved of this responsibility by :he Recovery Manager. /R1 6.0
References:
i 6.1 St. Lucie Plant Radiological Emergency Plan 6.2 Florida Radiological Emergency Plan for Fixed Nuclear Facilities ' 6.3 HP-202, "Offsi:e Environmental Moni:oring During Emergencies *. 6.4 St. Lucia Plant Emergency Plan Implementing Procedures. /Kt 7.0 Records and Notifications: 7.1 offsite moni:oring data and projected :hyroid and whole body doses will be recorded on Appendix A. 7.2 Integrated Off-Site Dose Table. /R1 I
Pcgo 3 of 10 FLORIDA POWER & LIGHT COMPANT ST. LUCIE UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E, REVISION 1 0FFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT
3.0 Instructions
3.1 Upon the classification of an ALERT level emergency the on-site out- l of-plant field sonitoring team shall be activated and the of f-site =' field teams say be activated at the discretion of the Emergency Coordinator. At the SITE AREA and GENERAL EMERGENCY Level, the on-site and off-site field monitoring teams shall be activated. The staffing and control of these teams is the responsibility of the Radiation Tem Leader. /R1 8.2 Se Radiation Team Leader shall determine sonitori=g points based upon seteorological conditions and population :ones. 8.2.1 Preselected monitoring points are listed in Appendix 3 and i=dicated on the area saps contained in the offsite monitoring kits. The preselected poiucs are possible sonitoring points and say be used as reference points to direct sonitoring teams. 8.3 Communication with monitoring teams will be through the FPL two-way radio system or telephone. /R1 8.4 Monitoring teams will take direct radiation readi:gs and air samples and analyze air samples for radiologline concentration. 8.4.7 Radioiodine analysis will normally be performed using
- portable analy:ers wich' scintillation detectors. ,
/R1 Note: In the event radioiodine analysis cannot be done in the field, the Radiation Team Leader vill provide for the transport of air samples to the plant site for analysis.
3.5 Thyroid dose projections shall be done using the comagram in Appendix C. The projected release time should be for 2 hours unless otherwise indicated. 8.5.1 The projected thyroid dose is determined by matching the radioiodine concentration, on the right, vertical scale, with the projected exposure time, en the horizontal scale, and readi::g the projected thyroid dose off the nemagram. 3.6 ~4 hole body dose projections will be decersised by multiplying the gamma exposure rate by the projected exposure time. 3.7 Projected doses armi survey data vill be recorded on Appendix A. 8.8 The Radiation Team Leader will inform the TSC Supervisor and the Emergency Coordinator in regard to monitoring data and proj ected doses. Recommended protective actions shall be based on whole body and thyroid dose proj ections for adults.
Psgo a of 10 , FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E, REVISION 1 l OFFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT )
8.0 Instructions
(continued) 8.9 Projected doses to field teams are computed by using the seasured dose rates and Iodine concentrations in the plume and the time the : J== team was in the plume. Record the information on Appendix D. 8.10 If it appears that a team will receive doses in excess of those listed in 4.1, the Radiation Tem Leader will make the necessary arrangements for replacing the tea. e '
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Pego 6 of 10 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 EMERGE NCY PLAN IMPLEMENTING PROCEDURE 3100035E REVISION 1 0FFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT APPENDIX 3 FRESELEC"'ED OFFSI E MONITORING POINTS (Page 1 of 3) Survey Distance EPZ Point Location From Plant Sector A-1 S.R. A1A, North of plant site 6.0 31. NNW 3-1 Intersection S.R. 707 and S.R. 712 3.9 31. W E. of White City & S. of it. Pierce 3-2 Intersection U.S. 1 & S.R. 611, S. 6.5 31. W side of Ft. Pierce near RR crossing B-3 S.R. 707, S.E. side of Ft. Pierce 6.7 si. W 3-4 Intersection U.S. I and S.R. 70 8.1 si. NW C-1 Intersection U.S.1 & S.R. 712 5.1 si. WNW White City C-2 S.R. 70 near Florida Turnpike 10.1 31. WNW D-1 S.R. 707 W. of plant site 1.1 si. W D-2 U.S. 1, S. of White City 4.9 21. W e E-1 Intersection U.S.1 & Prima Vista , 4.9 si. WSW 31vd. , Port St. Lucie
- F'-l Intersection U.S.1 & Walton Rd. , 5.0 si. SW
, Port St. Lucie . F-2 Port St. Lucie Blvd. at F1. Turnpike 3.6 31. SW G-1 Intersection S.R. 707 & Walton Rd. 3.5 si. S
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G-2 Intersection U.S.1 & Port St. Lucie 5.9 mi. SSW Blvd., Por: St. Lucia H-1 S.R. 707 in Eden, 2 si. N. of 3.5 31. S Jensen 3each Causeway H-2 S.R. 707 & Jensen Beach Causeway 6.9 31. S H-3 Intersection S.R. 707 & Palmer Rd., 3.1 31. S S. of Jensen 3each H-4 S.R. 707 in Rio 3.9 31. S H-5 Martin Memorial Hospital in Stuar 10.2 si. S I-l S.R. A1A, S. of plant site 4.0 21. SSE l I-2 S.R. AIA & Causeway in Sewell's Point 10.3 31. SSE l i I
l l l l l Page 7 of 10 , 4 i FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100035E REVISION 1 , 0FFSITE RADIOLOGICAL MONITORING AND DOSE ASSESSMENT. '
.a ? :.- ./., s . APPENDIX 3 (Page 2 of 3) !
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l 1 FLORIDA POWER & LIGHT COMPANY Page 1 j ACTIVATION AND USE OF THE INTERIM EMERGENCY OPERATIONS , FACILITY (ST. LUCIE) 0FF-SITE EMERGENCY ORGANIZATION PROCEDURE 1202 2/1/82 1.0 Ti tl e: ACTIVATION AND USE OF THE INTERIM EMERGENCY OPERATIONS FACILITY (ST. LUCIE) 2.0 Approval and List of Effective Pages 2.1 Approval _ Reviewed by M Emergency Planning Supervisor u L--Ag. ,, , ,, ,_ ,, , , 19 82 Approved by Resources V dd/ fj, pj _, , 1983-u Vice President of Power 3.0 Scope 3.1 Pur.pos e_ This procecure describes tne activation and use of tne Interim Emergency Operations Facility for the St. Lucie Plant. 3.2 Discussion The Interim Emergency Operations Facility (EOF) is a nearsite support facility designed to provide an operating center for the
- Recovery Manager or his designated alternate and other members of the Of f-Site Emergency Organization. From tne Interim E0F, tne Off-Site Emergency Organization will provide support to tne Control Room and tne Interim Technical Support Cent r, coordination witn federal, state, and county of ricials, and coordination of radiological assessments. Additionally, tne Interim EOF will provide a nearsite ,
location for federal and state support teams. 3.2.1 The Recovery Manager may use the Interim EOF as nis near-site headquarters and may nouse tne FPL Off-Site Emergency Organization support team tnere. 3.2.2 The Interim ECF may De usec to coordinate FPL nd State Radiological Healtn Services offsite cose prop. .tions. 3.2.3 The Interim EOF may De used to coordinate FPL operations witn those of federal, state and county officials. 3.3 Description The Interim EOF is located in tne St. Lucie Unit No. 2 site construction office ouilaing. This builcing is soutn of tne Unit #1 Control Room and is outstae tne Unit #1 Protected Area. It is a two story ouilding and nas adequate office space and support facilities to house over 100 people. Space nas oeen designated to nouse tne following groups:
i ...,...\.~..__.. l 1 FLORIDA POWER & LIGHT COMPANY Page 2 i ACTIVATION AND USE OF THE INTERIM EMERGENCY OPERATIONS FACILITY (ST. LUCIE) 0FF-SITE EMERGENCY ORGANIZATION ' PROCEDURE 1202 2/1/82 3.3.1 FPL Off-Site Emergency Organization 3.3.2 NRC Site Team 3.3.3 State Radiological Health Services Field Team 3.3.4 FEMA 3.3.5 State Bureau of Disaster Preparedness Figure 1 identifies the designated locations within tne building, as well as other facilities. 4.0 Precautions 4.1 The Interim EOF is activated upon tne direction of the Emergency Control Officer or his designated alternate only. 4.2 Radiological conditions snall De' monitored at the Interim EOF prior to and during its use. 4.3 The Recovery Manager shall be responsiole for determining tne need for relocation to tne Alternate EOF. 4.4 Normal security operations will assure that acce<s is limited to autnorized personnel only. 5.0 Responsibilities 5.1 The Emergency Control Officer is responsiole for activating tne Interim EOF. The Recovery Manager supervises activities witnin it. If tne Interim EOF is activatec and tne RM remains at the General Office Emergency Center, the RM shall designate an EOF Director to sup'ervise activities at tne Interim EOF. 5.2 Designated managers of the Off-site Emergency Organization are responsible for reporting to tne Interim EOF upon direction to do so from tne ECO or RM. Each designated manager is responsible for assuring that all necessary support staff and materials are orought to the Interim EOF. 5.3 The RM is responsible for ensuring tnat adequate communication systems are provided for use at the Interim EOF. 6.0 References 6.1 St. Lucie Plant Radiological Emergency Plan 6.2 Emergency Procedue 1101 Outies of the Emergency Control Ofric.r. 6.3 Emergency Procedure 1102 Outies of the Recovery Manager. 7.0 Reco rds All signt ricant information, events, and actions taken relative to tne duties of the Recovery Manager during tne emergency perioc will oe recorded and maintained by tne Recovery Manager or his designate.
.. - l.. - --- . . .. .. .. ... - - ......-- ~ .---.. .. .. -. ~ .- -- . - - - L FLORIDA POWER & LIGHT COMPANY Pagm 3 ACTIVATION AND USE'0F THE INTERIM EMERGENCY OPERATIONS FACILITY (ST. LUCIE) 0FF-SITE EMERGENCY ORGANIZATION PROCEDURE 1202 2/1/62 8.0 _ Instructions 8.1 Activation The Emergency Control Manager snall activate tne Interim E0F for any emergency condition classified as a Site Area Emergency or General Emergency. He nas tne option of activating tne Intt.-Ln EOF for an Alert. To activate the Interim EOF, tne ECO snali direct tne Emergency Coordinator to assign an individual (s) to activate cne Interim EOF, ascertain the radiological conditions, status of communications systems and otner facilities, arrange for controlled access and coordinate with any state or local officials who may arrive prior to tne FPL Off-Site Emergency Organization. The Interim EOF shall not be considered operational until so declared by tne Recovery Manager. At tnis time, tne Recovery Manager assumes responsibility for communicating with offsite emergency response agencies and for assisting tne ECO in making protective action recommendations. 8.2 Functional Assignments, The Recovery Manager or nis designated alternate is respo'nsible for assigning space and facilities to various groups using tne Interim EOF in accordance with Figure 1. The Recovery Manager nas tne authority to alter such assignments as ne deems necessary. It is the responsioility of eacn person assigned to tne Interim EOF to report to his designated manager upon arrival. 8.3 Staf fing The Recovery Manager and his designated managers are responsiole for notifying and assigning staf f to report to tne Interim EOF. 8.4 Communications The following conmunications systems are availaole at tne EOF. Appendix A describes pnone locations and their use. System
- 1. Commercial telepnone offsite dialing capabilities
- 2. Canmercial telepnones, onsite dialing capabilities only .
- 3. Dedicated telepnones to Control Room
- 4. Radio communications
- 5. Public address If the Unit #2 site construction ouilding switenboard is closed when the Interim EOF is activated, no outside calls can enter tne buil di ng. If this is tne case, tne Recovery Manager or nis designated EOF Director sna11 assign personnel to estaolisn open
.~._.
. FLORIDA POWER & LIGHT COMPANY Page 4 ACTIVATION AND USE OF THE INTERIM EMERGENCY OPERATIONS FACILITY (ST. LUCIE) 0FF-SITE EMERGENCY ORGANIZATION PROCEDURE 1202 2/1/82 telepnone lines to tne necessary coordination points. These lines will be kept open continuously to ensure proper communications until tne switchboard is activated. 8.5 Support Facilities The Interim EOF nas the following support facilities:
- 1) Telecopy or otner facsimile machines
- 2) Ouplicating machines
- 3) Typewriters (or word processing machines)
Rest roam facilities are provided. Food service will be provided - at the direction of the R overy Manager. 8.6 Radiological Supplies The Interim EOF contains emergency radiological monitoring equipment and supplies protective clothing, and respiratory proteccive devices. Table 1 details these supplies. 8.7 Jechnical Data The Interim EOF contains copies of Emergency Plans and Procedures. The following information can also be made availaole: precalculated emergency data, tecnnical specifications, plant drawings and diagrams. 8.8 Deactivation It is tne responsibility of tne Recovery Manager to deactivate and secure the Interim E0F wnen the emergency conditian no longer exists. 8.9 Alternate E0F The alternate ECF is the FPL Walton Service Center (approximately 5 miles west of the plant). This f acility will be used if tne Interim EOF becomes untenable as determined by the Recovery Manager or his designated EOF Director.
FLORIDA POWER & LIGHT COMPANY Page 5 ACTIVATION AND USE OF THE INTERIM EMERGENCY OPERATIONS FACILITY (ST. LUCIE) 0FF-SITE EMERGENCY ORGANIZATION PROCEDURE t202 2/1/82 TABLE 1 EMERGENCY OPERATIONS FACTLITY EMERGENCf EQUIPMENT EQUIPMENT QUANTITY UNIT
- 1. Coveralis, Large and Medium 10/10 PR
- 2. Plastic Bags 10 EA
- 3. Clotn Hoods or Caps 20 EA
- 4. Latex or Rubber Gloves and Liners 20 PR
- 5. Rubber Shoe Covers 20 PR
- 6. Full Face Respirators and Filters 6/12 EA
- 7. TLDs 6 EA
- 8. Pocket Dosimeters, 0-500 mr 10 EA 4
- 9. Pocket Dosimeters, 0-1 R 5 EA
- 10. Dosimeter Chargers 2 EA
- 11. PortaDie Dose Rate Instrument, 1 EA
! PIC 6A or equivalent
- 12. Portable Count Rate Instrument, 1 EA .
RM14/HP210 Proce or equivalent
- 13. Note Pads and pencils 10/10 EA
- 14. Step-off Pads 10 EA
- 15. Contamination Smears 10 Box
- 16. Envelopes 1 Box
- 17. Radiation Tape / Rope 100 Feet -
- 18. Emergency Kit 1 EA
- 19. Radiation signs and assorted inserts 10 EA l
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% i EMERGEllCY ENERGEtlCY
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' EOF SECURITY TECit'11 CAL SPARE g .
tjAtlAGER IWtAGER c: DIRECTOR ^ (RECOVERY o MAtlAGER) \ ' E s 'l
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YPL l l RADIOLOGICAL 8 fella CONFERENCE ROOM L------- ' FPL
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CORPORATE STATE E IIEALTil PilYSICS BDP m
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FLORILA JWER & LIGHT COMPANY Page 7 ACTIVATION AND USE OF THE INTERIM EMERGENCY OPERATIONS FACILITY (ST. LUCIE) 0FF-SITE EMERGENCY ORGANIZATION PROCEDURE 1202 2/1/82 APPENDIX A
- 1. All . extensions can dial "0" (switchboard operator) wno can obtain an outside line.
- 2. The following dialing codes are availaole at certain pnones:
9 = outside line to Ft. Pierce (local calls) 71 72 ==outside outside lineline to Miami to Stuart (local calls)) (local calls 73 = G0 tieline 80 = State WATS (dial 1 + area code [outside "305"] + pnone numoer) 85 = Out of state WATS (dial 1 + area code + phone numoer) 88 = Unit 1 tie line -
- 3. The following service codes will indicate wnich extensions nave specific dialing codes available:
02 = All listed above 03 = 9, 73 only 06 = 72, 80, 85 only 07 = All listed above, except 88
- 4. Phone extensions and service codes:
Extension Service Code 02 02 02 06 06 02 07
.- j. 06 fI' g.j.N-'
03 02 g v' - 02 02 03 03 02 03 02 07 02 02
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