ML17229B482

Forwards Semiannual fitness-for-duty Performance Data for Jul-Dec 1995

ML17229B482
Person / Time
Site:	Millstone, Haddam Neck  File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	02/29/1996
From:	Dacimo F NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B15537, NUDOCS 9603110579
Download: ML17229B482 (257)

Text

Page 1 of 35 FLORIDA POWER 8 LIGHT COMPANY ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E REVISION 38 O O

~ J C

1.0 TITLE

PROCEDuRp PRODugTl .

DUTIES AND ESPONSIBILITIES OF THE EMERGENCY C ORDINATOR 2.0 REVIEW AND A ROVAL:

Reviewed by Plant N clear Safety Committee 7/25 19 75 Approved by K. N. arris Plant General anager 7/29 19 75 Revision 38 Reviewed by cility Review Group 10/26 19 95 Approved by J. Scarola Plant Ge ral Manager 10/26 19 95

3.0 SCOPE

3.1 Purpose

This procedure provides the ins u tions to be followed by the Emergency Coordinator when an emerge y o urs that requires the implementation of the Radiological Emergency lan for t. Lucie Plant.

S OPS DATE OCT PROCEDURE CN 3100021 E s

CO COMPLETED ITM 38

(

Page 2 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

3.0 SCOPE

(continued)

3.2 Discussion

1. The Nuclear Plant Supervisor (NPS) and the'hift operating staff represent the first-line of response to any developing emergency condition. The primary responsibility of the Nuclear Plant Supervisor~s to control the condition as well as possible. The Nuclear Plant Supervisor becomes the Emergency Coordinator (EC) upon initiation of the Emergency Plan and remains as such, until the position is turned over to the Plant General Manager or alternate. The EC directs the on-site emergency organization to bring the emergency under control. He also ensures the FPL offsite emergency organization has the information necessary to analyze the event, make Protective Action Recommendations (PARs) (if the Emergency Operations Facility (EOF) is activated) and develop information for the media.

2. As conditions warrant, the Emergency Coordinator should identify available staff (Duty Call Supervisor (DCS), licensed operators), to assist in Control Room activities such as communications (i.e., telephone and radio notifications), checklists and logbook entries.

I

3. The primary route of communication to the off-site governmental agencies is the Hot Ring Down (HRD) Red Phone with NAWAS as the alternate.

Additional alternates are listed in EPIP 3100023E, "Onsite Emergency Organization and Call Directory",

3.3 Authority

The St. Lucie Plant Radiological Emergency Plan.

3.4 Definitions

1. Release (During any declared emergency).

Any effluent monitor increase of (approximately) 10 times or one decade above pre-transient values.

OR

b. Health Physics detecting airborne radioactivity levels in excess of 25% derived air concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

Page 3 of,35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESP ONSIBILITIES OF THE EMERGENCY COORDINATOR

3.0 SCOPE

(continued) 3.4 (continued)

2. Notification Process - defined to include the following steps:

A. Declaration of the Emergency Class by the Emergency Coordinator.

B. Completion of the notification forms with the required information

'..consistent with the declared Emergency Class.

C. Approval of the information by the Emergency Coordinator.

D. Transmission of the information on the notification forms within the time limits mandated by the regulations.

1. State and local agencies - within about 15 minutes for the unusual event class and sooner (consistent with the need for other actions) for other classes (NUREG 0654 App. 1).

2. NRC - the licensee shall notify the NRC immediately after notification of the appropriate State or local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes (10 CFR 50.72 (a)(3)).

4.0 PRECAUTIONS

4.1 OFFSITE NOTIFICATION

1. If, due to rapidly degrading conditions, Emergency Class escalation is known to be necessary, prior to completion of the notification process, Then:

A. Provide the State and local agencies with the initial notification information by completing steps 1-5 of the "State of Florida Notification Message Form for Nuclear Power Plants."

B. Terminate the phone call by informing the State and Local agencies that a new notification form will be transmitted within 15 minutes.

OR Begin transmitting the new notification form describing the conditions associated with the upgraded Emergency Class.

/R38

Page 4 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

4.0 PRECAUTIONS

(continued) 4.1 (continued)

1. (continued)

C. Ensure that the NRC is informed following notification of the State and local agencies but no later than 60 minutes from the initial Emergency Class declaration (an open line will be established with the NRC at an Alert or higher Emergency. Class) ~ /R38

2. If one unit is in a classified event and the same or the other unit enters into an event where the same or lesser emergency class would apply, a new classification should NOT be declared. The event should be issued as an update at the earliest practical time.

3. If one unit is in a classified event and the other unit enters into a'ore severe event in which a higher emergency class would apply, the new classification would be declared and promptly, within the regulatory time limits, issued to the State, Counties and NRC, 4.2 OFF-SITE COMMUNICATIONCONTENT:

During initial notification, the information provided in describing the emergency should be brief yet descriptive enough for the offsite agencies to gain an understanding of the event. It should be clear from the incident description which Emergency Action Level (EAL) has necessitated the emergency declaration. Wording should be as non-technical as possible with no abbreviations (i.e., reactor coolant pump instead of RCP). Assurance as to the level of safety of the plant must be clearly conveyed. Potential for degradation of plant conditions is always of interest to the offsite agencies.

Proper, accurate information will preclude the need for'follow-up information or numerous questions from offsite agencies.

Page 5 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

4.0 PRECAUTIONS

(continued) 4.3 OFF-SITE COMMUNICATION UPDATES:

Updates to offsite agencies may be more detailed than initial notifications, but should remain in layman's terms. The state and local authorities should be updated every 60 minutes or upon any significant change-in plant status (e.g.,

start or termination of a release, loss of major plant equipment, loss of off-site or onsite power, etc.) for an Alert or higher emergency declaration. The update frequency may be changed if agreed to by off-site authorities and FPL, in advance. Long, detailed explanations of plant systems or reactor theory should be avoided. If prompted for this kind of information by the State Duty Officer, refer him to the Nuclear Division Duty Officer (NDDO).

4.4 EMERGENCY FOLLOW-UP INFORMATION:

All incoming calls should come via the State Warning Point (SWP) over the HOT RING DOWN (HRD) phone. If the HRD is inoperable, the SWP may use NAWAS or commercial telephone. If an offsite agency contacts the Plant without going through the SWP, request that they contact SWP. SWP shall verify that the agency calling is a risk county or Department of Health and Rehabilitative Services (DHRS), and shall notify other county and state agencies of the updated information, thus reducing the number of calls that may be directed to the Plant.

4.5 PROTECTIVE ACTION RECOMMENDATIONS:

Protective Action Recommendations (PARs) should be made utilizing all of the available data. This includes plant status, off-site dose projections and/or field monitoring data, The most conservative recommendations should be made.

4.6 GENERAL EMERGENCY - MINIMUMPARs:

In any case where a GENERAL EMERGENCY has been declared, the minimum Protective Action Recommendation shall be: Shelter all people within a 2 mile radius and out to 5 miles in the downwind sectors.

4.7 SECURITY EVENT

1. Site security and Local Law Enforcement (LLEA) will take the lead in response to a Security Event in accordance with the Security Plan.

Page 6 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR Qi

4.0 PRECAUTIONS

(continued) 4.7 (continued)

2. Based on the nature of the Security Event and as conditions warrant, the Emergency Coordinator may delay, postpone or institute special arrangements concerning, but not limited to:

A. Emergency Response Facility activation B. Local or Site Evacuation C. Site or RCA access D. Operator field activities E. Unit shutdown

3. Intruder General Emergency - minimum PARs A. If the GENERAL EMERGENCY has been declared due to loss of physical control of the plant to intruders, including the Control Room or any other area(s) vital to the operation of the reactor system (as defined in the Security Plan), the minimum Protective Action Recommendation shall be: Evacuate all people within a 2 mile radius from the plant and out to 5 miles in the downwind sectors. Shelter all people in the remaining sectors from 2 to 5 miles and from 5 to 10 miles from the plant.

4.8 ORDER OF SUCCESSION:

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

1. Assistant Nuclear Plant Supervisor (from the affected unit)

2. Nuclear Watch Engineer

3. Any other Reactor Control Operator with Senior Reactor Operator License as per 10 CFR 55.

Page 7 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

4.0 PRECAUTIONS

(continued) 4.9 WATCH RELIEF:

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

4.10 DRILL MESSAGES:

'During exercises, drills, or tests, ALI MESSAGES shall begin and end with THIS IS A DRILL or THIS IS AN EXERCISE.

5.0 RESPONSIBILITIES

5.1 CLASSIFICATION OF EMERGENCIES:

The Nuclear Plant Supervisor shall classify any abnormal condition immediately in accordance with the criteria given in E-Plan Implementing Procedure 3100022E, "Classification of Emergencies." If the classification is, UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, OR GENERAL EMERGENCY, the Nuclear Plant Supervisor shall declare an emergency and become the Emergency Coordinator. He shall remain in the affected Unit's Control Room at all times during the emergency condition unless, in his opinion, his personal evaluation of the situation'is necessary to maintain plant safety.

5.2 MOBILIZE EMERGENCY ORGANIZATION:

The Emergency Coordinator (EC) shall mobilize the On-Site Emergency Organization to begin required corrective actions. As conditions warrant, the EC should identify and assign tasks to an assistant. See Figure 1 for Initial Notification Flow diagram.

5.3 PROTECTIVE ACTION RECOMMENDATIONS:

The EC is responsible for providing Protective Action Recommendations (PARs) to off-site authorities as indicated in Appendix B, Determination of Protective Action Recommendations (PARs). When the Recovery Manager (RM) has indicated that the Emergency Operations Facility (EOF) is manned and operational and has received turnover from the EC, the RM then relieves the EC of PAR responsibilities.

Page 8 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

5.0 RESPONSIBILITIES

(continued) 5.4 OFF-SITE COMMUNICATIONS:

Offsite communications and coordination shall be the responsibility of the EC initially from the Control Room and then from the Technical Support Center once it is operational. The Recovery Manager assumes this responsibility from the EC when the Emergency Operations Facility is operational. This does not include calls for off-site fire and medical assistance. These calls should always originate in the Control Room. Protective Action Recommendations shall always be given by the EC or RM. (see Section 4.2, Precautions, regarding content of off-site communications) 5.5 EC TRANSFER TO MANAGEMENT:

The Plant General Manager, Operations Manager, or the Operations Supervisor should assume the Emergency Coordinator function following proper turnover for ALERT, SITE AREA, or GENERAL EMERGENCIES.

Once the Technical Support Center (TSC) is operational the EC should lead the on-site emergency organization from the TSC. The NPS should remain in the control room to control and monitor plant conditions.

5.6 DELEGATION OF RESPONSIBILITIES'he Emergency Coordinator shall not delegate the following responsibilities:

Classification of the emergency.

2. The decision to notify state and local authorities and the content of those notifications.

3. Recommendation of protective actions for the public.

NOTE Once the EOF is operational and proper turnover has been conducted, the Recovery Manager will assume responsibility for offsite notifications to the state and local authorities and for recommending protective actions.

Page 9 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

6.0 REFERENCES

6.1 St. Lucie Plant Radiological Emergency Plan (E-Plan).

6.2 St. Lucie Plant Physical Security Plan 6.3 St. Lucie Plant Safeguards Contingency Plan 6.4 E-Plan Implementing Procedures, as follows:

EPIP-3100022E, "Classification of Emergencies."

EPIP-3100023E, "On-site Emergency Organization 8 Call Directory."

EPIP-3100025E, "Fire Emergencies."

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

EPIP-3100033E, "Off-site Dose Calculations."

6.5 10 CFR 50, Domestic Licensing of Production and Utilization Facilities. /R38 6.6 10 CFR 55, Operators's Licenses.

6.7 NUREG/BR-0150, Vol. 1, Response Technical Manual {USNRC).

6.8 NUREG-0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants. /R38 6.9 EPA 400-R-92-001, Manual of Protective Actions Guides and Protective Actions for Nuclear Incidents, October, 1991 ~

7.0 RECORDS

7.1 A copy of the data generated by this procedure shall be maintained in the plant files in accordance with Ql 17-PR/PSL-1, "Quality Assurance Records."

Page 10 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES'OF THE EMERGENCY COORDINATOR FIGURE 1 INITIALNOTIFICATION FLOW EMERGENCY COORDINATOR As Appears INTERIM On Checklist LOCAL SUPPORT EMERGENCY TEAMS

1. ST. LUCIECOUNTY-STATE OF FLORIDA FORT PIERCE FIRE STATE WARNING DISTRICT POINT US NRC OPERATIONS CENTER PLANT ST. LUCIE/MARTIN GENERAL MANAGER COUNTIES DEPARTMENT OF PUBUC SAFETY DUTY CALL SUPERVISOR (UNAFFECTED UNIT ANPS)

STATE DHRS OFFICE OF RADIATIONCONTROL ADDITIONAI PLANT SUPPORT EMERGENCYTEAM LEADERS TEAM MEMBERS NUCLEAR DIVISION DUTY OFFICER FPL OFFSITE EMERGENCY ORGANIZATION (0021E-A. IVPG)

Page 11 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

8.0 INSTRUCTIONS

TIME / INIT

/R38 8.1 The NPS shall initiate investigative and mitigating actions per the Off-normal Operating Procedures (ONOPs) and Emergency Operating Procedures (EOPs).

NOTE State and/or local agencies shall be notified within 15 minutes of initial classification.

/R38 8.2 The NPS shall classify the abnormal condition in accordance with EPIP 3100022E, "Classification of Emergencies".

8.3 The NPS shall declare the emergency to the Control Room staff and formally announce that he is the Emergency Coordinator (EC).

Notify the Shift Technical Advisor (STA) (Use boost function if Gaitronics is used).

8.5 If there are any injuries, Then consult Attachment 3, Medical Emergency Checklist, of AP 0005770, "On-site Medical Program.n~

8.6 If there is a fire or explosion, Then go to the Fire or Explosion Emergency Checklist (attached).

8.7 Complete the appropriate Emergency Classification Checklist (attached):

1. (Notification of) Unusual Event Checklist

2. Alert Checklist

3. Site Area or General Emergency Checklist 8.8 If a Fire Emergency is terminated, Then notify the following (complete the State and NRC notification forms):

Onsite PA announcement (use Gai-tronics boost function) ~ ..

State Warning Point NDDO /

Plant General Manager .. ~.... ~....... ~... ..

~ ~.....

~ NRC .. ~.... . ~ ~..... /

Page 12 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIRE OR EXPLOSION EMERGENCY CHECKLIST NOTE Complete all step blanks with time of completion and initials, or N/A if not applicable.

Date: i~

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

Site Area Emergency (time)

TIME / INIT

2. Sound Fire Alarm.

3. Using the Gai-tronics boost, make announcement of the affected Unit, location and extent of fire.

4. Activate the Fire Brigade and other appropriate emergency teams in accordance with EPIP 3100025E, "Fire Emergencies" using Gaitronics and boost function.

5. If the fire is in the Radiation Controlled Area (RCA), Then notify Health Physics.

6. If the evacuation of an area is necessary, Then initiate a Local Evacuation in accordance with EPIP 3100026E, "Criteria for and Conduct of Evacuations." Announce the following:

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

7. If off-site assistance is necessary, Then call St. Lucie County-Ft. Pierce Fire District PHONE No. 911 (Use Ft. Pierce phoneline)

~

8. Notify Security of the location of the fire and the expected arrival of the offsite fire fighting assistance.

9. Log Fire out to terminate Fire Emergency.

10. Return to instruction section, Step 8.7.

Page 13 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR UNUSUAL EVENT CHECKLIST (Page 1 of 3)

Date / /

Message ¹ /R38 NOTE Complete a new checklist for each notification made during an Unusual Event emergency.

/R38 rt TIME / INIT

1. If a radioactive release has occurred or is in progress, Then notify Chemistry to promptly perform offsite dose calculations per EPIP 3100033E, "Offsite Dose Calculations" and report results to the Emergency Coordinator. If Chemistry is unavailable, Then have Control Room personnel perform calculations.

2. If evacuation of an area is necessary, Then initiate a local evacuation in accordance with EPIP 3100026E, "Criteria for and Conduct of Evacuations."

3. Mobilize Emergency Teams to respond as required using Gai-tronics and boost function.

4. Prepare the State of Florida Notification Message Form For Nuclear Power Plants (attached) including Protective Action Recommendation.

NOTE

~

If Emergency Class escalation is known to be necessary, THEN terminate the notification after line 5.

/R38

5. Notify State Warning Point (SWP) within 15 minutes of classifying the emergency. Using the State HOT RING DOWN (HRD) Phone, dial 100. When the State answers, transfer the information from the State Notification Form. If the HRD is inoperable, Then go to the Alternate Notification Methods at the end of this checklist.

6. Notify the Plant General Manager, Plant Management and Security.

This may be accomplished by the Duty Call Supervisor (the unaffected unit's ANPS).

Page 14 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR UNUSUAL EVENT CHECKLIST (Page 2 of 3)

Date Message ¹

~ /

/R38 TIME / INIT

7. Notify the Nuclear Division Duty Officer (NDDO) and relay the-information on the State Notification Form and any other information necessary to characterize the event underway. See Nuclear Division Duty Officer Schedule for names and phone numbers.

8. Prepare the NRC Event Notification Worksheet.

9. Notify the NRC via the Emergency Notification System (ENS) phone immediately after notification of the State and counties. This shall be accomplished within one hour. /R38

10. Reassess corrective and protective actions. Verify assigned activities are under way and proper progress is being made. Reassign personnel and emergency teams as necessary.

11. Continue to assess conditions and review any changes against the Emergency Action Levels (EAI s) in EPIP 3100022E, "Classification of Emergencies."

12. Reclassify the event as necessary and follow instructions in the appropriate checklist.

13. If the classification is unchanged but a significant change in plant conditions has occurred, Then start a new Unusual Event Checklist, prepare notification forms and make the appropriate notifications as soon as possible.

NOTE Appropriate notification forms shall be completed for all updates.

14. If the event can be terminated, Then complete the notification forms (State, NRC) and notify the following:

State Warning Point Plant General Manager .............................. ~

Page 15 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR UNUSUAL EVENT CHECKLIST (Page 3 of 3)

Date / /

Message 0 /R38

14. (continued) TIME / INIT NDDO ~ ~ ~ ~ ~ ~ ~ ~ /

N RC ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

15. ALTERNATE NOTIFICATION METHODS CAUTION Use of an alternate method requires call back verification from the State Warning Point.

A. Alternate 1 - NAWAS B. Alternate 2 - Commercial phone C. Alternate 3 - Local Government Radio (LGR) via County relay Using the NAWAS/phone, notify the State Warning Point (SWP).

When the State answers, announce;

'State Warning Point, this is St. Lucie Unit

<SWP will acknowledge and give go-ahead>

'State Warning Point, this is St. Lucie Unit

, repeat

• Enter appropriate emergency classification.

Provide callback phone number.

Hang up the NAWAS/phone.

SWP shall call the Control Room via commercial phone to verify the notification. After verification is complete, pick up the NAWAS/phone and transfer the information from the State Notification Form.

Page 16 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ALERT CHECKLIST (Page 1 of 4)

Date /

Message 4 /R38 NOTE Complete a new checklist for each notification made during an Alert emergency.

/R38 TIME / INIT

1. If a radioactive release has occurred or is in progress, Then notify Chemistry to promptly perform offsite dose calculations per EPIP 3100033E, "Offsite Dose Calculations" and report results to the Emergency Coordinator. If Chemistry is unavailable, Then have Control Room personnel perform calculations.

2. Notify plant personnel of the emergency declaration using Gai-tronics and Boost function.

"Attention all plant personnel, Unit ~1/~2 has declared an ALERT."

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

"All nonessential personnel report to your Staging Areas."

Repeat the announcement. (N/A for updates).

3. If a release is in progress, Then review personnel access with the Radiation Team Leader (RTL) and notify Security with any special instructions. (N/A for updates) ~

4. Notify the Duty Call Supervisor to initiate staff augmentation in accordance with EPIP 3100023E, "Onsite Emergency Organization and Call Directory." (N/A for updates). /

A

5. If evacuation of an area is necessary, Then initiate a local evacuation in accordance with EPIP 3100026E, "Criteria for and Conduct of Evacuations." /

Page 17 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ALERT CHECKLIST (Page 2 of 4)

Date Message 0

/~ /R38 TIME / INIT

6. Prepare the State of Florida Notification Message Form For Nuclear Power Plants (attached) including Protective Action Recommendations.

NOTE If Emergency Class escalation is known to be necessary, THEN terminate the notification after line 5.

/R38

7. Notify State Warning Point (SWP) within 15 minutes of classifying the emergency. Using the State HOT RING DOWN (HRD) Phone, dial 100. When the state answers, transfer the information from the State Notification Form. If the HRD is inoperable, Then go to the Alternate Notification Methods at the end of this checklist,

8. Notify the Plant General Manager.

Notify the Nuclear Division Duty Officer (NDDO) and relay the information on the State Notification Form and any other information necessary to characterize the event underway. See Nuclear Division Duty Officer Schedule for names and phone numbers.

10. Prepare the NRC Event Notification Worksheet.

11. Notify the.NRC via the Emergency Notification System (ENS) phone immediately after notification to the State and counties. This shall be accomplished within one hour. /R38

12. Reassess corrective and protective actions. Verify assigned activities are under way and proper progress is being made. Reassign personnel and emergency teams as necessary.

13. Continue to assess conditions and review any changes against the Emergency Action Levels (EALs) in EPIP 3100022E, "Classification of Emergencies."

14. Reclassify the event as necessary and follow instructions in the appropriate checklist.

Page 18 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ALERT CHECKLIST (Page 3 of 4)

Date Message 0 j~ /R38 TIME / INIT

15. If the classification is unchanged but a significant change in plant conditions has occurred, Then start a new Alert Checklist, prepare notification forms and make the appropriate notifications as soon as possible.

16. If an off-site notification has not been completed in the last 60 minutes,

~ Then provide a routine update. Start a new Alert Checklist, prepare notification forms and make the appropriate notifications. /

NOTE Appropriate notification forms shall be completed for all updates.

17. If the event can be terminated, Then complete the notification forms (State, NRC) and notify the following:

State Warning Point .....

Plant General Manager N DDO ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

NRC ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

18. ALTERNATE NOTIFICATION METHODS CAUTION Use of an alternate method requires call back verification from the State Warning Point.

A. Alternate 1 - NAWAS B. Alternate 2 - Commercial phone C. Alternate 3 - Local Government Radio (LGR) via County relay

Page 19 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ALERT CHECKLIST (Page 4 of 4)

Date / /

Message 0 /R38 TIME / INIT Using the NAWAS/phone, notify the State Warning Point (SWP),

when the State answers, announce:

"State Warning Point, this is St. Lucie Unit

<SWP will acknowledge and give go-ahead>

"State Warning Point, this is St. Lucie Unit

, repeat

• Enter appropriate emergency classification.

Provide callback phone number.

Hang up the NAWAS/phone.

SWP shall call the Control Room via commercial phone to verify the notification. After verification is complete, pick up the NAWAS/phone and transfer the information from the State Notification Form.

Page 20 of 35 ST. LUCIE PLANT E-PL'AN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SITE AREA OR GENERAL EMERGENCY CHECKLIST (Page 1 of 5)

Date / /

Message 0 /R38 NOTE Complete a new checklist for each notification made during a Site Area Emergency or General Emergency.

/R38 TIME / INIT

1. If a radioactive release has occurred or is in progress, Then notify Chemistry to promptly perform offsite dose calculations per EPIP 3100033E, "Offsite Dose Calculations," and report results to the Emergency Coordinator. If Chemistry is unavailable, Then have Control Room personnel perform calculations.

2. If a radioactive release has occurred or is in progress, Then identify wind direction.

3. If a release is in progress, Then review personnel access with the Radiation Team Leader (RTL) and notify Security with any special instructions, (N/A for updates).

4. Notify Plant personnel of the emergency declaration using Gai-tronics and Boost function.

"Attention all plant personnel, Unit ~1/~2 has declared a SITE AREA EMERGENCY / GENERAL EMERGENCY ."

Repeat the announcement (N/A for updates).

5. If the Technical Support Center and Operational Support Center are NOT activated, Then notify plant personnel using Gai-tronics and Boost function.

"Attention all plant personnel, Activate the Technical Support Center and the Operational Support Center."

Repeat the announcement (N/A for updates).

Page 21 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SITE AREA OR GENERAL EMERGENCY CHECKLIST (Page 2 of 5)

Date / /

Message ¹ /R38 TIME / INIT

6. If the site is NOT evacuated, Then do the following;

a. Sound the Site Evacuation alarm.

b. Notify plant personnel to evacuate the site using the Gaitronics and Boost function; "Attention all personnel. All non-essential personnel, are to commence evacuation of the Owner Controlled Area. Persons igii ii i p plant to Ja cee Park / Jensen dpi/8 Beach Parkin i yi Area for accountability and further instructions.'.

REPEAT steps (a) and (b) above.

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

e. Inform St. Lucie and Martin Counties as part of the notification to the State Warning Point (SWP). Give them the evacuation routes and Assembly Area location.

7. If the TSC and OSC are NOT activated, Then notify the Duty Call Supervisor to initiate staff augmentation in accordance with EPIP 3100023E, "Onsite Emergency Organization and Call Directory."

(N/A for updates)

0 Page 22 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SITE AREA OR GENERAL EMERGENCY CHECKLIST (Page 3 of 5)

Date / /

Message ¹ /R38 TIME / INIT

8. Prepare the State of Florida Notification Message Form For Nuclear Power Plants (attached) including Protective Action Recommendations. /

NOTE If Emergency Class escalation is known to be necessary, THEN terminate the notification after line 5.

/R38 CAUTION PARs are required for General Emergencies.

9. Notify State Warning Point (SWP) within 15 minutes of classifying the emergency. Using the State HOT RING DOWN (HRD) Phone, dial 100. When the state answers, transfer the information from the State Notification Form. If the HRD is inoperable, Then go to the Alternate Notification Methods at the end of this checklist.

10. 'otify the Plant General Manager.

11. If the EOF is NOT operational, Then notify the Nuclear Division Duty Officer (NDDO) and relay the information on the State Notification Form and any other information necessary to characterize the event underway. See Nuclear Division Duty Officer Schedule for names and phone numbers.

12. Prepare the NRC Event Notification Worksheet.

13. Notify the NRC via the Emergency Notification System (ENS) phone immediately after notification of the State and counties. This shall be accomplished within one hour. /R38

14. Verify from the Security Team Leader that the Site Evacuation has been completed and all personnel have been accounted for. (N/A for updates).

15. Notify St. Lucie and Martin County Departments of Public Safety via State HRD Phone, dial 100, when the Site Evacuation is complete.

(N/A for updates).

I ll' A 4 % I~

Page 23 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SITE AREA OR GENERAL EMERGENCY CHECKLIST (Page 4 of 5)

Date / /

Message 0 /R38 TIME / INIT

16. Reassess corrective and protective actions. Verify assigned activities are under way and proper progress is being made. Reassign personnel and emergency teams as necessary.

17. Continue to assess conditions and review any changes against the Emergency Action Levels (EALs) in EPIP 3100022E, "Classification of Emergencies."

18. Upgrade to a General Emergency, as necessary. /

19. If the classification is unchanged but a significant change in plant conditions has occurred AND the EOF is NOT operational, Then start a new Site Area or General Emergency Checklist, prepare notification forms and make the appropriate notifications as soon as possible. /

20. If an off-site notification has not been completed in the last 60 minutes AND the EOF is NOT operational, Then provide a routine update.

Start a new Site Area or General Emergency Checklist, prepare notification forms and make the appropriate notifications.

NOTE Appropriate notification forms shall be completed for all updates.

CAUTION Only the Emergency Control Officer (ECO) can authorize the downgrading of emergency classifications from site area or general emergency.

21. If the event can be terminated, Then complete the notification form (State, NRC) and notify the following (unless notifications have been delegated to the Recovery Manager):

State Warning Point .. ~... ~... ..

~ ~........ ~ .

Plant General Manager NDDO.... ~.....

NRC ....

Page 24 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR SITE AREA OR GENERAL EMERGENCY CHECKLIST (Page 5 of 5)

Date Message ¹

~ /

/R38 TIME / INIT

22. ALTERNATE NOTIFICATION METHODS:

CAUTION Use of an alternate method requires call back verification from the State Warning Point.

A. Alternate 1 - NAWAS B. Alternate 2 - Commercial phone C. Alternate 3 - Local Government Radio (LGR) via County relay Using the NAWAS/phone, notify the State Warning Point (SWP),

when the State answers, announce:

"State Warning Point, this is St. Lucie Unit

<SWP will acknowledge and give go-ahead>

"State Warning Point, this is St. Lucie Unit

, repeat

• Enter appropriate emergency classification.

Provide callback phone number.

I Hang up the NAWAS/phone.

SWP shall call the Control Room via commercial phone to verify the notification. After verification is complete, pick up the NAWAS/phone and transfer the information from the State Notification Form.

Page 25 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR STATE OF FLORIDA NOTIFICATION MESSAGE FORM FOR NUCLEAR POWER PLANTS (Page 1 of 2)

Q THIS IS A DRILL Q THIS IS AN ACTUAL EMERGENCY

1. A. Time/Date: B. Reported by: (Name/Title)

C. Message Number. D.'rom: QControl Room QTSC Q EOF

2. SITE Q ST. LUCIE UNIT 1 Q ST. LUCIE UNIT 2

3. ACCIDENT CLASSIFICATION Q Notification of Unusual Event Q Site Area Emergency Q Alert Q General Emergency 4.

5.

CURRENT EMERGENCY DECLARATION INCIDENT DESCRIPTION OR UPDATE'ate: Time:

/R38

6. INJURIES A. Q Contaminated B. Q Non-contaminated

7. RELEASE STATUS:

A. Q No release (Go to Item 11) C. Q A Release is occurring-expected duration B. Q Potential (Possible) release D. Q A Release occurred, but stopped-duration

8. " RELEASE RATE A. Q NOBLE GASES: Curies per second Q Measured Q Default /R38 (calculated as per B. Q IODINES: Curies per second Q Measured Q Default EPIP 3100033E) C. Q Release within normal operating limits.

9. - TYPE OF RELEASE IS (Blanks are for specific nuclides, if available, i.e., 1-131, Cs-137, etc.) /R38 <<

A. Q Radioactive gases C. Q Radioactive liquids B. Q Radioactive airborne particulates D. Q Other

10. " PROJECTED OFFSITE DOSE RATE (calculated as per EPIP 3100033E) /R38 DISTANCE THYROID DOSE RATE (CDE) TOTAL DOSE RATE (TEDE) 1 Mile (Site boundary) mrern/hr mrem/hr 2 Miles mrem/hr mrem/hr 5 Miles mrem/hr mrem/hr 10 Miles mrem/hr mrem/hr IF Emergency Class escalation is known to be necessary, THEN add, 'a new notification form will be transmitted within 15 minutes GO TO line 14'. /R38 This information may not be available on initial notifications. /R38

Page 26 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR STATE OF FLORIDA NOTIFICATION MESSAGE FORM FOR NUCLEAR POWER PLANTS (Page 2 of 2)

11. METEOROLOGICAL DATA (at 10 meters)

A. Wind direction (from) degrees C. Wind speed MPH B. Sectors affected D. Stability class

12. UTILITYRECOMMENDED PROTECTIVE ACTIONS (from EPIP 3100021E)

A. 0 No recommendations at this time.

B. CI Notify the public to take the following protective actions:

NOTE If messages refer to 360'adius, use the word "ALL" under sectors.

MILES NO ACTION SHELTER/SECTORS EVACUATE/SECTORS 0-2 2-5 5-10

13. HAS EVENT BEEN TERMINATED? A. CI NO B. 0 YES Time: Date:

14. MESSAGE RECEIVED BY Name: Time: Date:

15. Return to applicable checklist (UE, ALERT, SITE AREA, GENERAL) and start from last completed step.

l Page 27 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR APPENDIX A DETERMINATION OF SECTORS AFFECTED AND STABILITY CLASS A. Affected Sectors

1. Using the guide below, determine the Affected Sectors and enter in line 11B of the State Notification form.

NOTE If the wind direction is directly on the edge of two sectors (e.g. 11', 33', 56',

etc.), an additional sector should be added to the Protective Action Recommendation (PAR) For example, if the wind direction is from

~ 78, then the affected sectors for the PAR should be L, M, N and P.

Wind Affected Wind Affected Wind Affected From Sectors From Sectors From Sectors 348 - 11 HJK 123 - 146 PQR 236 - 258 CDE 11 -33 JKL 146 - 168 QRA 258 - 281 DEF 33- 56 KLM 168 - 191 RAB 281 - 303 EFG 56-78 LMN 191 - 213 ABC 303 - 326 FGH 78 - 101 MNP 213 - 236 BCD 326 - 348 GHJ 101 - 123 NPQ there is no 0 sector there is no I sector B. Stability Class

1. Enter Delta-T (60 meter minus 10 meter temperatures) deg. F

2. Using Delta-T (AT) and the guide below, determine the Stability Class and enter in line 11D of the State Notification form.

Stability Stability Stability Class Class Class ST < -1.7 A -1.4 < bT < -0.5 D +1.4 < hT <+3.6 F

-1.7 < hT -1.5

< B -0.5 < bT < +1.4 E +3.6 < bT G

-1.5 < b,T < -1.4 C

4 Page 28 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR APPENDIX B DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 1 of 4)

A. Guidelines for Protective Action Recommendation (PARs) to off-site authorities.

1. FPL is required to provide county and state governmental-authorities with recommendations for protective action to be taken by the public during radiological emergencies at the St. Lucie Nuclear Power Plant.

2. The responsible authorities are the State of Florida Division of Emergency Management (DEM) and St. Lucie and Martin County Departments of Public Safety.

3. Protective action recommendations should be made utilizing all of the available data. This includes plant conditions, off-site dose projections and/or field monitoring data. The more conservative recommendations should be made.

4. 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:

a. If any case where a GENERAL EMERGENCY has been declared, the minimum protective action recommendation shall be; Shelter all people within a 2 mile radius and out to 5 miles in the affected sectors. (Affected sectors are the downwind sector plus the two adjacent sectors, three in total)

b. If a GENERAL EMERGENCY has been declared due to loss of physical control of the plant to intruders, including the Control Room or any other area(s) vital to the operation of the reactor system (as defined in the Security Plan), the minimum protective action recommendation shall be:

Evacuate all people within a 2 mile radius from the plant and out to 5 miles in the downwind sectors. Shelter all people in the remaining sectors from 2 to 5 miles and from 5 to 10 miles from the plant.

c. If the emergency has not been classified as a GENERAL EMERGENCY and the offsite doses are LESS THAN 500 mrem Total Dose (TEDE) or 1000 mrem Thyroid Dose (CDE) at 1 mile over the projected duration of the release, no protective action is recommended. This should be reported to DEM and other outside agencies who inquire as:

Page 29 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR APPFNDIX B DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 2 of 4)

A. (continued)

4. (continued)

c. (continued)

Based on our current assessment of all the information now available to us, Florida Power 8 Light Company recommends that you consider taking the following protective actions (PA) - NONE. This recommendation may change in the future, but we cannot now say when it may change or what it may change to.

B. 'etermining Protective Action Recommendations (PARs)..

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

1. In determining PARs, both plant conditions AND off-site doses must be considered. However, if a release has not occurred, then determine PARs based on plant conditions.

2. PARs based on plant conditions.

a. Refer to Figure 1, PARs Based on Plant Conditions.

b, Begin with the General Emergency question and proceed through the flowchart answering the questions at each prompt.

c. Upon completion of the flowchart, enter the PAR table and determine the PAR for each downwind distance.

d. Enter PARs into Line 1 of the table in Section C below.

Page 30 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR APPENDIX B DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 3 of 4)

B. (continued)

3. PARs based on off-site doses.

a. Refer to Figure 2, PARs Based on Off-site Doses.

b. For each downwind distance, enter the PAR table at the appropriate dose level and determine the PAR for that distance.

c. Enter PARs into Lines 2a and 2b of the table in Section C below.

Example:

A release has occurred at the St. Lucie Plant. The wind direction is from 22 degrees and the projected off-site integrated (2 hr) Thyroid Dose (CDE) is 10,000 mrem at 1 mile, 2000 mrem at 2 miles and less than 1000 mrem at 5 miles. The plant is in a GENERAL EMERGENCY with no actual or projected core damage and no loss of physical control of the plant. 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:

i ~ Evacuate all people between a 0 and 2 mile radius from the plant.

ii. Shelter all people between a 2 and 5 mile radius from the plant who are in sectors J, K and L.

iii. No protective action is recommended between a 5 and 10 mile radius from the plant.

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

4. When available, both plume calculations and off-site monitoring results should be evaluated when making protective action recommendations. If significant discrepancies exist between field monitoring results and plume dispersion calculations, then an evaluation of the discrepancy should be made, and the appropriate value should be selected in the determination of protective action recommendations.

Page 31 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR APPENDIX B DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS PARs (Page 4 of 4)

B. (continued)

5. Protective action recommendations have been developed based on guidance in NUREG/BR-0150, Vol. 1 and EPA 400-R-92-001.

C. Protective Action Recommendations (PARs)

NOTE Actual PARs shall be the most conservative PARs based on plant conditions or off-site doses.

1. Complete the table below Step 1. Determine PARs based on Figure 1, PARs Based on Plant Conditions, and enter into line 1.

Step 2. Determine PARs based on Figure 2, PARs Based on Off-site Doses, and enter into lines 2a and 2b.

Distance From Plant/Recommendation Protective Action Recommendations 0-2 Mile 2-5 Mile 5-10 Mile Line 1. Plant Conditions Line 2a. Total Dose (TDE)

Line 2b. Thyroid Dose (CDE)

2. Choose the most conservative PARs and record in Section 12 of the State Notification form.

Page 32 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE 1 PARs BASED ON PLANT CONDITIONS NOTE PARs are determined by considering plant conditions and off-site doses (Figure 1 and Figure 2).

Distance From Plant/Recommendations'-2 Miles 2-5 Miles 5-10 Miles General Emergency? N N N YES Actu or Proiected of Physical Severe Core Control of S(CR) S(DW)

Damatfe? Plant?

1) 2 YES YES E(CR) E(DW)+S(RS) S(CR)

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

(Enter the results of Plant Condition PARs in Appendix B, Section C.)

Notes: 'Legend of abbreviations:

'Severe core damage is indicated by either- N - No protective action recommended Loss of critical functions required for core S - Sheltering recommended protection (loss of injection with LOCA) E - Evacuation recommended High core temperatures (CET > 700') DW - Downwind + 2 adjoining sectors CHRRM reading of 4.2 E4 R/Hr RS - Remaining sectors 2Loss of physical control of the Control Room or CR - Complete circle around the plant at vital reactor operating areas to intruders. specified distance.

F E

Page 33 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR FIGURE 2 PARs BASED ON OFF-SITE DOSES NOTE PARs are determined by considering plant conditions and off-site doses (Figure 1 and Figure 2).

Determine PAR for each mile value using most conservative dose at that mile value.

Projected Dose, Distance From Plant/Recommendation'-2 Total Dose Thyroid Dose (TEDE) (CDE) Miles'-5 Miles 5-10 Miles

< 500 mrem < 1000 mrem

> 500 mrem > 1000 mrem S(CR) S(DW) S(DW)

But But

< 1000 mrem < 5000 mrem

> 1000 mrem > 5000 mrem E(CR) E(DW)+ E(DW)+

But But S(RS) S(RS)

< 5000 mrem < 25000 mrem

> 5000 mrem > 25000 mrem E(CR) E(CR) E(DW)+

S(RS)

(Enter the results of Off-site Dose PARs in Appendix B, Section C.)

Notes: 'Legend of abbreviations:

'Use 1 mile value to determine PARs N - No protective action recommended for 0-2 miles S - Sheltering recommended

~Use 2 mile value to determine PARs E - Evacuation recommended for 2-5 miles DW - Downwind + 2 adjoining sectors sUse 5 mile value to determine PARs RS - Remaining sectors for 5-10 miles CR - Complete circle around the plant at specified distance.

I 4 Page 34 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR NRC EVENT NOTIFICATION WORKSHEET (Page 1 of 2)

NDDO Contacts Name:

NRC Contacts Name:

EVENT NOTIFICATION WORKSHEET Notification Time Facility or Organization Unit Caller's Name Callback ¹: ENS FPL - St. Lucie Plant or (407)

Event Time & Zone Event Date 1 Hr. Non-Emergency (v) Lost Offsite Comms 10 CFR 50.72(b)(1)

(vi) Fire (i)(A) TS Required S/D (vi) Toxic Gas Power/Mode Before Power/Mode After (I)(B) TS Deviation (vi) Rad Release (ii) Degraded Condition (vi) Other Hampering Safe Op.

(ii)(A) Unanalyzed Condition 4-hr. Non.Emergency 10 CFR 50.72(b)(2)

(ii)(B) Outside Design Basis EVENT CLASSIFICATIONS (ii)(C) Not Covered by OPs/FPs (i) Degrade While S/D General Emergency (iii) Earthquake (ii) RPS Actuation (scram)

Site Area Emergency (iii) Flood (ii) ESF Actuation (iii) Hurricane (iii)(A) Safe S/D Capability Unusual Event (iii) Ice/Hail (iii)(B) RHR Capability 50.72 Non.Emergency (iii) Ughtning (iii)(C) Control of Rad Release Physical Security (73.71) (iii) Tornado . (iii)(D) Accident Mitigation Transportation (iii) Other Natural Phenomenon (iv)(A) Alr Release > 2X App B 20.403 Material/Exposure (iv) ECCS Discharge to RCS (iv)(B) Liq Release > 2X App B Other (v) Lost ENS (v) Offsite Medical (v) Lost Emerg. Assessment (vi) Offsite Notification DESCRIPTION Include: Systems aftected, actuations & their initiating signals, causes, effect of event on plant, actions taken or planned, etc.

Notitications Yes No Will Be Anything unusual or not understood? Yes NRC Resident (Explain above)

State(s) Did all systems function as required? Yes No (Explain above)

Other gov agencies Mode of operation Estimate for Additional into Media press release until corrected restart date: on back?

f I

'P

Page 35 of 35 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100021E, REVISION 38 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR NRC EVENT NOTIFICATION WORKSHEET (Page 2 of 2)

ADDITIONALINFORMATION Radiological releases: Check or fbi in applicable items (specific details/explanations should be covered in event descnpbon)

Liquid release Gaseous release Unplanned release Planned release Ongoing Terminated Monitored Unmonitored Offsite release T.S. exceeded RM alarms Areas evacuated Personnel exposed or contaminated Offsite protecbve actions recommended State release path in description.

Release Rate ( i/sec  % T.. Limit H vide Total Acbvity ( i  % T.. Limit H uide Noble Gas 0.1 Ci/SeC 1000 Ci Iodine 10 pCi/sec 0.01 Cl Paibculate 1 pCi/sec I mCi Liquid (excluding tntium and dissolved noble gases) 10 pCi/min 0.1 Ci Liquid (tnbum) 0.2 Ct/min 5Ci Total Acbmty lant tack ndenser/Air lector Main team Line lowdown ther RAD monitor readings:

Alarm setpoints:

% T.S. Limit (if applicable)

Rcs or sG tube leaks: check or fill in applicable items: (specific details/explanations should be covered in event descnption)

Location of the leak (e.g., SG ¹, valve, pipe, etc.):

Leak Rate Units: gpm/gpd T.S. Limits: Sudden or Long Term Development:

Leak Start Date: Time: Coolant Acbvily & Units: Primaiy- Secondary-List of Safety Related Equipment Not Operabonal:

EVENT DESCRIPTION (Continued from front)

Page 1 of 27 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT i E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E REVISION 68

1.0 TITLE

ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY PROGf DuRF- PRODUWI 2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group 7/25 19 75 Approved by K. N. Harris Plant General Manager 7/29 19 75 Revision 68 Reviewed by F R G 10/19 1995 Approved by J. Scarola Plant General Manager 10/19 1995 THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN, PLEASE READ ENTIRE PROCEDURE BEFORE PROCEEDING. /R68

3.0 SCOPE

3.1 Purpose This procedure provides instructions and phone numbers necessary to activate the On-Site Emergency Organization (see Figure 1) for shift augmentation in response to an emergency declaration. In the appendices are the names, phone numbers and alternates for company emergency personnel, as well as phone numbers of County, State and Federal agencies.

3.2 Discussion Once the Nuclear Plant Supervisor classifies and declares an emergency, he becomes the Emergency Coordinator (EC) and, as such, directs the On-site Emergency Organization. The operating staff constitutes the immediate response organization, i.e., the Interim Emergency Teams. Emergency requirements take immediate precedence over normal operating responsibilities (as determined by procedure or at the direction of the EC). The Primary Emergency Teams, S OPS which are composed of first line management will staff DATE the on-site support centers, relieve the Interim DOCT PROCEDURE Emergency Teams and provide support to the EC as DOCN 3100023E required to mitigate and manage the emergency svs situation. COMP COMPLETED ITM 68

Page 2 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY

3.0 SCOPE

(continued) 3.3 Authority The St. Lucie Plant Radiological Emergency Plan.

3.4 Definitions Interim Emergency Teams The Interim Emergency Teams are composed of members chosen from plant shift personnel. All are qualified in procedures and practices required for the performances of their duties as team leaders or members.

2. Primary Emergency Teams The Primary, Emergency Teams are composed of first line management personnel and others who normally work a regular Monday through Friday day shift schedule.

4.0 PRECAUTIONS

4.1 The Interim Emergency Teams should take action regardless of the fact that the Primary Emergency Team members may be present.

Members of an Interim Emergency Team may consider themselves relieved

~onl upon the specific instructions of a recognized superior or the Primary Emergency Team Leader. Merely knowing that a superior or a Primary Emergency Team Leader is present does not constitute a release from emergency duties and responsibilities.

4.2 At their own option and with the concurrence of the Emergency Coordinator, Primary Emergency Team Leaders may relieve their counterpart on the Interim Emergency Teams.

4.3 Persons filling positions with call-out responsibilities, as dictated by this procedure, should ensure that necessary call lists are available.

~ 1 I'

Page 3 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY 5.0 RESPONSIBILITIES'.1 Operations Duty Call Supervisor The ANPS on Unit 1 is the Duty Call Supervisor for any routine duties. During situations which require implementation of the Emergency Plan, the ANPS on the unaffected Unit will assume the role of the Duty Call Supervisor. He has the responsibility for assisting the Emergency Coordinator in notifying off-duty plant staff and the company's off-site emergency organization in the event of an emergency. See Figure 2 for the initial notification flow.

5.2 Technical Support Center Supervisor The System and Component Engineering Manager or his alternate (see Appendix A) assumes the position of TSC Supervisor when the Emergency Coordinator directs the TSC to be activated. As the TSC Supervisor, he "

supervises the TSC personnel and directs the technical support activities.

5.3 Operational Support Center Supervisor Off-hours initial staffing and setup of the OSC may be coordinated by the Mechanical Maintenance Supervisor on shift. This Mechanical Maintenance Supervisor serves as the Interim OSC Supervisor until relieved. Appendix A lists persons filling the position of OSC Supervisor. He supervises the maintenance and operations support activities and coordinates with the EC to carry out necessary tasks within the Plant.

5.4 Radiation Team and Leader The Health Physics Supervisor or alternate (see Appendix A) shall be the Primary Radiation Team Leader. He shall direct the actions of the Health Physics technicians, under the orders of the Emergency Coordinator,'o support the maintenance and operations activities with proper radiological monitoring. The Senior Health Physics representative on site is designated as the Interim Radiation Team Leader.

5.5 Shift Technical Advisor The Shift Technical Advisor's (STAs) primary responsibility during emergency situations is accident assessment. The STA also provides technical support to the Emergency Coordinator for corrective actions and plant repair.

I t Page 4 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY

5.0 RESPONSIBILITIES

(continued) 5.6 Fire Team and Leader The Fire Team provides the first line response to a fire on-site. The Nuclear Watch Engineer is the Fire Team Leader, This position is manned continuously, but, if he is not available, the Nuclear Plant<perator (NPO) acts as his alternate. See E-Plan Implementing Procedure No. 3100025E, "Fire Emergencies," for detailed description.

5.7 First Aid/Personnel Decontamination Team and Leader The Chemistry Supervisor shall be the Primary First Aid/Personnel Decontamination Team Leader with a Chemistry Technician as his alternate.

A Senior Nuclear Plant Operator, trained in first aid and personnel decontamination, shall be the Interim Team Leader. If no Chemistry Department personnel are available, any trained employee could act as a First Aid/Personnel Decontamination Team member until primary team members can be called in.

5.8 Security Team and Leader The Plant Security Supervisor shall be the Primary Security Team Leader with the Assistant Plant Security Supervisor as his alternate. The Security Shift Specialist shall act as the Interim Security Team Leader. Personnel control and accountability are the responsibilities of the Security Team. The Security Team Leader shall notify the Emergency Coordinator of personnel not accounted for, as soon as possible after concluding accountability efforts.

5.9 Rescue Operations Rescue Operations shall involve the First Aid/Personnel Decontamination Team and the Radiation Team as necessary. Under the control of the Radiation Team Leader, entry to potentially hazardous areas shall be made by the First Aid/Personnel Decontamination Team with assistance from the Radiation Team. Upon notification of the injury, both teams shall respond per the Emergency Coordinator's instructions.

5.10 Re-Entry Team Re-entry teams shall be formed as necessary in accordance with E-Plan Implementing Procedure 3100027E, "Re-Entry.'

'I I

Page 5 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY

5.0 RESPONSIBILITIES

(continued) 5.11 Recovery and Restoration Team Recovery and Restoration Operations shall involve all emergency teams as necessary. Team members shall be assigned from available plant staff.

5.12 Emergency Planning Coordinator The Emergency Planning Coordinator shall=be responsible to ensure the quarterly verification and updating of the emergency call directory and the autodialer database. Personnel in the directory shall notify the Emergency Planning Coordinator when a change pertinent to information appearing in the directory occurs.

6.0 REFERENCES

6.1 St. Lucie Plant Radiological Emergency Plan (E-Plan).

6.2 E-Plan Implementing Procedures, as follows:

EPIP 3100021E, "Duties and Responsibilities of the Emergency Coordinator."

EPIP 3100025E, "Fire Emergencies."

EPIP 3100027E, "Re-Entry."

6.3 HP-200, "Health Physics Emergency Organization."

6.4 HP-203, "Personnel Access Control During Emergencies."

6.5 Administrative Procedure 0010518, "Fitness For Duty - Call-Out and For Cause Testing."

6.6 NRC Generic Letter 91-14, Emergency Telecommunications.

~

6.7 NRC Administrative Letter 94-04, Change of the NRC Operations Center Commercial Telephone and Facsimile Numbers.

7.0 RECORDS

This procedure requires no records.

Page 6 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EM ERGENCY ORGANIZATION AND CALL DIRECTORY

8.0 INSTRUCTIONS

8.1 Upon notification by the Emergency Coordinator (EC), the Interim Team Leaders shall assemble their teams and prepare to respond as necessary to the emergency.

8.2 Upon notification by the EC, the Duty Call Supervisor (DGS), will initiate staff augmentation in accordance with Figure 3, Staff Augmentation Call Tree. The DCS will use the (automated dialing) Emergency Recall System or Appendix A, Duty Call Supervisor Call Directory, to notify persons to fill the positions of Radiation Team Leader, TSC Supervisor, Emergency Coordinator, Operations Coordinator, Chemistry Team Leader, OSC Supervisor and Security Team Leader.

8.3 Instructions for use of the Emergency Recall System are in the ANPS office in either Control Room. If the system is not used continue with the next step.

8.4 The DCS will record the names of persons filling positions as well as the expected times of arrival at the plant on a form similar to Figure 3.

8.5 Persons filling the positions of Radiation Team Leader (alternate) and Chemistry Team Leader (alternate) will notify the appropriate number of individuals from their respective departments in accordance with Figure 3 (See Appendix B, Radiation Team Leader and Chemistry Team Leader Call Directory).

8.6 The TSC Supervisor (alternate) shall call the necessary persons to establish the minimum staff per Figure 3. He may call additional persons, as necessary (See Appendix C, Technical Support Center Supervisor Call Directory).

8.7 The OSC Supervisor (alternate) shall call the necessary persons to establish the minimum staff per Figure 3. He may call additional persons, as necessary (see Appendix D, Operational Support Center Supervisor Call Directory) ~

8.8 To assist the OSC Supervisor, an Electrical and Mechanical Maintenance Call Directory is provided as Appendix E.

8.9 All calls made should document the person contacted, time of the call and comply with the requirements of Administrative Procedure 0010518, "Fitness For'Duty - Call-Out and For Cause Testing."

Page 7 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY

8.0 INSTRUCTIONS

(continued) 8.10 Appendix F is the Call Directory to assist the Emergency Coordinator in initial notifications.

8.11 Appendix G provides a listing of other useful phone numbers.

8.12 FPL Beeper System

1. Instructions for beeper activation A. Onsite: Dial 8-375-1111 Offsite: Dial 1-800-447-2433 B. After the tone, enter pager number:

Enter the four (4) digit (XXXX) number for the pager of the person you wish to beep.

C. After the tone, enter number to be displayed:

Enter the phone number where you wish to be called - then press the

¹ symbol twice.

D. Thank you for calling Terminate call.

Page 8 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY FIGURE 1 Plant General Emergency Coordinator Manager Nuclear Plant Supv.

(EC) or alteroate Interim Team Leaders Emergency Teams Primary Team Leaders As directed by None Recovery 8 Restoration Recovery Manager Health Physics Senior Supervisor Health Physics Radiation Representative or alternate Alternate Alternate Nuclear Watch Nuclear Watch Engineer Engineer (NWE)

Fire Nuclear Plant Oper.

Nuclear Plant Operator (NPO)

Senior Nuclear Plant Operator Chemistry Supervisor First Aid & Personnel or:

Decontamination Associate Nuclear or alternate Plant Operator (ANPO)

Security Shift Plant Security Supervisor Supervisor Alternate Security or Protected Area alternate Guard Re-Entry (formed as required)

NOTE To be qualified to fill an emergency team position, individuals must have received annual training as specified in EPIP 3100034E, "Maintaining Emergency Preparedness - Emergency Response Plan Training."

Page 9 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY FIGURE 2 INITIALNOTIFICATION FLOW EMERGENCY COORDINATOR STATE OF FLORIDA DUTY CALL PLANT DIVISION OF SUPERVISOR GENERAL EMERGENCY MANAGER MANAGEMENT STATE OF FLORIDA EMERGENCY DHRS OFFICE EMERGENCYTEAM TEAM OF RADIATION LEADERS MEMBERS CONTROL EPZ COUNTIES NUCLEAR FPL OFFSITE EMERGENCY DIVISION DUTY EMERGENCY RESPONSE OFFICER ORGANIZATION DIRECTORS (5)

USNRC (2)

OPERATIONS CENTER LOCAL SUPPORT (4) INTERIM

1. FIRE/AMBULANCE EMERGENCY

2. MEDICAL TEAMS iLEG END NOTES Primary Notification Pathway (1) via State Hot Ring Down telephone (HRD)

~ ---- Alternate Notification Pathway (2) via Emergency Notification System (ENS)

(3) Medical & Fire Emergencies only. as needed (4) via Plant Public Address System (PA)

(5) NDDO is the Emergency Control Officer (ECO) for Inlthl noNlcathn (0023E-A WPG)

Page 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY FIGURE 3 STAFF AUGMENTATION CALL TREE DUTY CALL SUPERVISOR Radfatlon TSC Emergency Security Operations OSC Chemistry Team Supervisor Coordinator Team Coordinator Supervisor Team Leader 102 101 Leader 110 tsy . - Leader 103 109 104 Time: Time: T}me~ }lmm Tlmo:

}11} HP Man tho EOF (1) Chemistry 151 155 (3) Communlcatlonsf (1) Mochanlcal Notiftcatfon Mafntenax>>

106 105 107 106 (2) Eloctrfcaf'alntonanco (1) (2) Mechanical I&C'alntonenco Malntonanco 152 156 153 154 158 NOTES:

1. Number (e.g., 102, 106, etc.) axrosponds to position number In (automated dialing) Emergoncy ftocalf System.

'.2. Number In paronthesls fs tho number of persons needed In that posltfon.

'Ihe Specfal Crew, when onslte, normally meets these requirements.

(3100023E-8. WPG)

Page 11 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX A DUTY CALL SUPERVISOR CALL DIRECTORY (Page 1 of 2)

TITLE NAME HOME WORK BEEPER MOBILE 103 Radiation Team Leader (RTL) - Health Physics Supervisor RTL H. F. Buchanan (8-1~7) 595-2505 X7300 Alt. 1 RTL H. M. Mercer (9) 878-3862 X7302 7590 AIL 2 RTL R. M. McCullers (8-1-407) 334-3270 X7301 7613 Alt. 3 RTL L. L Large (9), 878-3463 X7303 7597 102 TSC Supervisor TSC Supervisor D. M. Stewart (8-1-407) 334-4600 X7037 2410 Alt. 1 S. A. Valdes (8-1-407) 334-5029 X7060 Alt. 2 M. J. Snyder (9) 466-8837 X7036 104 First Aid/Personnel Decontamination Team and Chemistry Team Leader (CTL)

Chemistry Supervisor CTL R. J. Frechette (9) 465-8003 X3213 Alt. 1 CTL R. Cox (8-1-407) 334-8763 X3393 Alt. 2 CTL D. H. Faulkner (9) 465-1024 X3391 Ait. 3 CTL K. E. Beichel (9) 465-0207 X3556 157 OSC Supervisor OSC Supervisor C. D. Scott (8-1-407) 283-4871 X7025 2411 Alt. 1 A. W. Mawin (8-1-407) 334-1472 X7122 7390 Alt. 2 R. J. Davis (8-1-407) 692-3451 X7124 2401 109 Secu rity Team Leader (STL) - Plant S ecurity Supervisor STL W. G. White (9) 879-3597 X4176 2160 Alt. 1 STL, R. W. Czamecki (9) 878-6193 X4175 2171 Alt. 2 STL Security Shift Specialist X4174

II Page 12 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX A DUTY CALL SUPERVISOR CALL DIRECTORY (Page 2 of 2)

TITLE NAME HOME WORK BEEPER MOBILE 101 -

Emergency Coordinator (EC) Plant General Manager EC J. Scarola (8-1~7) 334-4663 X7103 2155 (8-1407) 285-0134 Alt. 1 EC J. A. West (8-1-407) 288-1708 X7105 7262 (8-1-407) 285-4641 Alt. 2 EC C. H. Wood (8-1-407) 334-1530 4310 (8-1-407) 595-2426 Alt. 3 EC C. D. Marple (9) 562-4531 X7294 2457 Alt. 4 EC C. L. Burton (8-1-407) 340-2018 X7106 (8-1407) 285-5773 110 Ope ratio ns Coordinator - 0 perations Supervisor Operations Coord. C. H. Wood (8-1-407) 334-1530 X7034 4310 (8-1-407) 595-2426 Alt. 1 C. D. Marple (9) 562-4531 X7294 2457 Alt. 2 W. L. Hagar (9) 878-5186 X3571N7123 2412 Alt. 3 R. D. Welter (9) 878-5166 X3571/X7394 2461 R. A. Storke (8-1-407) 334-7348 X3571 2460 P. B. Isaacs (8-1-407) 283-8238 X35711X7395 2451 J. S. Sandy (8-1-407) 229-2713 X3571 2463 C. D. Ladd (8-1-407) 337-0399 X3571 4311 J. P. Honeysett (9) 878-6122 X3571 6585

J N 4

Page 13 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX B RADIATION TEAM LEADER AND CHEMISTRY TEAM LEADER CALL DIRECTORY (Page 1 of 2)

TITLE NAME HOME WORK BEEPER 151 PSL Rad Team J. P, Ross (8-1-407) 286-3704 X41 16/4178 M. W. Routten (9) 879-0419 X4116 B. R. Horrell (8-1-407) 334-3850 X4116 B. H. Robertson (9) 466-0759 X4020 6534 M. W. Sandel (9) 878-4741 X411 6 J. H. Ledbetter (8-1-407) 564-9859 . X7318 D. R. Reisinger (8-1-407) 692-9147 X4116 C. T. Bogacki (8-1-407) 335-4269 X4116 M. P. Berube (8-1-407) 337-9003 X4116 V. G. Bradley (9) 878-1817 X4116 L. B. Bullington (9) 878-0689 X4116 D. J. Christensen (8-1-407) 286-4352 X4116 C. H. DeVilling (8-1-407) 335-0142 X3648 J. O. Elbert (8-1-407) 288-7289 X4116 J. J. Gross (8-1-407) 778-5818 X4178 D. R. Herrington (9) 466-6803 X4116 D. S. Hurlbutt (8-1-407) 334-1968 X4116 J. M. Levulis (9) 879<850 X4116 K. A. McKay (9) 465-4313 X4116 R, H. Nelson (9) 466-7534 X4116 R. C. Reed (8-1-407) 287-2612 X4116 R. L. Ruppel (9) 466-2479 X4178 A. B. Sexton (9) 465-4193 X4178 G. B. Shelley (8-1-407) 287-5644 X7319 6537 J. G. Shalkowski (8-1-407) 337-9146 X4116

Page 14 of 27 ST, LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX B RADIATION TEAM LEADER AND CHEMISTRY TEAM LEADER CALL DIRECTORY (Page 2 of 2)

TITLE NAME HOME WORK BEEPER 151 (continued)

S. B. Starkey (8-1-407) 283-7958 X4116 R. E. Wilson (8-1-407) 334-3842 X3430 J. Adderly, (9) 467-1831 X4116 R. VanErem (8-1-407) 335-5485 X4116 2598 J. B. Scott (8-1-407) 398-0243 X4116 D. Cooper (8-1-407) 229-6136 X4178 K. W. Payne (8-1-407) 334-7250 X7304 7621 R. B. Somers (8-1-407) 334-3763 X7305 7604 V. E. Munne (9) 879-1614 X3430 7591 B. K. Mouring (9) 879-3917 X7310 7612 E. C. Beurrier (9) 878-5003 X3545 1599 A. G. Wier (8-1-407) 288-2583 X3503 7385 D. K. Debock (8-1-407) 335-7690 X5284 7611 J. R. Smith (9) 466-7376 X5284 7291 D. C. Haithcox (8-1-407) 334-3739 X7309 7593 L. E. Jacobus (9) 879-0377 X7308 7397 L. L. Large (9) 878-3463 X7303 7597 R. M. McCullers (8-1-407) 334-3270 X7301 7613 L. E. Pugh (8-1-407) 288-2304 X7307 7581 155 Chemistry Supervisor D. A, Harte (8-1-407) 334-1161 X3208 K. E. Beichel (9) 465-0207 X3556 A. P. Butler (9) 465-4817 X3207 R. Cox (8-1-407) 334-8763 X3390 D. H. Faulkner (9) 465-1024 X3391

Page 15 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX C TECHNICAL SUPPORT CENTER SUPERVISOR CALL DIRECTORY (Page 1 of 1)

TITLE NAME HOME WORK BEEPER 106 TSC Communicator W. C. Green (8-1-407) 221-1852 X7075 2402 J. E. Hallem (9) 878-4173 X7244 2435 M. W. Wolaver (8-1-407) 337-0975 X7083 2418 V. N. Mendoza '(9) 460-1575 X7076 2447 S. C. Mead (8-1-407) 334.3206 X7247 2404 J. A. Hurchalla (8-1-407) 283-3192 X7257 D. Fields (8-1-407) 388-9083 X3426 2419 105 Reactor Engineering R. E. Supervisor B. Parks (8-1-407) 220-4583 X7035 7435 Alt. 1 W. D. Mead (8-1-407) 225-2567 X7293 2397 Alt. 2 R. M. Klein (8-1-407) 221-3233 X7292 2396 Alt. 3 P. K. Wachtel (9) 468-6804 X7089 241 5

Page 16 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX D OPERATIONAL SUPPORT CENTER SUPERVISOR CALL DIRECTORY (Page 1 of 1)

TITLE NAME HOME WORK BEEPER 107 Electrical Maintenance Representative W. N. Dean (8-1-407) 336-9289 X7074 2403 H. D. Casper (8-1-407) 336-8769 X7047 2556 R. L. Kulavich (9) 879-9717 X7080 2409 L. H. Clark (8-1-407) 398-3228 X7061 . 4362 L. J. Bossinger (8-1-407) 283-0930 X7110 2574 108 Mechanical Maintenance Representative J. G. Brady (8-1-407) 220-9424 X3021 2392 R. Toscano (9) 465-7993 X7415 2431 T. P. Sanders (8-1-407) 334-5529 X7038 2438 G. Pustover (8-1-407) 546-3011 X7401 7359 153 I 8c C Reentry Supervisor T. C. Glenn (8-1-407) 283-7856 X7430 7843 R. Sherman (8-1-407) 336-7757 X3603 7853 J. V. Kawa (8-1-407) 337-1727 X7337 2590 C. D. Connell (8-1-407) 334-2931 X3286 7861 F. L. Kenessey (9) 879-6645 X3601 7852 R. M. Law (8-1-407) 335-4533 X3536 7858 E. C. Ordway (8-1407) 335-3066 X3608 7838 F. P. Gusmano (8-1-407) 335-9720 X3649 7870 L. D. Hiegel (9) 770-2061 X3604 7857 T. A. Newhouse (9) 489-6790 X3930 7862 ~

Page 17 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX E ELECTRICAL AND MECHANICALMAINTENANCE CALL DIRECTORY (Page 1 of 1)

TITLE NAME HOME WORK BEEPER 152 Electrical Reentry Supervisor R. L. Hoskins (8-1-407) 334-4439 X4128 4309 J. E. Sissons (8-1-407) 287-8313 X3231 2424 H. R. Bishop (9) 464-4135 X4280 2557 H. D. Casper (8-1-407) 336-8769 X3540 156 Electrica I Chief P. Porter (8-1-407) 287-5969 X5433 2586 B. Cabot (8-1-407) 334-3216 X3437 2589 S. A. Joiner (8-1407) 567-1647 X3331 D. J. Page (8-1-407) 3344138 X7267 2588 G. G. Schweppe (8-1-407) 334-0899 X3121 154 Mechanic al Reentry Supervisor W. F. Haines (9) 464-0476 X7416 2428 R. L. Cline (9) 465-8199 X4132 2430 A. Martens (8-1-407) 221-0383 X4118 2429 R. J. Erickson (8-1-407) 334-5429 X4216 2426 158 Mechanic al Planner A. G. Rice (8-1-407) 569-4195 X7434 2445 L. K. Bean (8-1-407) 221-7254 X7427 6393 P. M. Griffis (8-1-407) 334-3265 X7432 6391 M. J. Rentz (8-1-407) 283-5389 X7444 6403

Page 18 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX F EMERGENCY COORDINATOR'S CALL DIRECTORY (Page 1 of 5)

• 1 ~ State Warnin Point - Division of Emerg. Mgt., (DEM)

Primary Hot Ring Down telephone (HRD) Dial 100 Alt. 1 NAWAS Primary (8-1-904) 413-9911 (DEM)

Alt. 2 Commercial phone Alt. 1 (8-1-904) 413-9912 (DEM)

Alt. 2 (8-1-904) 488-8676 (Highway Patrol)

Telecopy (8-1-904) 488-6366 NOTE In addition, the Local Government Radio (LGR) provides a means to relay a message to the state of Florida through either St. Lucie or Martin County once radio contact with the county has been established.

• 2. Emer enc Coordinator NAME HOME WORK MOBILE Plant General J. Scarola (8-1-407) 334-4663 X7103 (8-1-407) 285-0134 Manager Alt. 1 J.A. West (8-1-407) 288-1708 X7105 (8-1-407) 285-4641 Alt. 2 C. H. Wood (8-1-407) 334-1530 X7034 (8-1-407) 595-2426 Alt. 3 C. D. Marple (9) 562-4531 X7294 Alt. 4 C.L. Burton (8-1-407) 340-2018 X7106 (8-1-407) 285-5773 "3. Nuclear Division Du Officer NDDO Refer to the Nuclear Division Duty Officer Schedule, in the Duty Call Information notebook located in the Unit 1 and Unit 2 ANPS offices.

• Call dictated per EPIP 3100021E, "Duties and Responsibilities of the Emergency Coordinator".

Page 19 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX F EMERGENCY COORDINATOR'S CALL DIRECTORY (Page 2 of 5)

4. NRC FTS 2000 Emer enc Telecommunications S stem ETS Dialing Procedures The FTS 2000 Network utilizes dial tone from one of the FTS 2000 Network Services, Nodes located throughout the United States. To place a call over FTS 2000, Network, a user must do the following:

A. Lift the receiver on the telephone instrument and listen for dial tone; B; After receiving dial tone, dial the first number listed on the sticker located on the telephone instrument using all 10 digits. If the first number is busy, proceed on with the second, etc.

NOTE No access codes need to be dialed. Only dial the appropriate 10 digit telephone number.

Emer enc Notification S stem ENS Primary (301) 816-5100 Backup (301) 951-0550 Second Backup (301) 415-0550 "5. NRC Resident Ins ectors SITE OFFICE HOME BEEPER D. Prevatte X3410 464-7822 (9) 467-8814 6922 (FPL)

M. Miller X3411 464-7822 (9) 878-7107 6928 (FPL)

" Call dictated per EPIP 3100021E, "Duties and Responsibilities of the Emergency Coordinator."

Page 20 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX F EMERGENCY COORDINATOR'S CALL DIRECTORY (Page 3 of 5)

6. ~SA DHRS, Office of Radiation Control (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) 8-1-407 297-2095 NOTE When calling DHRS after 5 pm on weekdays or any time during weekend or holidays the phone will be answered by an answering service. Tell the answering service to Please patch me directly through to the On-Call DHRS Representative.

Florida Highway Patrol (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) 8-1-904 488-8676

7. ~Ct A OFFICE EMERGENCY NOTE Prefix (9) is not needed if the Fort Pierce line is used to call St. Lucie County.

A. Civil Defense St. Lucie County Dept. of Public Safety (8:00 a.m. - 5:00 p.m.) (9) 461-5201 (9) 911 Martin County Public Safety Department (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) (8-1-407) 287-1668, (8-1-407) 911 B. Law Enforcement St. Lucie County Sheriff (9) 461-7300 (9) 911 Martin County Sheriff (8-1-407) 220-7000 (8-1-407) 911 C. Fire and Rescue St. Lucie County (9) 911 Martin County (8-1-407) 911

Page 21 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX F EMERGENCY COORDINATOR'S CALL DIRECTORY (Page 4 of 5)

8. ~MCh I S Onsite Medical Clinic X4206 /

Martin Memorial Medical Center (North) X3017'8-1-407)

Emergency Room 223-5995 Main Desk (ask for Emergency Room) (8-1-407) 287-5200 NOTE If unable to contact hospital, call Martin County Dispatcher, (8-1-407) 287-1 668 and ask that information be relayed to the Martin Memorial Hospital - North Emergency Room.

Lawnwood Regional Medical Center Emergency Room (9) 468-4551 Main Desk (ask for Emergency Room) (9) 461-4000 REAC/TS (8-1-615) 576-3131 U.S. Dept. of Energy Oak Ridge, TN 24 Hour Number (8-1-615) 481-1000 (Ask for REAC/TS)

~ . ~OI A Explosive Ordnance Disposal 66th Ordnance Det.

Cape Canaveral Air Station (8-1-407) 853-9951 Federal Bureau of Investigation Local (9) 461-6142 Miami (8-1-305) 944-9101

)

. Page 22 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX F EMERGENCY COORDINATOR'S CALL DIRECTORY (Page 5 of 5)

9. ~atl A i

( Ii d)

NOANNWS Melbourne Office (8-1-407) 254-6923, 6083 Telecopy (8-1-407) 255-0791

10. Plant Phone Numbers A. Control Rooms OUTSIDE LINE PLANT Unit 1 465-7140 X3268 288-0800 X3302 X3293 Unit 2 466-7069 X3533 286-6291 X3534 X3535 B. Hot Rin Down Locations PSL Unit 2 Control Rm, 126 State Warning Point 100 Office Of Radiation Control DHRS 110 PSL Unit 1 Control Room 125 PSL TSC 127 PSL EOF 124 St. Lucie County EOC 131 Martin County EOC 141 All Station Ring Down A*

Page 23 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY i APPENDIX G OTHER PHONE NUMBERS (Page 1 of 5)

TITLE NAME HOME WORK BEEPER MOBILE 300 Vice President St. Lucie Plant D. A. Sager (8-1M7) 334-6776 X7100 2010 (8-1-407) 485-0508 114 ERDADS Operator D. Anthony (9) 468-2921 X7354 1661 S'. L. Miles (9) 468-3010 G. J. Patel (9) 466-9188 X7350 2599 119 System and Component Engineering D. M. Stewart (8-1-407) 334-4600 X7037 2410 S. A. Valdes (8-1407) 334-5029 X7060 R. J. Riha (8-1<07) 879-0988 X7246 2421 W. C. Green (8-1-407) 221-1852 X7075 2402 J. E. Hallem (8-1-407) 878-4173 2435 117 I & C Maintenance L. A. Rogers (8-1-407) 283-3799 X7065 2459 .

T. C. Glenn (8-1-407) 283-7856 X7430 7843 R. C. Olson (8-1-407) 334-0604 X7108 2416 J. V. Kawa (8-1-407) 337-1727 X7337 2590 L. Neely (8-1-407) 340-4930 X4148 R. Gonzalez (8-1-407) 334-1616 X7348 1252 115 Plant Engineering D. H. West (8-1-407) 286-2781 X7495 2385 C. O'Farrill (8-1-407) 743-4345 X7480 2137 118 Training D. H. Borgmann (9) 878-7386 X4265 5327 G. J. Imbriale (8-1-407) 225-5196 X3328 2602 K. Carpenter (9) 878-1191 X3787

Page 24 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX G OTHER PHONE NUMBERS (Page 2 of 5)

TITLE NAME HOME WORK BEEPER 170 Fire Protection Representative R. A. McDaniel (8-1-407) 286-6923 X7168 2793 R. T. Behre (8-1-407) 335-3661 X7173 6449 W. H. Sandel (8-1-407) 286-5195 X7172 2794 W. C. Alfera (8-1-407) 340-3763 X7171 2791 164 System an d Component Eng ineering Representative E. A. Dill (8-1-407) 335-4149 X7332 L. W. Harbach (8-1-407) 334-7041 X7248 R. J. Riha (8-1-407) 879-0988 X7246 2421 F. T. Orr (9) 464-0862 X7254 K. A. Mayhew (8-1-407) 287-8118 X7245 2604 J. R. Williams (9) 878-2163 X7077 2029 Nuclear Materials Managem ent Representative J. Chesser (9) 461-2765 X4199 M. Ullmann (8-1-407) 337-5538 X4184 A. Neuberger (9) 231-6752 X4180 6494

Page 25 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX G OTHER PHONE NUMBERS (Page 3 of 5)

CONTROL ROOMS UNIT 1 Emergency Notification System (ENS)

Hot Ring Down (HRD) Station ~125 Outside Lines 288-0800, 465-7140 Plant Extensions X3268, 3293, 3302 Telecopier 468-4153 UNIT 2 Emergency Notification System (ENS)

Hot Ring Down (HRD) Station 0126 Outside Lines 286-6291, 466-7069 Plant Extensions X3533, 3534, 3535 Telecopier 468-4253 TECHNICAL SUPPORT CENTER Emergency Notification System (ENS)

Health Physics Network (HPN)

Hot Ring Down (HRD) Station 0127 TSC/EOF Direct Line Outside Lines 461-8067, 461-8077 Dose Assessment 466-6642

Page 26 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX G OTHER PHONE NUMBERS (Page 4 of 5)

TECHNICAL SUPPORT CENTER (continued)

Telecopier 461-4457 TSC Supervisor X3260 Emergency Coordinator X3279 Operations Coordinator X3270 TSC/OSC Coordinator X3257 Plant Extensions X3250, 3251, 3252, 3261, 3264, 3271, 3275, 3276, 3278, 3280, 3281, 3282, 3296, 3298, 3299.

OPERATIONAL SUPPORT CENTER OSC Supervisor X3650 Plant Extensions X3651, 3652, 3654, 3655, 3656, 3659, 3661, 3698 SECURITY TELECOPIER NUMBER Plant Extensions X4177, 3193

Page 27 of 27 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100023E, REVISION 68 ON-SITE EMERGENCY ORGANIZATION AND CALL DIRECTORY APPENDIX G OTHER PHONE NUMBERS (Page 5 of 5)

EMERGENCY OPERATIONS FACILITY Commercial Phone ¹'s 468-26NN - the NN for some of the EOF groups are:

Switch Board 00 Emergency Control Officer 75, 76 Recovery Manager 69, 70 Emergency Technical Manager 59, 60 Dose Assessment 30, 31, 32 Health Physics 84, 85 Orpnifax (facsimile) 42, 43 Hot Ring Down (HRD) Station ¹124 Site Assembl Station SAS Plant X3277 NOTE The Local Government Radio (LGR) is available in both Unit t and Unit 2 Control Rooms, the Technical Support Center and the Emergency Operations Facility.

The Company Radio is available in all Emergency Response Facilities (portable hand-held units are used in the Operational Support Center).

Page 1 of 14 FLORIDA POWER S. LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E REVISION 19

1.0 TITLE

CRITERIA FOR AND CONDUCT OF EVACUATIONS PROCEDURE f%00UCTION 2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group 7/25 1975 Approved by K. N. Harris Plant General Manager 7/29 1975 Revision 19 Reviewed by F R G 2/14 1995 Approved by C. L. Burton Plant General Manager 2/14 1995 THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN, PLEASE READ ENTIRE PROCEDURE BEFORE PROCEEDING. /R19

3.0 SCOPE

3.1 Puruose This procedure provides criteria for determining if evacuation of a local area on-site or the Owner Controlled Area should be carried out. It provides instructions for effecting an ordered, rapid and safe evacuation of a local area or the Owner Controlled Area, It also provides instructions for personnel accountability.

3.2 Discussion 1 ~ Accurate classification of emergencies that may occur at the plant is necessary to enable the Nuclear Plant Supervisor to take the proper corrective action and to know when to initiate the Emergency Plan. For those emergencies involving high radiation and/or the release of radioactive material to the environment, it is necessary to provide the Nuclear Plant Supervisor (Emergency Coordinator) with guidelines that will enable him to know when to S OPS order a Local Evacuation or Owner Controlled Area DATE Evacuation. DOCT PROCEDURE DOC N 3100026E sYs COMP COMPLETED ITM 19

Page 2 of 14 ST. LUCIE PLANT t

EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

3.0 SCOPE

(continued) 3.2 (continued)

2. A Local Evacuation or Owner Controlled Area Evacuation may be necessitated by the occurrence of any of several events where evacuation of personnel would be necessary to minimize their exposure to radiation.

An Owner Controlled Area Evacuation will be conducted for any Site Area Emergency or General Emergency.

3. A Local Evacuation of Nonessential Personnel from the Protected Area will be conducted for any Alert occurring during a Normal Workday.

3.3 Authoritur The St. Lucie Plant Radiological Emergency Plan.

3.4 Definitions

~Abl A The location to which evacuated personnel report. In a Local Evacuation, personnel evacuate and assemble in a location designated by the Emergency Coordinator.

In an Owner Controlled Area Evacuation, personnel from the Protected Area will report to the offsite Assembly Area at Jaycee Public Park on Highway A1A, 7 1/2 miles north of the plant or Jensen Beach Parking Area 6 miles south of the plant, as directed by the Emergency Coordinator.

2. Escort An individual specifically assigned to accompany other persons who are required by the Security Plan or Health Physics Manual to be escorted.

3, Essential Personnel Personnel essential to plant operation or currently filling or relieving an on-site emergency response position, including all qualified operators.

Page 3 of 14

\ ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

3.0 SCOPE

(continued) 3.4 (continued)

4. Health.Ph sics Office Area The Health Physics Office Area, located in each of the Auxiliary Buildings, is likely to be used as an Assembly Area during a Local Evacuation of a radiologically affected area.

5. Local 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, Protected Area or other portion of the Owner Controlled Area.

6. Nonessential Personnel Personnel NOT essential to plant operation or currently filling or relieving an on-site emergency response position.

7. Normal Workda The hours of 0700 to 1530 on all weekdays except holidays.

8. 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 site boundary line on the attached Florida Power 8 Light property plan, Figure 1 of this procedure).

9. Owner Controlled Area Evacuation The evacuation from the Owner Controlled Area of all personnel except those required to place the plant in a safe condition, the emergency teams and the guards necessary to fulfilltheir evacuation responsibilities.

10. Protected Area The area (within the Owner Controlled Area) occupied by the nuclear units and associated equipment and facilities enclosed within the security perimeter fence.

Page 4 of 14 S T. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

3.0 SCOPE

(continued) 3.4 (continued)

~ai A An area to which Nonessential Personnel initially report upon declaration of an Alert.

For Alert declarations during Normal Workdays, the Protected Area will be evacuated and Staging Areas are designated as follows:

A. Nuclear Training Center Room 123 - all Nonessential Personnel who park in the north parking lot.

B. 8-11 HP Training Classroom - all nonessential FPL personnel who work inside the Protected Area and who park in the east parking lot.

C. 8-12 SBI Offices Training Classroom - all nonesseritial FPL personnel who work outside the Protected Area and who park in the east parking lot.

D. 8-12 Speakout Classroom/Central Outage Processing Point - all nonessential non-FPL personnel who park in the east parking lot For times other than Normal Workdays, Staging Areas are determined for each department by its department head.

4.0 PRECAUTIONS

4.1 Efforts shall be made to maintain personnel exposures as low as reasonably achievable.

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 an Assembly Area until they have been monitored for possible contamination, unless they are injured.

Injured personnel shall be treated as discussed in E-Plan Implementing Procedure 3100021E, "Duties and Responsibilities of the Emergency Coordinator."

4.3 Except as discussed in 4.2 above, personnel reporting to an Assembly Area shall group according to departments in order to facilitate personnel accountability and monitoring.

Page 5 of 14 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

4.0 PRECAUTIONS

(continued) 4.4 When reporting to an Assembly Area, take the most direct route possible, but do not use any route or area that has been declared part of the emergency area or that could result in excessive individual exposure or injury.

4.5 If ari area or building is evacuated, any records regarding the persons in the area shall be removed and taken to the appropriate Assembly Area, 4.6 Health Physics personnel exiting the RAB as necessitated by an emergency condition of possible radiological nature shall pick up suitable portable radiation monitoring equipment which would be required for re-entry monitoring.

5.0 RESPONSIBILITIES'.1 The Nuclear Plant Supervisor is responsible for:

1. Classifying and declaring any emergency that may occur at the site.

2. Initiating the Emergency Plan when appropriate.

3. Initiating the evacuation of any area in which the criteria for evacuation as expressed in steps 8.1 and 8,2 are met.

5.2 The Nuclear Plant Supervisor shall act as Emergency Coordinator after declaration of an emergency.

5.3 The Emergency Coordinator is responsible for advising the Security Team Leader of a Local Evacuation or an Owner Controlled Area Evacuation. This notification will be by the alarm or the PA system. Information needed by the Security Force to properly fulfilltheir responsibilities during the evacuation shall be provided to the Security Team Leader by the Emergency Coordinator (see E-Plan Implementing Procedure 3100021E, "Duties and Responsibilities of the Emergency Coordinator" ).

5,4 The Security Guard Force is under the supervision of the Plant Security Supervisor. He serves as the Primary Security Team Leader. The Security Shift Specialist is the Interim Security Team Leader.

5.5 The responsibilities of individuals acting as Escorts are contained in Sections 5.11 and 8.3.2 of this procedure.

Page 6 of 14 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO, 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

5.0 RESPONSIBILITIES

(continued) 5.6 All personnel permanently or temporarily assigned to St. Lucie Plant shall receive as part of General Employee Training (GET), information concerning:

1 ~ Plant Alarms

2. Evacuation

3. The locations of the evacuation Assembly Areas:

A. The Health Physics Office Areas in the Auxiliary Buildings B. Staging Areas for Protected Area evacuation as defined in Section 3.4.

C. The Jaycee Public Park on Route A1A, north of the plant site (see Figure 2),

D. The Jensen Beach Parking Area on Route A1A, south of the plantsite (see Figure 2).

E. Other location(s) as determined by the Emergency Coordinator.

5.7 It shall be the responsibility of each supervisor and department foreman not involved in the emergency response to assist in accounting for all personnel under his supervision, 5.8 Security Department responsibilities are defined in Security Procedure 0006123.

5.9 Security shall maintain accurate records of all personnel entering or leaving the Protected Area and make the records available when required.

5.10 An Assembly Area Supervisor will be responsible to ensure that personnel accounting is being done at the Off-site Assembly Area and serve as the liaison to the Emergency Coordinator and/or Operational Support Center (OSC) Supervisor.

5.11 Tour guides are assigned to escort groups of visitors during tours of the plant site. In an emergency, tour guides are responsible for personnel accountability of their respective groups and the evacuation of their group in cooperation with the Security Force.

Page 7 of 14 ST, LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO, 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

6.0 REFERENCES

6.1 St. Lucie Plant Radiological Emergency Plan (E-Plan) 6.2 E-Plan Implementing Procedures, as follows:

EPIP 3100021E, "Duties and Responsibilities of the Emergency Coordinator" EPIP 3100027E, "Re-entry" 6.3 St, Lucie Plant Security Plan 6.4 Security Procedure 0006123.

6.5 HP-207, "Monitoring Evacuated Personnel During Emergencies" 6.6 HP-208, "Personnel Decontamination During Emergencies" 7.0 RECORDS AND NOTIFICATIONS:

7.1 A list of all persons at the Off-site Assembly Area shall be prepared by the Assembly Area Supervisor 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.

J

Page 8 of 14 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

8.0 INSTRUCTIONS

8.1 Criteria for Local Evacuation The need for Local Evacuation shall be determined in. accordance with the following criteria:

Evacuate the affected local area in which any of the following conditions occur:

1. Area Radiation Monitor Alarm.

2. Containment Evacuation Alarm.

3. Unevaluated direct radiation dose rate increase in excess of 100 mRem/hour above normal levels.

4. Unexpected airborne radioactivity concentration in excess of 1 x Ci/cc.

10'icro

5. Removable radioactive surface contamination in an unposted area in excess of 1000 dpm/100 cm'eta-gamma over an area of 100 ft'.

6. Removable radioactive surface contamination in an unposted area in excess of 50 dpm/100cm'lpha over an area of 100 ft'.

7. Alert declaration during a Normal Workday (Protected Area evacuation).

8. 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 Owner Controlled Area should be evacuated.

Page 9 of 14

'i ST, LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

8.0 INSTRUCTIONS

(continued) 8.3 . Evacuation Pre aredness All visitors shall have adequate transportation available on-site to evacuate all members of their respective groups.

Escorts shall maintain control of groups or individuals to which they are assigned to enable all members of the groups to be located, notified and evacuated.

8.4 Local Evacuation Im lementation If Health Physics personnel confirm any of the radiological conditions in Section 8.1, they shall notify the Nuclear Plant Supervisor.

2. When the Emergency Coordinator (Nuclear Plant Supervisor) determines that a Local Evacuation is necessary, he shall, in following E-Plan Implementing Procedure 3100021E, "Duties and Responsibilities of the Emergency Coordinator," announce an evacuation using the PA system, giving the area to be evacuated, any radiologically affected area if known, the Assembly Area and other instructions as required.

3. All personnel in the evacuation area shall stop work, turn off potentially hazardous equipment, such as cutting torches and leave the area by the same route taken to enter the area, unless otherwise instructed by the Emergency Coordinator.

Unless otherwise directed by the Emergency Coordinator, all personnel in a radiologically affected evacuated area shall contact H.P. and report to the H.P. Office Area of the affected unit's Auxiliary Building for monitoring and accountability.

The Radiation Team shall monitor evacuated personnel for contamination (for areas where contamination may have been present).

Injured personnel shall be treated as discussed in E-Plan Implementing Procedure 3100021E. If an injured person is evacuated from the plant site, the person's TLD and direct-reading dosimeter, should be removed and given to the First Aid and Personnel Decontamination Team Leader who should in turn, provide the items to Health Physics.

Page 10 of 14

~

ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

8.0 INSTRUCTIONS

(continued) 8.4 (continued)

7. The Emergency Coordinator, department supervisors and foremen having personnel working in the evacuated area shall verify that all personnel in the evacuated area are accounted for.

8. The Control Rooms, Technical Support Center and Operational Support Center shall report facility accountability to Security.

The Emergency Coordinator shall initiate a search for the personnel who have not been accounted for.

8.5 Owner Controlled Area Evacuation Im lementation When the Emergency Coordinator (Nuclear Plant Supervisor) 'determines that an Owner Controlled Area Evacuation is necessary, he will order an evacuation using the PA system and the evacuation alarm as described in E-Plan Implementing Procedure 3100021E, "Duties and Responsibilities of the Emergency Coordinator."

2. All personnel in the evacuation area shall stop work, turn off potentially hazardous equipment such as cutting torches and leave the area. All personnel not needed to place the affected unit in a safe condition and not on an emergency team or otherwise required on site, shall evacuate.

Emergency Teams shall report to the OSC for assignment.

3. Injured personnel shall be treated as discussed in E-Plan Implementing Procedure 3100021E. If an injured person is evacuated from the plant site, the person's TLD and self-reading dosimeter should be removed and given to the First Aid and Personnel Decontamination Team Leader who should in turn, provide the items to Health Physics.

4 Personnel shall remove protective clothing prior to leaving the Radiation Controlled Area.

5. Personnel shall proceed to any Security-Plant Access Station by the most direct route, unless an alternate route is specified by the Emergency Coordinator.

6. Each person shall then proceed to the off-site Assembly Area (see Figure 2), as directed by the Emergency Coordinator.

Page 11 of 14 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

8.0 INSTRUCTIONS

(continued) 8.5 (continued)

7. Assemble by department for accounting and monitoring and remain at the off-site Assembly Area until given instructions by the Assembly Area Supervisor.

8. If the conditions associated with the emergency are such that the Jaycee Park area is untenable, the Emergency Coordinator shall direct all personnel to report to the Jensen Beach Parking Area.

9. The department supervisors and foremen shall account for their personnel at the off-site A sembly Area.

10. The Emergency Coordinator, in conjunction with the Radiation Team Leader will determine the need for personnel monitoring dependent on radiological conditions at the time of evacuation of the Owner Controlled Area. All personnel shall be monitored for contamination prior to leaving the off-site Assembly Area, as appropriate.

11. The Control Rooms, Technical Support Center and Operational Support Center shall report facility accountability to Security.

12, The Assembly Area Supervisor shall report personnel accountability to Security.

13. Security shall examine all the personnel records available to determine if any personnel are unaccounted for.

14. The Emergency Coordinator shall initiate a search for the personnel who have not been accounted for.

8.6 Securi Force Evacuation Im lementation

1. Upon notification of an evacuation, the Security Shift Specialist (Interim Security Team Leader) shall advise by radio all other guards on duty that an evacuation is in progress. The Security Force will proceed with the evacuation of persons and with personnel accountability activities,

Page 12 of 14 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100026E, REVISION 19 CRITERIA FOR AND CONDUCT OF EVACUATIONS

8.0 INSTRUCTIONS

(continued) 8.6 (continued)

2. The Security Team shall:

A. Sweep the plant site to verify that all personnel have evacuated.

B. Immediately review badge records.

C. Report initial accountability to the Emergency Coordinator.

D. As instructed by the Emergency Coordinator, initiate a search for the personnel who have not been accounted for.

E. Perform additional duties as specified in the Security Instructions.

3. 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 FPL Off-Site Emergency Security Manager or Emergency Coordinator of any circumstances which require his attention or assistance.

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Page 2 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

3.0 SCOPE

(continued) 3.2 (continued)

1. (continued)

3. To perform operations which may mitigate the effect of the emergency or hazardous condition. /R16

4. To determine the nature and extent of the emergency and/or radiological conditions. /R16 5, To establish definite personnel exclusion area boundaries.

2. The Re-entry Team members should be selected based on appropriate qualifications in First Aid, Operations, Health Physics, Maintenance and Security.

3. The initial entry of the Re-entry Team, and all subsequent entries, until radiation areas have been properly marked, shall take place under the direction of the Radiation Team Leader.

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

3.3 ~Authorit:

The St. Lucie Plant Radiological Emergency Plan.

Page 3 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

4.0 PRECAUTIONS

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

4.2 The EC may waive the requirements of this procedure to allow access for search and rescue for injured or lost personnel ~

4.3 The EC may waive the requirements of this procedure to place the plant in a safe shutdown condition or mitigate a release.

4.4 The NPS/ANPS may authorize re-entry into the plant for performing EOP steps and Emergency Team actions.

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

4.6 The team members should not deviate from the planned route, unless required by un-anticipated conditions such as rescue, performing an operation which would minimize the emergency conditions, etc.

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

4.8 The following is the Nuclear Energy Policy on Exposure Limits for Emergency Response Personnel.

1. Exposure to emergency response personnel should be maintained As Low As Reasonably Achievable (ALARA). Actions taken during an emergency should take into consideration the amount of exposure required to accomplish the task versus the potential benefit to the public health and safety. /R16

2. Conditions may warrant re-entry into high radiation areas leading to exposure in excess of the regulatory limit. Except for rescue of personnel (life-saving only), authorization must be given in advance by the Emergency Coordinator (EC) in consultation with the Radiation Team Leader (RTL) (or alternates). /R16

Page 4 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

4.0 PRECAUTIONS

(continued) 4.8 (continued)

2. (continued)

If time permits, the EC should obtain concurrence from the Recovery Manager (RM) (if the Emergency Operations Facility (EOF) is operational) or one of his superiors in plant management. In any case where regulatory limits have, been exceeded the EC shall notify the RM of the event. /R16

3. For those remote circumstances involving an event in progress, and

-obtaining EC approval will result in leaving the accident scene or decrease the victim(s) chance of survival, lifesaving actions may be performed without obtaining EC approval. The EC shall be notified immediately following the rescue operation.

4. Re-entry personnel that have been selected/chosen to exceed regulatory exposure limits should be volunteers, be broadly familiar with the risks involved (radiosensitivity of fetuses, effects of acute exposures, etc.) and whose normal duties have trained them for such missions.

5. Declared pregnant persons should not be used as "onsite emergency workers." /R16

/R16

6. For the following missions,

/R16

"'he exposure limit is: TOTAL THYROID@

DOSE'TED E) (CDE) /R16 Performance of actions that would 5 REM 50 REM not directly mitigate the event, minimize escalation, or minimize effluent releases. /R16 Performance of actions that mitigate 10 REM 100 REM the escalation of the event, rescue persons from a non-life threatening situation, minimize exposures or minimize effluent releases.

Page 5 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

4.0 PRECAUTIONS

(continued) 4.8 (continued)

6. (continued)

TOTAL DOSE THYROID( ) /R16 (TED E) (CDE) /R16

. Performance of actions that 25 REM 250 REM decrease the severity of the event or terminate the processes causing the event in an attempt

%o control effluent releases to avoid extensive exposure of large populations. Also, rescue fp situation.

~ fp P ~fif -fP<<

situation, (Volunteers should be above the age of 45.)"'OTE

1. Both Total Dose (TEDE) and Thyroid Dose (CDE) should be used for purposes of controlling exposure.

2. Protective clothing, including respirators, should be used where appropriate.

"'xposure limits to the lens of the eye are 3 times the Total Dose (TEDE) values listed.

"'otal Dose (TEDE) is the total dose from both external and internal

'weighted) sources - Total Effective Dose Equivalent.

@ Thyroid Dose (CDE) commitment from internal sources - Committed Dose Equivalent. The same dose limits also apply to other organs (CDE), skin (Shallow Dose Equivalent) and extremities (Extremity Dose Equivalent) ~

"'olunteers with full awareness of risks involved including numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects.

Page 6 of 17 ql Wi~

ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

4.0 PRECAUTIONS

(continued) 4.8 (continued)

6. (continued)

"'o upper limit for Total Dose (TEDE) and/or Thyroid Dose (CDE) has been established because it is not possible to pre-judge the risks that one person should be allowed to take to save the life of another. Also, no specific limit is given for thyroid dose since in the extreme case, complete thyroid loss might be acceptable sacrifice for a life saved.

This should not be necessary if respirators and/or thyroid protection for rescue personnel are available as the result of adequate planning. /R16

/R16 4.9 A Re-entry Team shall consist of at least two persons.

5.0 RESPONSIBILITIES

5.1 The Emergency Coordinator has the responsibility for authorizing re-entry into an area after it has been evacuated.

5.2 The Emergency Coordinator provides priorities for Re-entry Team formation and dispatch. Typically, the sequence of priorities will be:

1. Mitigate the accident sequence.

2. Mitigate a release of radioactivity.

3. Rescue injured or trapped personnel.

4. Gather information to assess the accident.

5. Protect plant assets.

5.3 The EC also has the responsibility for authorizing exposure to Re-entry Teams that are in excess of the EPA 400 limits. /R16

/g J

Page 7 of 17 ql jts ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

5.0 RESPONSIBILITIES

(conttnued) 5.4 The Radiation Team Leader shall be responsible for the supervision of the initial entry into an evacuated area, and for all subsequent entries until radiation areas have been properly marked and a safe route determined. He shall also make recommendations to the Emergency Coordinator as to the expected doses the Re-entry Team personnel will be subjected to and the feasibility of attempting re-entry into a given area.

5.5 The Operational Support Center (OSC) Supervisor is responsible for selecting Re-entry Team personnel in conjunction with Re-entry Team Supervisors.

5.6 The OSC Supervisor is responsible for ensuring Re-entry Teams are properly briefed and that forms documenting the team's mission and expected exposure are in order.

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

/p Page 8 of 17

) l 'il ) ~

ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

6.0 REFERENCES

6.1 St. Lucie Plant Radiological Emergency Plan (E-Plan) 6.2 E-Plan Implementing Procedures, as follows:

EPIP 3100026E, "Criteria for and Conduct of Evacuations."

6.3 HP-2, "FPL Health Physics Manual."

6.4 HP-200, "HP Emergency Organization" 6.5 HP-201, "Personnel Exposure Control" 6.6 HP-203, "Personnel Access Control During Emergencies" 6.7 Nuclear Energy Policy on Exposure Limits for Emergency Response Personnel, Revision to Policy Statement.

Ltr. No. JNO-HP-94-056, 26 October, 1994. /R16 6.8 Security Procedure 0006123 7.0 RECORDS AND NOTIFICATIONS:

Detailed records of all significant actions of the Re-entry Team shall be recorded by the Emergency Coordinator, and/or the Operational Support Center (OSC)

Supervisor.

Page 9 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

8.0 INSTRUCTIONS

8.1 The Emergency Coordinator shall:

1. Provide priorities for Re-entry Team formation and dispatch. Typically the sequence of priorities will be:

1. Mitigate the accident sequence.

2, Mitigate a release of radioactivity.

3. Rescue injured or trapped personnel.

Gather information to assess the accident.

5. Protect plant assets.

2. Notify the Recovery Manager of any authorization for emergency exposure to personnel. If possible the EC should discuss this with the RM prior to entry.

8.2 The Radiation Team Leader or his designee shall:

1. Evaluate the emergency to determine the possible dose rates and stay times. Refer to Step 4.8 of this procedure for guidelines. /R16

2. Supervise the initial entry of the Re-entry Teams into the area of the emergency and any subsequent entries until radiation areas have been properly marked.

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

4. Assure that all Re-entry personnel are properly equipped with protective clothing, high range dosimeters, low range dosimeter, TLD, respiratory devices and other protective equipment as required.

5. Specify self-monitoring and decontamination procedures for the Re-entry Teams.

Page 10 of 17 I~ ~

ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

8.0 INSTRUCTIONS

(continued)

NOTE Refer to the HP-200 series procedures for additional guidelines and actions to be taken by the Health Physics Department personnel upon implementation of the PSL Radiological Emergency Plan.

8.3 Operational Support Center (OSC) Supervisor shall:

1. Establish communications with the Technical Support Center (TSC) by contacting the TSC Supervisor or TSC/OSC Coordinator (refer to EPIP 3100023E, "Onsite Emergency Organization and Call Directory" for ghone numbers) and providing contact phone numbers for OSC personnel.

2. Declare the OSC activated (refer to EPIP 3100032E, "Onsite Support Centers" for initial staffing).

NOTE See Section 4.2 through 4.4 for special conditions that allow expediting teams from the OSC.

3. Coordinate re-entry activities requested by the Emergency Coordinator.

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

5. Brief the team members concerning the nature of the emergency and the possibility of hazards being present.

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

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

2. Operate equipment as needed.

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

4. Establish definite personnel exclusion areas and access routes.

r Page 11 of 17

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ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY

8.0 INSTRUCTIONS

(continued) 8.3 (continued)

7. Complete Appendix C, "Re-entry Team Request Form," /R16

8. Ensure copies of Appendices are available for OSC personnel.

8.4 The Re-entry Team members shall:

1 ~ Wear protective clothing and other protective devices and dosimetry as specified by the Radiation Team Leader.

2. unless unanticipated conditions are encountered, follow the pre-planned route into the affected area and perform the assigned jobs quickly and safely.

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

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

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

6. Record and report to the Emergency Coordinator, or his designee, the radiological conditions and extent of damage in the affected area. /R16 8.5 The Emergency Coordinator and the appropriate Emergency Team Leaders shall evaluate the existing conditions and plan further actions as required.

Page 12 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY APPENDIX A OSC RE-ENTRY TEAM SUPERVISORS - RESPONSIBILITY LIST (Page 1 of 3)

1. Upon notification of emergency, notify emergency response Re-entry Team members.

2. At an ALERT declaration or higher, report to the OSC.

3. Assist in preparation and set-up of the OSC.

4. Report emergency response personnel available from your group to the OSC Supervisor.

5. Obtain dosimetry (as appropriate), designated reference materials and procedures.

6. Determine operability of communications equipment and other tools/supplies, as necessary.

7. Report equipment problems/facility activation status to the OSC Supervisor.

8. Initiate and maintain documentation of activities in a log (notebook).

9. Identify emergency repair/control activities through discussions with the OSC Supervisor.

10. Select Re-entry Team members and Team Leader, as appropriate.

11. Coordinate with the HPOSC on selection of Re-entry Team members (exposure histories, respiratory qualification status, authorization to exceed 10CFR20 exposure limits, if necessary).

12. Coordinate with HPOSC to determine routes to work location, necessity for protective equipment and HP escort.

13. Direct Re-entry Team members to obtain protective equipment, if necessary, and other equipment for repair/damage activities.

14. Assist in Team briefing prior to dispatch as requested by the OSC Supervisor.

Page 13 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY APPENDIX A OSC RE-ENTRY TEAM SUPERVISORS - RESPONSIBILITY LIST (Page 2 of 3)

15. Obtain approval of OSC Supervisor to dispatch Re-entry Team.

16. Dispatch Re-entry Team.

17. Document Team assignment, organization, time of dispatch, etc..

18. Provide Team tracking information to the OSC Supervisor.

19. Inform OSC Status Board Recorder of Team dispatch and information for OSC Status Board.

20. Communicate with Re-entry Team on status/activities.

21. Inform OSC Supervisor of Re-entry Team activities,

22. Contribute status of activities being conducted during OSC Status Updates when requested by the OSC Supervisor.

23. Evaluate need to replace dispatched Re-entry Team members with other personnel

24. Direct Re-entry Team members to report to the OSC Supervisor upon return to the OSC for debrief.

25. Inform OSC Status Board Recorder of Re-entry Team return for update of OSC Status Board.

26. Coordinate with HPOSC on update of exposure records for Re-entry Team members, if required.

27. Direct Re-entry Team members to restore equipment, as necessary, and stand by for further instructions.

28. Coordinate shift relief activities with the OSC Supervisor.

Page 14 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY APPENDIX A OSC RE-ENTRY TEAM SUPERVISORS - RESPONSIBILITY LIST (Page 3 of 3)

29. Perform shift turnover with alternate Re-entry Team Supervisor, when directed.

30. Direct shift turnover of Re-entry Team personnel, when directed.

31. When directed to deactivate OSC, direct Re-entry Team personnel to evaluate status of equipment/supplies, report deficiencies, return equipment to storage and turn in documentation.

32. Report status of equipment/supplies to the OSC Supervisor upon OSC deactivation.

33. Transmit activities log, originals of team tracking information and any other paperwork generated during the emergency to the OSC Supervisor upon deactivation of the OSC.

Page 15 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY APPENDIX B OSC RE-ENTRY TEAM MEMBERS - RESPONSIBILITY LIST (Page 1 of 2)

Upon declaration of an emergency, notify or report to the Re-entry Team Supervisor.

2. Obtain briefing from the Re-entry Team Supervisor on performance of emergency repair/damage control activities, radiological conditions, exposure limits, routes to work location and protective equipment, if necessary.

'3. Obtain tools/supplies and communications equipment necessary to perform emergency repair/damage control activities.

Determine operability of equipment.

5. Report equipment problems to the Re-entry Team Supervisor.

6. Don personal protective equipment/clothing/dosimetry, if directed by the Re-entry Team Supervisor and HPOSC.

7. Proceed to work location and perform emergency repair/damage control activities, as directed by the Re-entry Team Supervisor.

8. Maintain communications with the Re-entry Team Supervisor.

9 Request additional personnel/equipment, as necessary, through the Re-entry Team Supervisor.

10. Check dosimetry/monitor exposure while performing emergency response activities.

11. Report to the OSC Supervisor on return to the OSC for debrief.

12. Provide OSC Supervisor with observations/activities at work location.

13. Restore equipment as directed by the Re-entry Team Supervisor.

14. Provide dosimetry to OSC Dose Recorder for exposure history update.

15. Stand by for further instructions from the Re-entry Team Supervisor.

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Page 16 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY APPENDIX B OSC RE-ENTRY TEAM MEMBERS - RESPONSIBILITY LIST (Page 2 of 2)

16. Perform shift turnover when directed by the Re-entry Team Supervisor.

17. Evaluate condition of equipment/supplies when directed to deactivate the OSC.

18. Report equipment/supply status and deficiencies to the Re-entry Team Supervisor.

19. Return equipment and supplies to storage upon OSC deactivation.

Page 17 of 17 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100027E, REVISION 16 RE-ENTRY APPENDIX C RE-ENTRY TEAM REQUEST FORM (Page 1 of 1)

Requester: Request Number:

Date/Time Received:

1. Reason for Request:

2. Team Number:

3. Task

Description:

4. Team Members:

5. Briefing Information:

Special Instructions:

Communications Method:

Controlling Facility:

Briefing Completed by:

Team Dispatched (OSC Approval): Time

8. Debriefing Information:

Task Completed: 0 Yes C3 No Additional Entry Required: Cl Yes 0 No Observations/Work Performed/Hazards:

Debriefing Completed by: Time:

Page 1 of 17 FLORIDA POWER 8 LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO, 3100027E REVISION 16

1.0 TITLE

RE-ENTRY 2.0 REVIEW AND APPROVAL: ~~ PROOUCBON Reviewed by Facility Review Group 7/25 1975 Approved by K. N. Harris Plant General Manager 7/29 1975 Revision 6 Reviewed by F R G 1/5 1995 Approved by C. L. Burton Plant General Manager 1/5 1995

3.0 SCOPE

3.1 Puruose

This procedure provides the instructions for the selection and deployment of Re-entry Teams.

3.2 Discussion Re-entry into an evacuated area shall be made only when authorized by the Emergency Coordinator and under the direction of the Radiation Team Leader (RTL) or Interim RTL for one or more of the following reasons:

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

2. To assist in evacuating injured or incapacitated personnel from the affected area. /R16 S OPS DATE DOCT PROCEDURE DOCN 3100027E sYs COMP COMPLETED ITM 16

C) 4~5 HOtT .UQGFiil 3AUU~>CK'

Page 1 of 22 FLORIDA POWER 8 LIGHT COMPANY ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E REVISION 16

1.0 TITLE

ON-SITE SUPPORT CENTERS 2.0 REVIEW AND APPROVAL: PRQCEOURE PFX DL'CiiOH Reviewed by Facility Review Group 3/20 8, 3/25 1981 Approved by A.D. Schmidt V.P. Power. Res. 3/26 19 81 Revision 16 Reviewed by Facility Review Group 4/4 1995 Approved by C. L. Burton Plant General Manager 4/4 1995

3.0 SCOPE

3.1 Purpose This procedure provides guidelines and responsibilities for activation and use of the on-site Technical and Operational Support Centers.

3.2 Discussion The activities of plant management, technical and engineering support personnel are an important part of the overall site response to an accident and must be properly defined and logistically supported. The need for additional operational support personnel, other than those required and allowed in the Control Room, is also recognized as vitally important in properly responding to an emergency.

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

DATE DOCT PROCEDURE DOCN 3100032E sYs COMP COMPLETED ITM 16

Page 2 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS

3.0 SCOPE

(continued) 3.3 Description 1 ~ Technical Support Center (TSC)

The TSC is located adjacent to the Unit 1 Control Room. Representative emergency supplies available for the TSC are listed in Table 1.

Documents and drawings available are listed, in part, in Table 2.

2. Operational Support Center (OSC)

The targe conference room on the second floor of the North Service Building serves as the OSC. Representative emergency supplies available for the OSC are listed in Table 3.

3. Communications Equipment The Control Room contains necessary telephone and public address systems for communications within and outside the plant. The Control Room also contains special telephones and Local Government Radio for communications with state and county agencies.

The TSC contains necessary telephones to communicate with the Control Room, OSC, the Nuclear Division Management Center, the Emergency Operations Facility and outside agencies. It also contains an Emergency Notification System (ENS) and Emergency Response Data System (ERDS) to the NRC Operations Center and the NRC Region II Office.

3.4 Authority 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 Technical and Operational Support Centers shall be monitored when required to be in use. Radiation levels in the TSC should be monitored using available (stored in Unit 1 Control Room) portable instruments.

Page 3 of 22 S T, LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS

4.0 PRECAUTIONS

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

5.0 RESPONSIBILITIES

5.1 The Emergency Coordinator is responsible for activating the TSC, activating the OSC and arranging for staffing through the Duty Call Supervisor.

5.2 The Emergency Coordinator has the overall responsibility for the conduct of emergency operations and activities and should work closely with the TSC to ensure all information is used in making accident recovery decisions.

5.3 The TSC Supervisor is responsible for supervising TSC activities, reporting to the Emergency Coordinator and communicating with the Emergency Operations Facility (EOF).

5.4 The TSC Supervisor is responsible for providing Security with a roster of TSC personnel as soon as practical.

5.5 Each department head or designated alternate is responsible for reporting to the TSC when called, 5.6 The OSC Supervisor is responsible for supervising OSC activities and

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maintaining communications with the Emergency Coordinator and the TSC.

5.7 The OSC Supervisor is responsible for providing Security with a roster of OSC personnel as soon as practical.

5.8 Re-entry Team Supervisors who report to the OSC should ensure that the essential equipment needed by their team members is readily accessible to the OSC. If necessary, these team supervisors should arrange for additional equipment to be transported to a convenient storage area.

5.9 Those reporting to the Operational Support Center are responsible for being prepared to carry out support functions designated by the Emergency Coordinator.

Page 4 of 22 S T. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS

5.0 RESPONSIBILITIES

(continued) 5.10 Health Physics Department shall provide a portable monitor to the Technical Support Center for radioiodine monitoring. This monitor can also be used for monitoring the Unit 1 Control Room. An additional monitor will be made available for use in the Unit 2 Control Room, 5.11 Technical Staff Department is responsible for establishing the communication between the St. Lucie Plant's Emergency Response Data Acquisition and Display System (ERDADS) and the NRC's Emergency Response Data System (ERDS).

5.12 The Information Services Department is responsible for ensuring that records, documents and prints are maintained in the TSC or are available for immediate use in the Nuclear Records Vault.

6.0 REFERENCES

6.1 St. Lucie Plant Radiological Emergency Plan (E-Plan).

6.2 E-Plan Implementing Procedures, as follows:

EPIP 3100021 E, "Duties and Responsibilities of the Emergency Coordinator" EPIP 3100022E, "Classification of Emergencies" EPIP 3100027E, "Re-entry" EPIP 3100033E, "Off-Site Dose Calculations" 6.3 NUREG 1394, Emergency Response Data System (ERDS).

7.0 RECORDS; 7.1 A record of actions taken at the TSC will be maintained by the TSC Supervisor.

7,2 A record of actions taken at the OSC will be maintained by the OSC Supervisor.

Page 5 of 22 S T. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS

8.0 INSTRUCTIONS

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

1. TSC A. Appendix A, TSC Activation Checklist, may be used to assist in the activation of the TSC.

B. Appendix B may be used to assist in initiating and terminating communication between the St. Lucie Plant's ERDADS and the NRC's ERDS.

2. OSC A. Appendix E, OSC Activation Checklist, may be used to assist in the activation of the OSC.

8.2 Staffing The Emergency Coordinator shall arrange for staffing through the Duty Call Supervisor. Table 4 identifies the initial staffing requirements for both the TSC and OSC.

8.3 Site Accountability The TSC Supervisor should ensure Appendix D, Control Rooms and TSC Personnel Accountability Form or its equivalent, is completed and provided to Security in a timely manner,

2. The OSC Supervisor should ensure Appendix F, OSC Personnel Accountability Form or its equivalent, is completed and provided to Security in a timely manner.

3. A Security telecopier number is provided in EPIP 3100023E, "On-Site Emergency Organization and Call Directory."

Page 6 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS

8.0 INSTRUCTIONS

(continued) 8.4 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. Primary tasks shall be to relieve the Control Room of off-site communications to the state and local agencies, NRC and the FPL Off-Site Emergency Response Organization and to perform off-site dose calculations. These tasks become the responsibility of the Emergency Operations Facility (EOF) when manned and fully operational. The TSC staff shall provide technical support as requested by the Emergency Coordinator and shall direct itself toward determining current and projected plant status and providing in-depth diagnostic and engineering assistance, as required. Information shall be provided to the EOF in support of core damage assessment.

8.5 Use of the Operational Support Center

1. The Emergency Coordinator shall assign available plant staff not needed in the TSC or Control Room to the OSC. The OSC Supervisor shall maintain communications with the TSC and report as directed by the Emergency Coordinator or TSC Supervisor.

2. When the OSC is set up, the Interim OSC Supervisor or OSC Supervisor should identify the following:

A. Any areas of the plant which have been evacuated B. The nature of the emergency and the Emergency Classification in effect C. Any teams or individuals who are known to be working in the plant, their task and the communication method/controlling facility

Page 7 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS

8.0 INSTRUCTIONS

(continued) 8.5 (continued)

3. The OSC Supervisor's primary functions are to supervise the OSC staff, respond to requests from the TSC and maintain accountability of personnel assigned to the OSC. Since teams may be dispatched from the OSC prior to the evacuation of any plant areas, the OSC Supervisor and Health Physics Supervisor in the OSC (HPOSC) must evaluate the event in progress and determine the most likely trends in radiological conditions. If the event is likely to result in evacuation of areas of the plant, the teams should be dressed, equipped and briefed, similarly to re-entry teams. After area evacuations are ordered, the OSC Supervisor shall ensure the requirements of EPIP 3100027E, "Re-entry" are carried out.

8.6 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, 8.7 Alternate OSC In the event that the OSC becomes untenable, the Emergency Coordinator shall designate an alternate location.

8.8 Periodic Status Appendix C contains a checklist which may be used by the TSC during periodic status updates.

Page 8 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS TABLE 1 RADIOLOGICAL EMERGENCY EQUIPMENT ST. LUCIE PLANT CONTROL ROOM STORAGE LOCKERS UNIT 1/TECHNICAL SUPPORT CENTER AND UNIT 2 Self Contained Breathing Apparatus

2. Pocket Dosimeters

3. Dosimeter Charger

4. TLDs

5. Coveralls

6. Hoods

7. Gloves Shoe Covers Full Face Respirators and Filters

10. Portable Count Rate Instrumentation 11 ~ Portable Dose Rate Instrumentation

12. Contamination Smears and Envelopes Radiation Tape/Rope

14. Radiological Signs

15. Step-Off Pads

16. Plastic Bags NOTE An Industrial First Aid Kit is maintained in both Control Rooms as part of the plant First Aid Program.

Page 9 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS TABLE 2 EMERGENCY DATA, DRAWINGS AND DOCUMENTS MAINTAINEDAT THE TSC ST. LUCIE PLANT

1. Plant Technical Specifications

2. Plant Operating Procedures

3. Emergency Operating Procedures

4. Emergency Plan and Implementing Procedures

5. Final Safety Analysis Report

6. Drawings, Schematics and Diagrams

Page 10 of 22 S T. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS TABLE 3 RADIOLOGICALEMERGENCY EQUIPMENT ST. LUCIE PLANT OPERATIONAL SUPPORT CENTER

1. Coveralls

2. Shoe Covers

3. Hoods 4, Gloves

5. Full Face Respirators and Filters

6. Self Contained Breathing Apparatus

7. Pocket Dosimeters

8. Dosimeter Chargers 9 TLDs

10. Portable Count Rate Instrumentation

11. Portable Dose Rate Instrumentation

12. Radiological Signs

13. Contamination Smears and Envelopes

14. Flashlights

15. Survey Maps

16. Writing Materials

17. Log Book

18. Decontamination Kits

19. Radiological Tape/Rope

20. Selected Procedures

21. Waste Storage Bags

22. Assorted Batteries

Page 11 of 22 S T. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS TABLE 4 ONSITE SUPPORT CENTERS ST. LUCIE PLANT INITIALSTAFFING TECHNICAL SUPPORT CENTER Emergency Coordinator Core Damage Analyst Chemistry Team Leader Electrical Maintenance 'echanical Maintenance Radiation Team Leader (3) Communicators Support Staff as determined by the Emergency Coordinator and TSC Supervisor.

OPERATIONAL SUPPORT CENTER OSC Supervisor (2) Electrical Maintenance (11) Health Physics l&C Maintenance (2) Mechanical Maintenance Chemistry Support Staff as determined by the Emergency Coordinator and OSC Supervisor.

I Page 12 of 22 S T. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX A TECHNICAL SUPPORT CENTER ACTIVATIONCHECKLIST I. Initial Staffing and Activation Requirements TIME / INIT

1. TSC Activation initiated (ALERT Declared;

2. Phones Installed

3. ERDADS Link with NRC (ERDS) Established/Attempted

4. Communications Check Complete

5. Position Staffing/Name

a. Emergency Coordinator.

b. Radiation Team Leader:

c. Chemistry Team Leader:

d. Core Damage Analyst:

e. Electrical Maintenance:

f. Mechanical Maintenance:

g. Communicator:

h. Communicator:

i. Communicator:

6. TSC Declared Activated

Page 13 of 22 S T. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX A TECHNICAL SUPPORT CENTER ACTIVATIONCHECKLIST (continued)

II. Expanded Staffing TIME / INIT The Emergency Coordinator and TSC Supervisor determine appropriate additional TSC staffing.

NOTE The following list is provided as guidance. The Emergency Coordinator will determine required additional staffing as appropriate.

1. TSC Supervisor

2. Operations Coordinator

3. Reactor Engineering

4. Dose Assessment Analyst(s)

5. TSC/OSC Coordinator

6. Security

7. Communicators

a. State Warning Point

b. Health Physics Network (HPN)

c. Field Team Communicator

d. EOF Direct Line

8. Status Board and Log Keepers, Messengers

a. Plant Status

b. Radiological Conditions

c. Events Board

d. OSC Activities Board

e. TSC Log Keeper

f. Duplicating/Telecopying

Page 14 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX A TECHNICAL SUPPORT CENTER ACTIVATIONCHECKLIST (continued)

9. ERDADS Operator(s)

10. Problem Solving Team

a. Tech Staff

b. Mechanical Maintenance

c. Electrical Maintenance

d. I&C Maintenance

e. Plant Engineering /R16

f. Training (SRO)

11. Other

a. Combustion Engineering

b. Ebasco

c. Westinghouse

d. AT&T Technician TIME / INIT III. Long Term Staffing Review long term staffing requirements IV, Emergency Food and Water Supply Have food and water supply brought to TSC

Page 15 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX 8 (Page 1 of 2)

This appendix provides the instructions for initiating and terminating the communications link between the St. Lucie Emergency Response Data Acquisition and Display System (ERDADS) and the NRC Emergency Response Data System (ERDS). This communications link must be activated not later than one hour after declaring an emergency class of ALERT or higher. If communications cannot be established then the accepted method of data transmission to the NRC will be through the Emergency Notification System (ENS).

INITIATINGthe ERDS communication link:

1. At any TSC ERDADS terminal clear the display screen by depressing the CLEAR key.

2. Log on to ERDADS by typing in PSW ¹¹ XXXXXXXX(the Xs stand for the password issued to the Technical Staff Department) Then depress the EXEC key.

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3. Clear the screen with the CLEAR key and select the desired St. Lucie Unit by typing PUP UNIT X (the X will be either a 1 or 2 depending on the unit). Then depress the EXEC key.

Clear the screen by depressing the CLEAR key and type in ERD and depress the DSPLY

'. key. This will display the ERDS link control picture on the terminal.

Depress the TAB + keys to place the cursor on the INITIATE action bar and then depress the ENTER key. The depressing of the enter key will initiate the communications link to the NRC ERDS.

6. After the communication link with the NRC ERDS has been established clear the terminal screen by depressing the CLEAR key and log off by typing in PSW 0 and depressing the EXEC key, The logging off of the terminal's screen will allow that terminal to be used in obtaining information for TSC activities without affecting the communication link with the NRC ERDS.

7. Periodically check the status of the ERDS link by typing in HLX (the X will be a 2 for Unit 1 or 3 for Unit 2) and depress the DSPLY key.

NOTE If the blinking message NOTIFY THE NRC appears after the CURRENT STATUS then the communications link has been lost and a reconnection is necessary when the NRC requests it through the established voice connection in the TSC. If this happens then it will be necessary to reinitiate the communications link beginning with step 1.

Page 16 of 22 ST. LUCIE PLANT

'EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX B (Page 2 of 2)

NOTE Generally the ERDS link will be terminated by the NRC. The following steps are to be used if the link needs to be terminated from the TSC.

TERMINATING the ERDS communication link:

1. At any TSC ERDADS terminal clear the display screen by depressing the CLEAR key.

2. Log on to ERDADS by typing in PSW ¹¹ XXXXXXXX(the Xs stand for the password issued to the Technical Staff Department). Then depress the EXEC key.

3. Clear the screen with the CLEAR key and select the desired St. Lucie Unit by typing PUP UNIT X (the X will be either a 1 or 2 depending on the unit). Then depress the EXEC key.

Clear the screen by depressing the CLEAR key and type in ERD and depress the DSPLY key. This will display the ERDS link control picture on the terminal.

5. Depress the TAB - keys to place the cursor on the TERMINATE action bar and then depress the ENTER key. The depressing of the enter key will initiate the communications link to the NRC ERDS.

6. After the communication link with the NRC ERDS has been terminated clear the terminal screen by depressing the CLEAR key and log off by typing in PSW 0 and depressing the EXC key.

Page 17 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX C TSC PERIODIC STATUS UPDATE CHECKLIST

1. Overview Time:

Unit is in the Emergency Classification.

This results from the category.

Offsite communications are via: TSC (or) EOF.

PARs are from the: Emergency Coordinator (or)

Recovery Manager (EOF)

2. Plant Status:

3. Chemistry status (By Chem Team Leader):

4. Health Physics status (By HP Supv/Team Leader):

5. Problem Solving (By Problem Solving Team Leader):

6. OSC Status (By TSC/OSC Coordinator):

7. Plan / Strategy:

8. Concerns or Questions:

Page 18 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX D CONTROL ROOMS AND TECHNICAL SUPPORT CENTER PERSONNEL ACCOUNTABILITYFORM TSC Supervisor: TSC Ext:

PRINT LEGIBLY Date ~~

Name SSN Badge Number NOTE Telecopy this or an equivalent form to Security when complete.

Page 19 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX E OPERATIONAL SUPPORT CENTER ACTIVATIONCHECKLIST (Page 1 of 2)

I. Initial Staffing and Activation Requirements TIME / INIT

t. OSC activation initiated (ALERT Declared:~

2. OSC setup and telephone installation complete (a room setup and telephone arrangement similar to Figure t is recommended).

3. Communications established with TSC

4. Position Staffing/Name

a. OSC Supervisor:

b, Mechanical Maintenance:

c. Mechanical Maintenance:

d. Electrical Maintenance:

e, Electrical Maintenance:

f. I & C Maintenance:

g, Chemistry:

h. HP i ~ HP

Page 20 of 22 S T. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX E OPERATIONAL SUPPORT CENTER ACTIVATIONCHECKLIST (Page 2 of 2)

TIME / INIT I. (continued)

4. (continued)

I. HP

m. HP

n. HP

o. HP

p. HP

q. HP

r. HP

5. OSC Declared Activated II. Expanded Staffing

1. The Emergency Coordinator and OSC Supervisor determine appropriate additional OSC staffing.

III. Long Term Staffing 1, Review long term staffing requirements.

Page 21 of 22 ST, LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS APPENDIX F OPERATIONAL SUPPORT CENTER PERSONNEL ACCOUNTABILITYFORM Department: Completed by: OSC Ext.:

PRINT LEGIBLY Date: ~ /

Name SSN Badge Number TLD NOTE Telecopy this or an equivalent form to Security when complete.

k I

Page 22 of 22 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE NO. 3100032E, REVISION 16 ON-SITE SUPPORT CENTERS FIGURE 1 OPERATIONAL SUPPORT CENTER

, (Recommended Layout)

MM X3552 01P Conference EM X3559 Room kr Rrat AklTeam and HP Tecfrnkfana X3531 SEC HP HP X3M1 X 3555 Mechankal Mahfanance X3339 Etecakal Mafntenrmce X3253 IbC Step X4143 cr X3031

/R16

Page 1 of 51 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E REVISION 24

1.0 TITLE

OFF-SITE DOSE CALCULATIONS Z 0

2.0 REVIEW AND APPROVAL: PRO('CD>>'-

Reviewed by Facility Review Group 3/20 8 3/25 19 81 Approved by A.D. Schmidt V.P. Power Resources 3/26 19 81 Revision 24 Reviewed by F R G 10/23 19 95 Approved by J. Scarola Plant General Manager 10/23 19 95

3.0 SCOPE

3.1 Purpose

1 ~ This procedure provides a method for estimating Total Dose (TEDE) and Thyroid Dose (CDE) dose rates and projected Total Dose (TEDE) and Thyroid Dose (CDE) doses, via hand calculations.

3.2 Discussion

1. This procedure is applicable to both Unit 1 and Unit 2. Provisions have been made on Release Rate Worksheets to sum releases from both units.

A Unit should only be included if it is an AFFECTED unit.

S OPS DATE DOCT PROCEDURE DOCN 3100033E sYs COMP COMPLETED ITM 24

Page 2 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS

3.0 SCOPE

(continued) 3.2 (continued)

2. This procedure has an Appendix A for use by Technical Support Center (TSC) and/or Emergency Operations Facility (EOF) Dose Assessment personnel to cope with unmonitored releases resulting from rapid containment depressurization events. Additionally, Appendix B provides a method to back calculate a release rate from field team survey results. /R24

3. The'Emergency Coordinator or his designee will perform these off-site dose calculations, delegating this activity to the Chemistry Department representative if available or to the TSC or EOF when manned and operational.

4. A computer dose calculation model is available for use by the Chemistry Department representative. This model estimates off-site dose rates and cumulative doses when releases of radioactive materials occur during an emergency. This model closely parallels this procedure.

5. This activity will be performed by the dose assessment group in the EOF when it is manned and operational. The Chemistry Department should continue to perform dose assessments and compare results with the dose assessment group in the EOF.

6. The Emergency Coordinator will use these off-site dose estimates, release rates and radiation levels in containment for emergency classification or off-site protective action recommendations.

3.3 Definitions

1. AFFECTED UNIT (for this procedure): A reactor unit that has activated the emergency plan and has a RELEASE.

2. IODINE REMOVAL SYSTEM - is defined as any one Containment Spray occurring with its chemical addition system injecting the chemicals (Sodium hydroxide for Unit 1, Hydrazine for Unit 2).

Page 3 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS

3.0 SCOPE

(continued) 3.3 (continued)

3. RELEASE - During any declared emergency:

A. Any effluent monitor increase of (approximately) 10 times or one decade above pre-transient values OR B. Health Physics detecting airborne radioactivity levels in excess of 25% derived air concentration (DAC) OUTSIDE of plant buildings due to failure of equipment associated with the declared emergency.

4. PARTICULATE FACTOR (PF) - The additional factor is added when core melt or overheat is underway to account for the particulate in the release pathway.

5. SNF - The designation on the Dose Calculation Worksheets that refers to data that should be transferred to the State Notification Form.

6. PAR - The designation on the Dose Calculation Worksheets that refers to data that should be used when determining Protective Action Recommendations.

3.4 Authority The St. Lucie Plant Radiological Emergency Plan.

4.0 PRECAUTIONS

4.1 None

5.0 RESPONSIBILITIES

5.1 The Emergency Coordinator (EC) or his designee shall assure that dose rates and projected doses are calculated following releases of radioactive material during an emergency. The EC is responsible for developing and providing Protective Action Recommendations (PARs) to off-site authorities.

5.2 The Chemistry Department representative shall perform the Off-Site Dose Calculations upon arrival at the Technical Support Center at the direction of the Emergency Coordinator or his designee. The results of the calculation shall be given immediately to the EC.

Page 4 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS

6.0 REFERENCES

6.1 St. Lucie Plant Radiological Emergency Plan (E-Plan) 6.2 E-Plant Implementing Procedures, as follows:

EPIP 3100021 E, "Duties and Responsibilities of the Emergency Coordinator."

EPIP 3100022E, "Classification of Emergencies."

6.3 HP-2, "FPL Health Physics Manual."

'.4 St. Lucie Unit 1 FUSAR.

6.5 St. Lucie Unit 2 FUSAR.

6.6 NUREG-0654, Rev. 1, FEMA Rep-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, November, 1980.

6.7 NUREG/BR-150, Vol. 1, Response Technical Manual.

6.8 EPA-400-R-92-001, EPA Manual of Protection Action Guides and Protective Actions for Nuclear Incidents, October, 1991.

6.9 Bases for Accident Dose Calculations for St. Lucie Nuclear Power Plant (Bases prepared by HMM Associates of Waltham, Massachusetts).

7.0 RECORDS AND NOTIFICATIONS:

The attached worksheets shall be maintained in the plant files in accordance with Ql 17-PR/PSL-1, "Quality Assurance Records."

Page 5 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS

8.0 INSTRUCTIONS

NOTE Data required to perform emergency off-site dose calculations can be obtained from the Emergency Response Data Acquisition and Display system (ERDADS). ERDADS terminals are located in both the Unit 1 and Unit 2 Control Rooms, the on-site Technical Support Center (TSC), and the off-site Emergency Operations Facility (EOF).

CAUTION Ensure the ERDADS computer is addressing the affecte'd unit's database.

If needed, change the unit data being accessed by performing the following steps:

Press the CLEAR key Type PUP UNIT X (where X is the number of the unit you wish to change to)

Press the EXEC key NOTE Input data needed for dose calculations can be acquired from ERDADS on the following screens:

Input Data U/1 screen V/2 screen Fan Status SF1 SF2 Effluent Monitor Source Term RG1 RG2 Site Meteorological Conditions RG1 or SMD RG2 or SMD Steam Generator Blowdown R12 R22 Steam Jet Air Ejector R12 R22 To access information from these ERDADS screens, perform the following:

Press the CLEAR key Type the screen's name Press the DSPLY key

/R24

Page 6 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS

8.0 INSTRUCTIONS

(continued)

CAUTION Meteorological Wind Speed, Wind Direction and Delta Temperature values should vary with time, i.e., Chart Recorders in the Unit 1 Control Room and A1A Site Tower Sharck should not be straight lining. Investigate data that is unchanging.

8.1 Complete ONE METEOROLOGICAL DATA WORKSHEET, select one from the three prioritized methods listed below.

Primary Method MET WORKSHEET A - SITE TOWER The ERDADS terminals, Unit 1 Control Room and local Tower Chart Recorders provide 15 minute average data.

OR 1" alternate MET WORKSHEET B - WEST PALM BEACH AIRPORT This primary back up is for use if site tower data is not available.

OR 2" alternate MET WORKSHEET C - DEFAULT For use if both site tower and airport data is unavailable.

8.2 Select the DOSE CALCULATIONWORKSHEET indicated by the completed METEOROLOGICAL DATA WORKSHEET. The Dose Calculation Worksheet will be used to determine doses after the Release Rate Worksheet is completed.

/R24

Page 7 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SI TE DOSE CALCULATIONS

8.0 INSTRUCTIONS

(continued)

NOTE if both units are in a declared emergency and both units have or had a release, then the site release rate is the sum of both units'elease rates.

NOTE TO TSC / EOF DOSE ASSESSMENT PERSONNEL If a rapid, unexplained containment pressure reduction occurs (e.g., not due to operation of sprays, additional coolers, etc.) consult Appendix A.

8.3 Determine the Site Release Rate; Complete ONE RELEASE RATE WORKSHEET for each affected unit.

For the accident type, select one from the four prioritized methods listed below.

Primary method, CHEMISTRY GRAB SAMPLING All accidents for Unit 1: RELEASE RATE WORKSHEET - A1 for Unit 2: RELEASE RATE WORKSHEET - A2 OR 1" alternate, EFFLUENT MONITORS All accidents for Unit 1: RELEASE RATE WORKSHEET - B1 for Unit 2: RELEASE RATE WORKSHEET - B2 OR 2" alternate, CONTAINMENT HI-RANGE RADIATION MONITOR LOCA Only either Unit: RELEASE RATE WORKSHEET - C OR POST LOCA MONITORS, either Unit: RELEASE RATE WORKSHEET - D OR 3'~ alternate, DEFAULT, only if no other source of data is available AII accidents either Unit: DEFAULT RELEASE RATE WORKSHEET - E

/R24

Page 8 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS

8.0 INSTRUCTIONS

(continued) 8.4 Calculate the offsite dose rates and projected doses by following the instructions on the DOSE CALCULATIONWORKSHEET selected during step 8.2.

8.5 The Emergency Coordinator shall be informed immediately of the results of TOTAL RELEASE RATE, DOSE RATES and PROJECTED DOSE.

8.6 The Emergency Coo'rdinator or his designee shall monitor release rates and meteorological conditions to determine how frequently to update the dose rate estimates.

1. Release and Dose estimates shall be revised at least hourly for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the accident unless it is determined that releases of radioactivity have been terminated.

2. Dose rate estimates shall be updated if any of the following averages change by the amounts indicated below, over a period not to exceed 30 minutes:

A) Release rates increase by more than 25%.

OR B) Wind speed decreases to less than one half of previous value.

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

OR D) Wind direction changes by. more than 22.5 deg. (i.e., plume centerline is more than one sector away from prior location).

/R24

Page 9 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS MET WORKSHEET A SITE TOWER (Page 1 of 2)

1. Gather Data A)

B) 0 kTiit t I g'i I b Enter 10 Meter (alternate 60 Meter) WIND SPEED: mph C) Enter 10 Meter (alternate 60 Meter) WIND DIRECTION (from) deg.

D) Enter Delta-T (60 Meter minus 10 Meter temperatures) deg. F

2. Using Delta-T (bT) and the guide below, determine and enter the Stability Class Stability Stability Stability Class Class Class AT < -1.7 A -1.4 < b,T <-0.5 D +1.4 < bT < +3.6 F

-1.7 < bT < -1.5 B -0.5 < AT < +1.4 E +36 < bT G

-1.5 < AT < -1.4 C

3. Using the guide below, determine and circle the AFFECTED SECTORS.

NOTE If the wind direction is directly on the edge of two sectors (e.g. 11, 33', 56',

etc.), an additional sector should be added to the Protective Action Recommendation (PAR). For example, if the wind direction is from 78', then the affected sectors for the PAR should be L, M, N and P.

Wind Affected Wind Affected Wind Affected From Sectors From Sectors From Sectors 348 - 11 HJK 123 - 146 PQR 236 - 258 CDE 11 - 33 JKL 146 - 168 QRA 258 - 281 DEF 33- 56 Kl M 168 - 191 RAB 281 - 303 EFG 56- 78 LMN 191 - 213 . ABC 303 - 326 FGH 78 - 101 MNP 213 - 236 BCD 326 - 348 GHJ 101 - 123 NPQ there is no 0 sector there is no I sector

I J Page 10 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS MET WORKSHEET A SITE TOWER (Page 2 of 2)

4. Check for Sea Breeze effect:

Only if All of the following conditions are met, then the Sea Breeze effect is YES If one or more conditions are not met, then the Sea Breeze effect is NO i) Stability Class A, B or C ii) Time of day 6 AM to 7PM iii) Wind Direction (from) is between 0 through EAST to 180 degrees iv) 10 meter air temperature greater than HISTORICAL AVERAGE SURFACE WATER, listed below:

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 69 65 69 73 76 79 80 81 81 79 74 71 Sea Breeze Impact (Yes or No)

5. Using the guide below, select a DOSE CALCULATIONWORKSHEET:

Stab. Seabreeze Dose Gale Stab. Seabreeze Dose Gale Stab. Dose Gale Class ~tm act Worksheet Class ~tm act Worksheet Class Worksheet A YES 1 D 7 A NO 2 C YES E 8 B YES 3 C NO F 9 B NO 4 G 10

6. Copy information to the selected DOSE CALCULATIONWORKSHEET A) WIND DIRECTION and the AFFECTED SECTORS to line A B) WIND SPEED to line 2

7. This worksheet is completed, proceed to release rate determination.

Page 11 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS MET WORKSHEET 8 WEST PALM BEACH AIRPORT (Page 1 of 5)

Gather Data: Call West Palm Beach Airport NOAA/National Weather Service (NWS) station (phone number in EPIP 3100023E Appendix F, Other Agencies).

When the NOAA person answers, identify FPL - St. Lucie Plant. as calling party and obtain:

A) Date/Time of observation: Eastern Standard Time, /R24 Daylight Savings Time (circle eastern or daylight)

B) WIND DIRECTION (From): Degrees C) WIND SPEED: Knots D) Sunrise: am Sunset: pm E) Sky Condition: Clear Scattered Overcast Broken (circle)

F) If sky condition is overcast or broken, then enter Ceiling Height G) Estimated air temperature for Ft. Pierce area 'F /R24 H) If time permits, ask for a weather forecast for the area:

2. Determine and circle the Solar Radiation Characteristics (nil, weak, slight, etc.):

A) IF Daytime (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after sunrise to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> before sunset), THEN, use the table below Solar Altitude, see Figure on page 5 of this worksheet /R24 Day Sky Ceiling, 15 to < 35 deg 35 to 60 deg > 60 deg

< 15 deg

< 7000 Nil Nil Nil Nil 7K to 16K Weak Weak Weak Slight Overcast

> 16000 Weak Weak Slight Moderate

< 7000 Weak Weak Weak Slight 7K to 16K Weak Weak Slight Moderate Broken

> 16000 Weak Slight Moderate Strong Clear not applicable Weak Slight Moderate Strong Scattered

Page 12 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS MET WORKSHEET B WEST PALM BEACH AIRPORT (Page 2 of 5)

B) IF NOT Daytime, use the table below Night Sky Condition Ceiling, Ft. Solar Altitude is not applicable less than 7000 Nil

=Overcast 7000 or higher Weak Loss Broken not applicable Weak Loss Clear or scattered not applicable Strong Loss

3. Using the Wind Speed in Knots and the Solar Radiation Characteristics, find in the table below and circle the Stability Class Wind Speed in KNOTS Solar 0-1 > 1-3 > 3-5 > 5-6 > 6-7 > 7-9 > 9-10 > 10-11 Radiation Strong A A A B B C Moderate A B B B B C C D Slight B C C C C C D Weak C C D D D D D Nil D D D D D D D D Weak Loss F E E D D D D D Strong Loss G G F F E D D

Page 13 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS MET WORKSHEET B WEST PALM BEACH AIRPORT (Page 3 of 5)

4. Using the guide below, determine and circle the AFFECTED SECTORS NOTE If the wind direction is directly on the edge of two sectors (e.g. 11', 33', 56',

etc.), an additional sector should be added to the Protective Action Recommendation (PAR). For example, if the wind direction is from 78', then the affected sectors for the PAR should be L, M, N and P.

Wind Affected Wind Affected Wind Affected From Sectors From Sectors From Sectors 348 - 11 HJK 123 - 146 PQR 236 - 258 CDE 11 - 33 JKL 146 - 168 QRA 258 - 281 DEF 33- 56 KLM 168 - 191 RAB 281 - 303 EFG 56-78 LMN 191 - 213 ABC 303 - 326 FGH 78 - 101 MNP 213 - 236 BCD 326 - 348 GHJ 101 - 123 NPQ there is no 0 sector there is no I sector

5. Check for Sea Breeze effect:

Only if ALL of the following conditions are met, then the Sea Breeze effect is YES If one or more conditions are not met, then the Sea Breeze effect is NO i) Stability Class A, B or C ii) Time of day 6 AM to 7 PM iii) Wind Direction (from) is between 0 through East to 180 degrees iv) 10 meter air temperature greater than HISTORICAL AVERAGE SURFACE WATER, listed below:

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 69 65 69 73 76 79 80 81 81 79 74 71 Sea Breeze Impact (Yes or No)

Page 14 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS MET WORKSHEET B WEST PALM BEACH AIRPORT (Page 4 of 5)

6. Using the guide below, select a DOSE CALCULATIONS WORKSHEET:

Stab. Seabreeze Dose Gale Stab. Seabreeze Dose Gale Stab. Dose Calc Class ~tm act Worksheet Class ~tm act Worksheet Class Worksheet A YES 1 D 7 A NO 2 C YES"" E 8 B YES 3 C NO 'F 9 B NO 4 G 10

7. Copy information to the selected DOSE CALCULATIONWORKSHEET:

A) from line 1B, the WIND DIRECTION to line A of Dose Calculation Worksheet.

B) from line 1C, multiply the wind speed in knots by 1.15 to obtain the WIND SPEED mph, copy to line 2 of Dose Calculation Worksheet.

C) from line 4, the AFFECTED SECTORS to line A of Dose Calculation Worksheet.

8. Use of this method is complete, proceed to release rate determination.

8

'(

Page 15 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFFeSITE DOSE CALCULATIONS MET WORKSHEET B WEST PALM BEACH AIRPORT (Page 5 of 5)

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Page 16 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS MET WORKSHEET C DEFAULT NOTE This method is to be used only if Site Met Tower and National Weather Service (West Palm Beach Airport) data are not available.

1. IF Daytime Hours (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after sunrise to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> before sunset)

THEN select DOSE CALCULATIONWORKSHEET 7 and enter AFFECTED SECTORS = ALL in line A check Default method in line A WIND SPEED = 5 mph in line 2

2. IF Not Daytime THEN select DOSE CALCULATIONWORKSHEET 9 and enter AFFECTED SECTORS = ALL in line A check Default method in line A WIND SPEED = 3 mph in line 2

3. Use of this method is completed, proceed to release rate determination.

F Page 17 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET A1 UNIT 1 CHEMISTRY GRAB SAMPLING (Page 1 of 2)

1. Date and time of data:

2. Ask Emergency Coordinator: A) Accident Type B) Is core overheating or melting (yes/no)

If the core IS overheating or melting PF = 4.4, If not, PF = 1.0; Enter PF =

C) Potential DURATION of release (if unknown, use 2): hours

3. Enter sample assay data of gross Noble gas and DEQ Iodine-131 p,CI/cc concentration in the step 5 table below under pCi/cc.

4. Choose the applicable pathway(s). Check the ON fans and line thru the SCFM of the fans NOT running. Add up the flows and enter total pathway SCFM in the SCFM column in step 5.

PLANT VENT FUEL BUILDING Fan Yon SCFM Fan /on SCFM 1-HVE-6A Shield Bldg 6000 1-HVE-15 New Fuel 8450 1-HVE-6B 6000 1-HVE-16A Fuel Pool 10350 1-HVE-7A 954 1-HVE-16B 10350 1-HVE-7B 954 1-HVE-17 H&V Room 6144 1-HVE-8A RCB Exhaust 42000 (Add) Fuel Bldg. Total =

1-HVE-8B 42000 1-HVE-10A RAB Exhaust 74050 ECCS AREA 1-HVE-10B 74050 Fan SCFM (Add) Plant Vent Total = 1-HVE-9A 30000 1-HVE-9B 30000

/R24

Page 18 of 5]

ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET A1 UNIT 1 CHEMISTRY GRAB SAMPLING (Page 2 of 2)

5. Calculate Release Rates: IjCI/cc x SCFM x factor = Ci/sec Pathway pci/CC SCFM factor Noble Gas, Cilsec iodine, Ci/sec Plant Vent Noble Gas 4.72 E -4 iodine Fuel Bldg. Noble Gas 4.72 E -4 iodine ECCS - A Noble Gas 30,000 4.72 E -4 iodine ECCS - B Noble Gas 30,000 4.72 E -4 iodine /R24

6. Calculate the Site Release Rate, Ci/sec Noble Gas, iodine, Ci/sec Ci/sec A) Total the unit 1 release rates determined above B) IF Unit 2 is AFFECTED, enter its release rates C) Add A and B to obtain the SITE RELEASE RATES

7. Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET A) On line B, check Grab Sample under Unit 1 B) Enter the NOBLE GAS RELEASE RATE into line 8 C) Enter the IODINE RELEASE RATE into line 1 D) Enter the DURATION (if 2 affected units, use longest) into line 6 E) Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11

8. This worksheet is done, follow the instructions on the DOSE CALCULATION WORKSHEET

• '. I

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Page 19 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET A2 UNIT 2 CHEMISTRY GRAB SAMPLING (Page 1 of 2)

1. Date and time of data:

2. Ask Emergency Coordinator: A) Accident Type

8) Is core overheating or melting (yesino)

If the core IS overheating or melting PF = 4.4, If not, PF = 1.0; Enter PF =

C) Potential DURATION of release (if unknown, use 2):" hours

3. Enter sample assay data of gross Noble gas and DEQ Iodine-131 ljCiicc concentration in the step 5 table below under pCi/cc.

4. Choose the applicable pathway(s). Check the ON fans and line thru the SCFM of the fans NOT running. Add up the flows and enter total pathway SCFM in the SCFM column in step 5.

PLANT VENT FUEL BUILDlNG If NOT Diverted to Plant Vent, Use Stated Row Fan v'on SCFM Fan /on SCFM Fan SCFM 2-HVE-6A Shield Bldg 6000 2-HVE-15 New Fuel 15216 2-HVE-9A 30000 2-HVE-6B 6000 2-HVE-16A Fuel Pool 15677 2-HVE-9B 30000 2-HVE-7A H, Purge 2000 2-HVE-16B Fuel Pool 15677 2.HVE-7B 2000 2-HVE-17 Bldg H8,V 6000 2-HVE-8A RCB Exhaust 42000 (Add) Fuel Bldg. Total =

2-HVE-8B 42000 2.HVE-10A RAB Exhaust 84500 2-HVE-10B 84500 (Add) Plant Vent Total =

5. Calculate Release Rates: pCI/cc x SCFM x factor = Ci/sec Pathway TYPE pci/CC SCFM factor Noble Gas, Ci/sec iodine, Ci/sec Plant Vent Noble Gas 4.72 E -4 iodine Fuel Bldg. Noble Gas 4.72 E -4 iodine ECCS - A Noble Gas 30,000 4.72 E;4 iodine ECCS - B Noble Gas 30,000 4.72 E -4 iodine

/R24

Page 20 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET A2 UNIT 2 CHEMISTRY GRAB SAMPLING (Page 2 of 2)

6. Calculate the Site Release Rate, Ci/sec Noble Gas, iodine, Ci/sec Ci/sec A) Total the unit 2 release rates determined above B) IF Unit 1 is AFFECTED, enter its release rates C) Add A and B to obtain the SITE RELEASE RATES

7. Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKS HEET A) On line B, check Grab Sample under Unit 2 B) Enter the NOBLE GAS RELEASE RATE into line 8 C) Enter the IODINE RELEASE RATE into line 1 D) Enter the DURATION (if 2 affected units, use longest) into line 6 E) Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11

8. This worksheet is done, follow the instructions on the DOSE CALCULATION WORKSHEET

Page 21 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET B1 UNIT 1 EFFLUENT MONITORS (Page 1 of 3)

1. Date and time of data:

2. Ask Emergency Coordinator: A) Accident Type B) Is core overheating or melting (yes/no)

If the core IS overheating or melting PF = 4.4, If not, PF = 1.0; Enter PF =

C) Potential DURATION of release (if unknown, use 2); hours

3. Determine gross Noble gas concentrations via Eberline Control Terminal A or B:

A. Enter the following sequence on the keypad for each applicable channel number:

1. Press 10 MIN HIST

2. Enter the applicable pathway channel number (see below)

3. Press ENTER (value appears in window)

4. Press PRINT

5. Press FILE

6. Press ENTER

7. Enter the next to last point from the lowest non-alarming range into the Data column in step 6.

Page 22 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET B1 UNIT 1 EFFLUENT MONITORS (Page 2 of 3)

A licable Pathwa Channel Number NOTE Use a steamline channel ONLY if the Safeties and/or Atmospheric Steam Dumps are releasing steam. Monitors have one range.

Range Path Low Mid Hi Plant Vent . 1-5 1-7 1-9 ECCS-A....,. ~ 2-5 2-7 2-9 ECCS-B .. ~... ~ 3-5 3-7 3-9 Fuel Bldg. . 4-5 4-7 4-9 Steamline A .... . N/A 5-1 N/A Steamline 8 .... . N/A 5-2 N/A Choose the applicable pathway(s) Check the ON fans and line thru the SCFM of

~

the fans not running. Add up the flows and enter total pathway SCFM in the SCFM column in step 6.

PLANT VENT FUEL BUILDING ECCS AREA Fan /on SCFM Fan Yon SCFM Fan SCFM 1-HVF-6A Shield Bldg 6000 1HVE-15 New Fuel 8450 1-HVE-9A 30000 1-HVE-6B 6000 1-HVE-16A Fuel Pool 10350 1-HVE.9B 30000 1-HVE-7A H, Purge 954 1-HVE-16B 10350 1-HVE-7B 954 1-HVE.17 HRV Room 6144 1-HVE-8A RCB Exhaust 42000 (Add) Fuel Bldg. Total =

1-HVE.8B 42000 1-HVE RAB Exhaust 74050 1-HVE 74050 (Add) Plant Vent Total =

5. Select Pathways IODINE FACTOR (IF) for the accident type below and enter under IF Column in step 6.

Plant Vent 0.01 1. ER 1.0 4. E-5 0 0 ECCS 0.01 0 0 0 0 0 Fuel Bldg. 0 0 0 0 0.04 1.3 Steamline 0 1. EQ 0 0 0 0

/R24

Page 23 of 51 ST. LUCIE PLANT

,'i E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE NORKSHEET B1 UNIT 1 EFFLUENT MONITORS (Page 3 of 3)

6. Calculate Release Rates:

DATA x SCFM x factor = N.G. Ci/sec x IF = Iodine Ci/sec Pathway DATA SCFM factor Noble Gas, Ci/sec IF iodine Ci/sec Plant Vent uci/cc 4.72 E-4 ECCS.A "uci/cc 30,000 4.72 E-4 ECCS.B uCi/cc 30,000 4.72 E-4 Fuel Bldg. uci/cc 4.72 E.4 Steamline A mr/hr 1.0 1.24 E-2 Steamline B mr/hr 1.0 1.24 E-2

7. Calculate the Site Release Rate, Ci/sec Noble Gas, Ci/sec Iodine, Ci/sec A) Enter the Unit 1 release rates determined from this worksheet B) IF Unit 2 is AFFECTED, enter its release rates C) Add A and B to obtain the SITE RELEASE RATES

8. Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET A) On line B, check Effluent Monitor under Unit 1 B) Enter the NOBLE GAS RELEASE RATE into line 8 C) Enter the IODINE RELEASE RATE into line 1 D) Enter the DURATION (if 2 affected units, use longest) into line 6 E) Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 1$ .

9. This worksheet is done, follow the instructions on the DOSE CALCULATION WORKSHEET

Page 24 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET B2 UNIT 2 EFFLUENT MONITORS (Page 1 of 3) 0t ~ ti fdt'.

2. Ask Emergency Coordinator: A) Accident Type B) Is core overheating or melting (yes/no)

If the core IS overheating or melting PF = 4.4, If not, PF = 1.0; Enter PF =

C) Potential DURATION of release (if unknown, use 2): hours

3. Determine gross Noble gas concentrations via the PC-11, Radiation Monitoring Console. Use the following keystroke sequence for each applicable channel number: /R24 A. Press Key F8 to display Control Menu B. Use the ARROW Key to highlight the RM-80 Utility Task under the status display C. Press ENTER key D. Press Key F1 to select Historical Display E. Press Key F4 to select Graph 10 Minute NOTE Start with lowest scale not in alarm.

/R24 F. At prompt, type M then the Channel Number (see below) /R24 G. Press ENTER, Record Top ¹1 reading as DATA in step 6 H. Press Keys F10, F10, then F1 to display All Monitor Schematic /R24

/R24

Page 25 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET B2 UNIT 2 EFFLUENT MONITORS (Page 2 of 3)

A licable Pathwa Channel Number NOTE Use a steamline channel only if the Safeties and/or Atmospheric Steam Dumps are releasing steam. Monitors have one range. Use NET value (Channel - Background).

Range Path Low Mid Hi Plant Vent .... ~.... ~......... .. 621 622 623 A.....,........,........

~

ECCS - 601 602 603 ECCS - B....... ~ . ~ ~ . ~.......... 611 612 613 Fuel Bldg. (If NOT diverted).....,.... 413 N/A N/A Steamline A ........... ~....... N/A 631 N/A

.... ~........... ~... N/A

~

Steamline B 632 N/A Background (Steamline) .... ~...... N/A ~ 633 N/A

4. Choose the applicable pathway(s). Check the ON fans and line thru the SCFM of the fans NOT running. Add up the flows and enter total pathway SCFM in the SCFM column in step 6.

PLANT VENT FUEL BUILDING ECCS AREA IF NOT DIVERTED Fan Yon SCFM Fan eron SCFM SCFM 2.HVE-6A Shield Bldg 6000 2HVE-15 New Fuel 15216 2-HVE-9A 30000 2-HVE-6B 6000 2-HVE-16A Fuel Pool 15677 2.HVE-9B 30000 2-HVE-7A H, Purge 2000 2-HVE-16B 15677 2.HVE-7B 2000 2-HVE-17 HSV Room 6000 2-HVE-8A RCB Exhaust 42000 (Add) Fuel Bldg. Total =

2-HVE-8B 42000 2-HVE-10A RAB Exhaust 84500 2-HVE-10B 84500 (Add) Plant Vent Total =

/R24

Page 26 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET B2 UNIT 2 EFFLUENT MONITORS (Page 3 of 3)

5. Select Pathways IODINE FACTOR (IF) for the accident type below and enter under IF Column in step 6.

PATHWAY LOCA SGTR MSLB WASTE GAS TR FUEL HANDLING CASK DROP Plant Vent 0.01 1. EW 1.0 4. E-5 0.04 1.3 ECCS 0.01 0 0 0 Fuel Bldg. 0 0 0 0.04 1.3 0

/R24 Steamline 0 1. E-3 0 0

6. Calculate Release Rates:

DATA x SCFM x factor = N.G. Ci/sec x IF = Iodine Ci/sec Pathway DATA SCFM factor Noble Gas, Ci/sec IF Iodine Ci/sec Plant Vent uci/cc 4.72 E-4 ECCS-A vci/cc 30,000 4.72 E-4 ECCS.B uci/cc 30,000 4.72 E-4 Fuel Bldg. uci/cc 4.72 E-4 Steamline A mr/hr 1.0 1.24 E-2 Steamline B mr/hr 1.0 1.24 E-2

7. Calculate the Site Release Rate, Ci/sec Noble Gas. Ci/sec Iodine, CVsec A) Enter the Unit 2 release rates determined from this worksheet B) IF Unit 1 is AFF ECTED, enter its release rates C) Add A and B to obtain the SITE RELEASE RATES

8. Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET A) On line B, check Effluent Monitor under Unit 2.

B) Enter the NOBLE GAS RELEASE RATE into line 8 C) Enter the IODINE RELEASE RATE into line 1 D) Enter the DURATION (if 2 affected units, use longest) into line 6 E) Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11 ~

9. This worksheet is done, follow the instructions on the DOSE CALCULATION WORKSHEET

Page 27 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET C CONTAINMENT Hl-RANGE RADIATION MONITORS (APPLICABLE TO UNIT 1 AND UNIT 2)

(Page 1 of 2)

(If both units are using this method, then complete one worksheet for each unit)

Ot dt's tdt.:~

2. Ask Emergency Coordinator: A) Accident Type B) Is core overheating or melting (yes/no)

If the core IS overheating or melting PF = 4.4, If not, PF = 1.0; Enter PF =

C) Potential DURATION of release (if unknown, use 2): hours Obtain: Highest CHRRM reading: R/hr, Hours since Reactor Trip: hours; then copy the CHRRM R/hr to step 6 and 8.

Find in the table below and enter into step 6 and 8, the core fraction factor (CF)

Hours since Reactor trip CF Hours since Reactor Trip CF 5.00 E-7 > 2.0 to < 4.0 6.25 E - 6

> 0 to 5 0.5 1.00 E -6 > 4.0 to 6 8.0 1.25 E -5

> 0.5 to < 1.0 1.67 E - 6 > 8.0 2.22 E -5

> 1.0 to 5 2.0 3.33 E-6

5. Find in the table below and enter into step 6 the noble gas reduction factor (NGRF)

Hours since Hours Since Hours Since Hours Since Rx Tnp NGRF R x Tnp GRF Rx Tnp NGRF Rx Tnp NGRF 1.0 >4to<5 >9to510 0.26 > 14 to 6 15 0.16

>Otod 1 0.90 >5toS6 0.39 >10to51T 0.23 > 15 to 6 16 0.16

>1 to 53 0.70 >6to<7 0.35 >> 11 to 5 12 0.21 > 16to<17 0.14

> 2to53 0.60 >7to58 0.32 > 12 to 5 13 0.19 >17to<18 0.14

>3 to<4 0.50 >8to<9 0.28 >13to<14 0.18 ) 18 0.13

6. Calculate: R/hr x (CF) x (NGRF) x 40 = N.G. Ci/sec the NOBLE GAS RELEASE RATE, N.G. Ci/sec

7. If the Iodine Removal System IS in use then ICV = 0.6, if NOT in use then ICV =

1.6. Copy the selected ICV into step 8.

~ ~ /R24

)

f

Page 28 of 51 ST, LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET C CONTAINMENT HI-RANGE RADIATION MONITORS (APPLICABLE TO UNIT 1 AND UNIT 2)

(Page 2 of 2)

8. Calculate: R/hr x (CF) x (ICV) = - lod. Ci/sec the IODINE RELEASE RATE, lod. Ci/sec.

9. Calculate the Site Release Rate, Ci/sec Noble Gas Iodine A) Enter the release rates determined from this worksheet B) IF the other Unit is AFFECTED, enter its release rates C) Add A and B to obtain the SITE RELEASE RATES

10. Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET A) On line B, check CHRRM under the Unit(s) using the CHRRM method.

B) Enter the NOBLE GAS RELEASE RATE into line 8 C) Enter the IODINE RELEASE RATE into line 1 D) 'Enter the DURATION (if 2 affected units, use longest) into line 6 E) Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11 11 ~ This worksheet is done, follow the instructions on the DOSE CALCULATION WORKS HEET

1 1 r

Page 29 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET D POST LOCA MONITORS (APPLICABLE TO UNIT 1 OR UNIT 2)

(Page 1 of 2)

(If both units are using this method, then complete one worksheet for each unit)

1. Date and time of data: /

2. Ask Emergency Coordinator: A) Accident Type B) Is.'"core overheating or melting (yes/no)

If the core IS overheating or melting PF = 4.4, If not, PF = 1.0; Enter PF =

C) Potential DURATION of release (if unknown, use 2): hours

3. For the Reactor Unit(sj, using this method, obtain the Hicihest POST LOCA reading mR/hr

4. For the applicable Unit(s), find the release rates in the table below and enter them in step 5A.

Iodine Release Rate, (Ci/sec)

Post Loca with Iodine Removal System Noble Gas Monitor Reading Release Rate (mR/hr) In Use Not in Use (Ci/sec)

< 60 Negligible Negligible Negligible

>60, <100 2.0 0.03 0.1

> 100, < 1000 10.0 0.14 0.4

> 1000 40.0 0.60 1.6

5. Calculate the Site Release Rate, Ci/sec Noble Gas Iodine A) If used, enter the AFFECTED Unit's release rates determined from this worksheet B) IF the other Unit is AFFECTED enter its release rates C) Add A and B to obtain the SITE RELEASE RATES

Page 30 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET D POST LOCA MONITORS (APPLICABLE TO UNIT 1 OR UNIT 2)

.(Page 2 of 2)

6. Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET A) On line B, check Post LOCA under the Unit(s) using the Post LOCA method B) Enter the NOBLE GAS RELEASE RATE into line 8 C) Enter the IODINE RELEASE RATE into line 1 D) Enter the DURATION (if 2 affected units, use longest) into line 6 E) Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11

7. This worksheet is done, follow the instructions on the DOSE CALCULATION WORKSHEET

Page 31 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS RELEASE RATE WORKSHEET E DEFAULT (APPLICABLE TO UNIT 1 OR UNIT 2)

(Page 1 of 2)

CAUTION Use this method only if there is no data to use in other methods 2.

Ot dt's tdt::~

Ask Emergency Coordinator: A) Accident Type

8) ls core overheating or melting (yes/no)

If the core IS overheating or melting PF = 4.4, If not, PF = 1.0; Enter PF =

C) Potential DURATION of release (if unknown, use Default Duration from the table below):

hours

3. For the affected Unit(s) and the accident type, select and circle the Noble Gas and Iodine Release Rates in the table below.

Release Rates, Ci/sec Default Accident Type Duration, Noble Gas Iodine LOCA WITHOUT 2 37 1.6 ~

Iodine Removal System in use hours LOCA WITH 2 37 0.6 Iodine Removal System in use hours Steam Generator Tube Rupture 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2.0 4.0 E -5 Main Steam Line Break 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.04 0.01 Fuel Handling 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 4.0 E - 3 Cask Drop 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2.0 0.03 Waste Gas Decay Tank Rupture 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2.0 2.0 E - 6 Noble Gas Iodine

4. Calculate the Site Release Rate, Ci/sec A) Enter the release rates determined from this worksheet B) IF the other Unit is AFFECTED enter its release rates C) Add A and B to obtain the SITE RELEASE RATES

Page 32 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS i RELEASE RATE WORKSHEET E DEFAULT (APPLICABLE TO UNIT 1 OR UNIT 2)

(Page 2 of 2)

5. Enter the SITE RELEASE RATES in the selected DOSE CALCULATION WORKSHEET A) On line B, check Default under the Unit(s) using the default method B) Enter the NOBLE GAS RELEASE RATE into line 8 C) Enter the IODINE RELEASE RATE into line 1 D) Enter the DURATION (if 2 affected units, use longest) into line 6 E) Enter the PF (Particulate Factor) (if 2 affected units, use largest) into line 11

6. This worksheet is done, follow the instructions on the DOSE CALCULATION WORKSHEET

Page 33 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 1 Stability Class = A Seabreeze Impact = YES A. Met Summary: WIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Airport Default Release Rate Method: Unit 1 Unit 2 Grab Sample

~

ENuent Monitor CHRRM POST LOCA Detault Appendix A Date and time oi data trom release rate determination:

Follow the instructions to calculate doses O line instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles 1 Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF 3 Divide line 1 by line 2 4 iodine Dose Factors, 2.3 E+4 8.1 E+3 2.3 E+3 8.0 E+ 2 Mu!tiply line 3 by line 4 to obtain SNF THYROID DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF Multiply line 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 mile 2 miles 5 mites 10 miles 8 Enter NOBLE GAS RELEASE RATE, Ci/sec 9 Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 5.0 2.6 0.73 0.26 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain PAR TOTAL DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator (RM if done in EOF)

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose Calculations completed; continue monitoring releases and assessing doses.

Page 34 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 2 Stability Class = A Seabreeze Impact = NO A. Met Summary: WIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Airport Default B. Release Rate Method: Unit 1 Unit 2 Grab Sample

~

Effluent Monitor CHRRM POST LOCA Default Appendix A Date and time oi data from release rate determination:

Follow the instructions to calculate doses line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF 3 Divide line 1 by line 2 4 Iodine Dose Factors, 3.8 E+ 3 1.8 E+ 3 7.9 E+ 2 4.0 E+ 2 Multiply line 3 by line 4 to obtain SNF THYROID DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF Multiply line 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8 Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9 Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 0.82 0.57 0.25 0.13 14 Multiply line 12 by line 13 15 Enter (Une 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain PAR TOTAL DOSE (TEDE). mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator (RM if done in EOF)

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring releases and assessing doses.

Page 35 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 3 Stability Class = B Seabreeze Impact = YES A. Met Summary: WIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Airport Default B. Release Rate Method: Unit 1 Unit 2 Grab Sample

~

ENuent Monitor CHRRM POST LOCA Default Appendix A Date and time oi data from release rate determination:

Follow the instructions to calculate doses O line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles 1 Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF 3 Divide line 1 by line 2 4 Iodine Dose Factors, 3.0E+4 1.1 E+4 3.0 E+3 1.1 E+ 3 Multiply line 3 by line 4 to obtain SNF THYROID DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF Multiplyline 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8 Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9 Enter WIND SPEED from line 2, above 10 Divide line 8 by tine 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 9.6 3.4 0.97 0.36 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain PAR TOTAL DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator (RM if done in EOF)

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring releases and assessing doses.

a a ~

Page 36 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 4 Stability Class = 8 Seabreeze Impact = NO A. Met Summary: WIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Airport Default Release Rate Method: Unit 1 Unit 2 Grab Sample

~

Effluent Monitor CHRRM POST LOCA Default Appendix A Date and time oi data from release rate determination:

Follow the instructions to calculate doses O line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF 3 Divide line 1 by line 2 4 Iodine Dose Factors, 2.3 E + 4 6.0 E + 3 1.1 E + 3 5.7 F + 2 Multiply line 3 by line 4 to obtain SNF THYROID DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF Multiply line 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8 Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9 Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 7.4 1.9 0.36 0.18 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TED E), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain PAR TOTAL DOSE (TEDE), rnrem 19 FonNard this worksheet (or a copy) to the Emergency Coordinator (RM if done in EOF}

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring releases and assessing doses.

k ~

Page 37 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 5 Stability Class = C Seabreeze Impact = YES A. Met Summary: WIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Airport Default B. Release Rate Method: Unit 1 Unit 2 Grab Sample

~

Effluent Monitor CHRRM POST LOCA Default Appendix A Date and time of data from release rate determination:

Follow the instructions to calculate doses e line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF Divide line 1 by line 2 Iodine Dose Factors, 6.0 E + 4 1.7 E + 4 3.9 E + 3 1.5 E + 3 Multiply line 3 by line 4 to obtain SNF THYROID DOSE RATE (CDE), mrem/hr Enter DURATION of release, hours SNF Multiply line 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8 Enter NOSLE GAS RELEASE RATE, Ci/sec SNF Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 19.0 5.3 1.2 0.48 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain PAR TOTAL DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator (RM if done in EOF)

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring releases and assessing doses.

l I

Page 38 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 6 Stability Class = C Seabreeze Impact = NO A. Met Summary: NIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Airport Deieutt B. Release Rate Method: Unit 1 Unit 2 Grab Sample Effluent Monitor CHRRM POST LOCA Default Appendix A Date and time of data from release rate determination:

Follow the instructions to calculate doses O line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles SNF Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph 3 Divide line 1 by line 2 4 Iodine Dose Factors, 6.0 E + 4 1.7 E + 4 3.3 E + 3 9.5 E + 2 SNF Multiply line 3 by line 4 to obtain THYROID DOSE RATE (CDE), rnrem/hr Enter DURATION of release, hours SNF 6

PAR Multiply line 5 by line 6 to obtain PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles Enter NOBLE GAS RELEASE RATE, Ci/sec' SNF 8

Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 19.0 5.3 1.0 0.30 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain PAR TOTAL DOSE (TEDE). mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator {RM if done in EOF)

C. Compare dose calculations to Emergency-Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring releases and assessing doses.

I ~

Page 39 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 7 Stability Class = D Seabreeze Impact = N/A A. Met Summap; WIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Atrport Default B. Release Rate Method: Unit 1 Unit 2 Grab Sample Effluent Monitor CHRRM POST LOCA Default Appendix A Date and time of data from release rate determination:

Follow the instructions to calculate doses O line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles 1 Enter the IODINE RELEASE RATE, Ci/sec SNF SNF 2 Enter the WIND SPEED, mph 3 Divide line 1 by line 2 4 Iodine Dose Factors, 1.7 E + 5 6.0 E + 4 1.7 E + 4 5.7 E + 3 SNF Multiply line 3 by line 4 to obtain THYROID DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF PAR Multiply line 5 by line 6 to obtain PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles SNF 8 Enter NOBLE GAS RELEASE RATE, Ci/sec 9 Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 53.0 19.0 5.3 1.8 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04)

SNF 16 Add line 14 and 15 to obtain TOTAL DOSE RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above PAR 18 Multiply line 16 by line 17 to obtain TOTAI. DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator (RM if done in EOF)

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring releases and assessing doses.

I g I'

Page 40 of 51

~

s e s ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 8 Stability Class = E Seabreeze Impact = N/A A. Met Summary: WIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Airport Default B. Release Rate Method: Unit 1 Unit 2 Grab Sample

~

Effluent Monitor CHRRM POST LOCA Default Appendix A Dale and time oi data from release rate determination:

Follow the instructions to calculate doses O line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles 1 Enter the IODINE RELEASE RATE, Ci/sec SNF 2 Enter the WIND SPEED, mph SNF 3 Divide line 1 by line 2 4 Iodine Doss Factors, 3.0 E+5 1.2 E+ 5 3.8 E+4 1.4 E+ 4 Multiply line 3 by line 4 to obtain SNF THYROID DOSE RATE (CDE), mrem/hr 6 Enter DURATION of release, hours SNF Multiply line 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles 8 Enter NOBLE GAS RELEASE RATE, Ci/sec SNF 9 Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 11 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 94.0 39.0 12.0 4.5 14 Multiply line 12 by line 13 15 Enter (Une 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain PAR TOTAL DOSE (TEDE), mrem 19 Fonvard this worksheet (or a copy) to the Emergency Coordinator {RM if done in EOF)

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring'releases and assessing doses.

I l ~ ~

III

Page 41 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 9 Stability Class = F Seabreeze Impact = N/A A.'et Summary: used: WIND DIRECTION (from)

Tower Airport AFFECTED SECTORS Default check method B. Release Rate Method: Unit 1 Unit 2 Grab Sample ENuent Monitor CHRRM POST LOCA Default Appendix A Date and time of data from release rate determination:

Follow the instructions to calculate doses line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles Enter the IODINE RELEASE RATE, Ci/sec SNF Enter the WIND SPEED, mph SNF Divide line 1 by line 2 Iodine Dose Factors, 5.3 E + 5 2.5 E + 5 7.9 E + 4 3.5 E + 4 Multiply line 3 by line 4 to obtain SNF THYROID DOSE RATE (CDE), mrem/hr Enter DURATION of release, hours SNF Multiply line 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles Enter NOBLE GAS RELEASE RATE, Ci/sec SNF Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 1.7 E + 2 7.8 E + 1 2.5 E + 1 1.1 E + 1 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TEDE), mrem/hr 17 Enter DURATION from line 6, above 18 Multiplyline 16 by line 17 to obtain PAR TOTAL DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator (RM if done in EOF)

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring releases and assessing doses.

~ ~ I Page 42 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS DOSE CALCULATIONWORKSHEET - 10 Stability Class = G Seabreeze Impact = N/A A. Met Summary: WIND DIRECTION (from) AFFECTED SECTORS check method used: Tower Airport Default Release Rate Method: Unit 1 Unit 2 Grab Sample

~

ENuent Monitor CHRRM POST LOCA Default Appendix A Date and time oi data from release rate determination:

Follow the instructions to calculate doses O line Instruction for THYROID DOSES (CDE) 1 Mile 2 Miles 5 Miles 10 Miles 1 Enter the IODINE RELEASE RATE, Ci/sec SNF Enter the WIND SPEED, mph SNF Divide line 1 by line 2 Iodine Dose Factors, 9.1 E+5 4.7 E+5 1.'8 E+5 7.9E+4 Multiply line 3 by line 4 to obtain SNF THYROID DOSE RATE (CDE), mrem/hr Enter DURATION of release, hours SNF Multiply line 5 by line 6 to obtain PAR PROJECTED THYROID DOSE (CDE), mrem line Instructions for TOTAL DOSES (TEDE) 1 Mile 2 Miles 5 Miles 10 Miles Enter NOBLE GAS RELEASE RATE, Ci/sec SNF Enter WIND SPEED from line 2, above 10 Divide line 8 by line 9 Enter the PARTICULATE FACTOR 12 Multiply line 10 by line 11 13 Dose Factors 2.9 E+ 2 1.5 E + 2 5.7 E + 1 2.5 E + 1 14 Multiply line 12 by line 13 15 Enter (Line 5 multiplied by 0.04) 16 Add line 14 and 15 to obtain SNF TOTAL DOSE RATE (TEDE), mrerrvhr 17 Enter DURATION from line 6, above 18 Multiply line 16 by line 17 to obtain PAR TOTAL DOSE (TEDE), mrem 19 Forward this worksheet (or a copy) to the Emergency Coordinator {RM if done in EOF)

C. Compare dose calculations to Emergency Action Levels (EALs) and PARs to ensure correct classification and PAR are selected. (Emergency Coordinator only)

D. Dose calculations completed; continue monitoring releases and assessing doses.

Page 43 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS APPENDIX A TSC/EOF DOSE ASSESSMENT GUIDANCE FOR RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 1 of 9)

1. Purpose This appendix provides methods for TSC and/or EOF Dose Assessment personnel to define release rates from a containment burp, evaluating field team measurements.-relative to estimated release rates and includes NRCs RTM-91 methods for estimating dose rates based on plant/reactor conditions.

2. Discussion

1. A containment burp is any suspected release from the containment that may be indicated by a rapid decrease of the containment pressure or rapid decrease in the Containment High Range Radiation Monitor that is determined, by operations or engineering, not due to changes in equipment operation (e.g., additional containment spray, additional containment coolers, etc.)

2. It must be remembered and understood that the methodology provided in this appendix includes conservative assumptions and is intended to provide the means to estimate an upper bound to the release, not an exact release rate.

3. Contents Section 1 - Provides guidance in estimating release rates during a LOCA resulting from rapid containment depressurizations; that is, an unmonitored burp release. The guidance is further sub-divided into three cases:

,Case 1 - Rapid decrease in CHRRM reading during burp Case 2 - No change in CHRRM reading during burp Case 3 - Increase in CHRRM reading during burp

/R24 Section 2 - Provides guidance in estimating doses based on plant/reactor conditions following the methodology in NRC RTM-91.

Page 44 of 51 g g ~ ~

ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS APPENDIX A TSC/EOF DOSE ASSESSMENT GUIDANCE FOR RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 2 of 9)

4. Basis Section 1:

Assumes CHRRM is responding only to Noble Gases Assumes Curies in (from core) <<Curies lost 2 E + 6 R/hr = 100% Core Inventory of Noble Gas (1 :

CF,.0. CF from 33E) 6.43 E + 8 Curies of Noble Gas is 100% Core Inventory (PSL2 UFSAR) 322 = 6 43 E + 8 Curies : 2 E + 6 R/hr

/R24

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Page 45 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS APPENDIX A TSC/EOF DOSE ASSESSMENT GUIDANCE FOR RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 3 of 9)

Section 1 (Page 1 of 4)

Case 1: Ra id Decrease in CHRRM Readin NOTE

1. A CHRRM drop of, about, 3% per hour may be due to'radiological decay.

2. The CHRRM may drop by as much as 10% very quickly if containment spray is actuated due to Iodine washout.

METHOD:

1. Date and time of data:

2. Calculate Delta-CHRRM:

Start CHRRM - End CHRRM Delta-CHRRM, R/hr

3. Calculate Duration:

a. Clock Time End - Clock Time Start Delta-Clock

/R24

b. Convert Delta-Clock to Delta-Seconds: 6 sec

4. Estimate Curies Lost:

Delta CHRRM x 322 Ci N.G. per R/hr = Noble Gas Curies Lost

5. Estimate Noble Gas Release Rate (loss rate):

Noble Gas Curies lost b, sec =. Noble Gas Ci/sec

6. Estimate the Iodine Release Rate:

N.G. Ci/sec x 0.01 (Iodine Factor) = Iodine Ci/sec

7. Utilize the current meteorological conditions and appropriate Dose Calculation V/orksheets (check Appendix A as method) or enter as Direct if using the computer, to estimate Offsite Doses.

~ I J ~

Page 46 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS APPENDIX A TSC/EOF DOSE ASSESSMENT GUIDANCE FOR RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 4 of 9)

Section 1 (Page 2 of 4)

Case 2: Constant CHRRM Readin NOTE Request Engineering to evaluate the % mass lost'in the burp METHOD:

Date and time of data:

2. Estimate Noble Gas Curies in the containment:

CHRRM R/hr x 322 Ci N.G. per R/hr = Noble Gas Curies in can 3.~ Calculate Duration:

a.~ Clock Time End - Clock Time Start Delta-Clock

/R24

b. Convert Delta-Clock to Delta-Seconds: 6 sec

4. Estimate Curies Lost:

N.G. Curies in can  % mass lost . 100 = Noble Gas Curies lost

5. Estimate Noble Gas Release Rate (loss rate):

Noble Gas Curies lost d sec = Noble Gas Ci/sec

6. Estimate the Iodine Release Rate:

N.G. Ci/sec x 0.01 (Iodine Factor) = Iodine Ci/sec

7. Utilize the current meteorological conditions and appropriate Dose Calculation Worksheets (check Appendix A as method) or enter as Direct if using the computer, to estimate Offsite Doses.

Page 47 of 51 1 ~

ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS APPENDIX A TSC/EOF DOSE ASSESSMENT GUIDANCE FOR RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 5 of 9)

Section 1 (Page 3 of 4)

Case 3: Increasin CHRRM Readin NOTE Request Engineering to evaluate the % mass lost'in the burp METHOD:

1. Date and time of data:

2. Calculate average CHRRM reading (Start CHRRM + End CHRRM ) ~ 2= Avg CHRRM, R/hr

3. Estimate Noble Gas Curies in the containment:

Avg. CHRRM R/hr x 322 Ci N.G. per R/hr = Noble Gas Curies in can

4. Calculate Duration:

a. Clock Time End - Clock Time Start Delta-Clock

/R24

b. Convert Delta-Clock to Delta-Seconds: b, sec

5. Estimate Curies Lost:

N.G. Curies in can  % mass lost = 100 = Noble Gas Curies lost

Page 48 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CAI CULATIONS APPENDIX A TSC/EOF DOSE ASSESSMENT GUIDANCE FOR RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 6 of 9)

Section 1 (Page 4 of 4)

Case 3: Increasin CHRRM Readin P

6. Estimate Noble Gas Release Rate (loss rate):

Noble Gas Curies lost hsec= Noble Gas Ci/sec

7. Estimate the Iodine Release Rate:

N.G. Ci/sec x 0.01 (Iodine Factor) = Iodine Ci/sec

8. Utilize the current meteorological conditions and appropriate Dose Calculation Worksheets (check Appendix A as method) or enter as Direct if using the computer, to estimate Offsite Doses.

Page 49 of 51

( i~ ~

ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS APPENDIX A TSC/EOF DOSE ASSESSMENT GUIDANCE FOR RESPONDING TO AN UNMONITORED CONTAINMENT BURP (Page 7 of 7)

Section 2 (Page 1 of 1)

Use this method IF there is not radiological data (e.g., CHRRM, containment grab sample, etc.) AND the accident has progressed past gap failure AND the containment has undergone catastrophic failure (e.g., know there should be pressure and there is none).

NOTE The following method provides DOSES, not release rates. Doses based on stability class D and four m.p.h. wind speed.

REACTOR ACCIDENT CONSEQUENCE OVERVIEW Containment Leaka e Core Condition Containment Status Early total Status '"'B Mitigating System No Mitigation Release 1000+

I Acute Dose (rem) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 mile'"

THY 1O" Failure (< 1 hr) Mitigated 250 104 MELT Release Late total failure 250 1O4 From Core (2- 12 hr) 45000 F Major L'eakage 10 10 (100% / day)

Design leakage 10 Early total No Mitigation 50 10'0 Failure (< 1 hr) Mitigated 10 Gap Release Late total failure From Core 10 (2-12 hr) 1500'F Major Leakage 10 (100% / day) 10'0 Design Leakage n/a 10 Notes: (A) Sprays, filters (B) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cloud immersion and inhalation plus 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of ground shine BASIS: NRC's Response Technical Manual RTM-91 Vol. 1, Rev. 1, pg C-2

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)

Page 50 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS APPENDIX B RELEASE RATE FROM FIELD TEAM MEASUREMENTS (Page 1 of 2)

NOTE Survey meter Gamma (closed window) results must be from plume centerline; that is, the maximum value from a lateral transverse of the plume.

1. DATE: , TIME: '-, Unit:

2. IF the survey meter measurement was at 1 mile value, THEN go to Step 4.

3. Estimate the 1 mile value:

Estimated 1 mile value = Survey meter results x (downwind distance, miles)~

Where the exponent Z = 2'or Stability Class A, B 1.5 for Stability Class C, D 1.0 for Stability Class E, F, G (Z) mr/hr x (miles) = Estimated 1 mile mr/hr meter results downwind distance

4. For the met conditions at time of sampling, select the Dose Calculation Worksheet (DCW).

a. Use Wind Speed in Miles Per Hour, mph

b. Copy from Line 13, the 1 mile Dose factor as the DF for use in Step 5.

5. Estimate Noble Gas Release Rate: Estimated 1 mile mr/hr - DF x Wind Speed mr/hr . (DF) x mph = .Noble Gas Ci/sec

6. Estimate Iodine Release Rate (IF = Iodine Factor, see the affected units'ffluent Monitor Worksheet):

N.G. Ci/sec x (IF) = Iodine (131 Deq) Ci/sec

Page 51 of 51 ST. LUCIE PLANT E-PLAN IMPLEMENTING PROCEDURE NO. 3100033E, REVISION 24 OFF-SITE DOSE CALCULATIONS APPENDIX 8 RELEASE RATE FROM FIELD TEAM MEASUREMENTS (Page 2 of 2)

7. Utilize the current meteorological conditions and appropriate Dose Calculation Worksheets (enter "B" next to Appendix as method), or enter release rates as Direct if using the computer, to estimate Offsite Doses from this appendix.

NOTE Dose rates at other distances (e.g., 1, 2, 5, 10 miles)-'can'be rapidly estimated using the following relationship as referenced, EPA-520 Rev. 6/79, page 5.10.

Estimated Dose Rate Dist x = Measured Dose rate times (DWD/Dist DWD = Measurement downwind distance, miles x)'here:

Dist x = other distance, miles z = exponent based on stability class

f.

I

Page 1 of 16 PSL FLORIDA POWER &. LIGHT COMPANY ST. LUCIE PLANT

'MERGENCY PLAN IMPLEMENTING PROCEDURE NO. 310 0 REVISION 14 8 1.0 TITLE:-

MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES, DRILLS, TESTS, AND EVALUATIONS 2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group 7/25 1975 Approved by K. N. Harris Plant General Manager 7/29 19 75 Revision 14 Reviewed by Facility Review Group 5/11 1995 Approved by C. L. Burton Plant General Manager 5/11 1995

3.0 SCOPE

3.1 Purpose This procedure provides instructions for maintenance of the Emergency Preparedness Program at the St. Lucie Plant.

3.2 Discussion Periodic exercises and drills will be conducted in order to test the state of emergency preparedness of participating personnel, organizations and agencies. Each exercise or drill will be conducted to:

1. Ensure that participants are familiar with their respective duties and responsibilities 2, Verify the adequacy of the Emergency Plan and Emergency Plan Implementing Procedures.

3. Test the communication network and systems S OPS

4. Check the availability of emergency supplies and DATE equipment DOCT PROCEDURE DOCN 3100050E

5. Verify the operability of emergency equipment sYs COMP COMPLETED ITM 14

Page 2 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS

3.0 SCOPE

(continued) 3.2 (continued)

-Drills may be scheduled such that two or more are conducted simultaneously with an exercise.

The results of the exercises will form the basis for corrective action to eliminate identified deficiencies, and will be discussed during a post-exercise evaluation.

Periodic tests and reviews of components of the Emergency Preparedness Program (e.g. facilities, equipment, Emergency Plan and Implementing Procedures, etc.) will be conducted to ensure availability, operability and reliability.

3.3 Authority The St. Lucie Plant Radiological Emergency Plan.

4.0 PRECAUTIONS

4.1 Every emergency alarm or announcement shall be assumed to be true unless an announcement is made to the contrary.

5.0 RESPONSIBILITIES

5.1 When an exercise is to be conducted, the Manager - Nuclear Emergency Preparedness will:

1. Schedule a date for the exercise in coordination with the Emergency Planning Coordinator and the primary State and County emergency response agencies.

2. Coordinate all FPL efforts with other participating personnel, organizations and agencies.

Page 3 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS

5.0 RESPONSIBILITIES

(continued) 5.1 (continued)

3. Obtain the approval of Plant Management.

4. Offer federal, state and local observers the opportunity to evaluate the exercise.

5. Discuss and evaluate the exercise with observers and principal participants.

6. Ensure that for all identified deficiencies, corrective measures are recommended.

7. Prepare and retain documentation for record keeping.

5.2 When'an exercise or a major drill is to be conducted, Plant Management will assure that the following is accomplished:

1. Assign personnel to prepare a scenario.

2. Assign personnel to assist in control and evaluation of the exercise.

3. Coordinate through the Manager - Nuclear Emergency Preparedness all activities which involve off-site personnel, organizations, or agencies.

4. Schedule a date for this activity in coordination with the Manager-Nuclear Emergency Preparedness and assign observers,

5. Review evaluations of exercise or drill with the observers and the Facility Review Group.

6. Ensure that deficiencies which are identified are addressed with corrective measures.

7. Prepare and submit documentation to the Manager - Nuclear Emergency Preparedness for record keeping.

Page 4 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS

6.0 REFERENCES

6.1 St..kucie Plant Radiological Emergency Plan (E-Plan) 6.2 NUREG 0654, Rev. 1, FEMA REP1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, November 1980.

7.0 RECORDS AND NOTIFICATIONS:

7.1 Written evaluation to FRG, Plant Management and Manager - Nuclear Emergency Preparedness by the Emergency Planning Coordinator.

7.2 Consolidated exercise summary by the Manager - Nuclear Emergency Preparedness.

7.3 Appendix A shall be maintained in the plant files in accordance with Ql 17-PR/PSL-1, "Quality Assurance Records."

Page 5 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS 8.0 INSTRUCTIONS; 8.1 The following emergency exercises, drills and tests will be conducted at the frequency indicated:

1. Exercises Inte rated Drills A major radiological emergency response exercise will be conducted at least once every calendar year to demonstrate the effectiveness of the Emergency Plan. This exercise shall be conducted as a Site Area Emergency or General Emergency. Any exercise that will provide for the coordination with and participation of off-site emergency response personnel, organizations and agencies including those of federal, state, and local governments should escalate to a General Emergency. The exercise scenario shall be varied from year to year such that all major elements of the Plan are tested at least every 6 years.

A. The major elements that should be tested every six years include the following:

1. Off hours staffing (6 P.M. - 4 A.M.)

2. Activation of Emergency News Center

3. Use of fire control teams

4. Use of medical support personnel

5. Use of one or more portions of backup communications for notification

6. Field monitoring

7. Capability for determining the magnitude and impact of the particular components of a release

8. Capability for post-accident coolant sampling and analysis

Page 6 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS

8.0 INSTRUCTIONS

(continued) 8.1 (continued)

1. (continued)

A. (continued)

9. Assembly and accountability

10. Initial recovery planning activities This emergency response exercise will be critiqued by Florida Power &

Light Company observers/evaluators and other evaluators, as appropriate, from federal, state and local agencies.

2. Radiolo ical Monitorin Drill A radiological monitoring drill will be conducted at least once every calendar year. These drills will include collection and analysis of sample media (i.e. air). This drill should include testing of communications and understanding of messages between the Radiation Team Leader (RTL) and the offsite monitoring teams.

3. Health Ph sics Drills The Health Physics Department will conduct Health Physics drills semi-annually and one of the semi-annual drills may be incorporated into, the radiological monitoring drill.

4. Medical Emer enc Drill A medical emergency drill involving a simulated contaminated individual, with provisions for activation of the plant First Aid and Personnel Decontamination Team and participation by local support services (i.e.,

ambulance and off-site medical treatment facility) will be conducted at least once every calendar year.

Page 7 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 M'AINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS

8.0 INSTRUCTIONS

(continued) 8.1 (continued)

5. Fire Emer enc Drill Fire drills are conducted in accordance with 10 CFR 50, Appendix R, III.I, 3. to test the operational readiness (personnel, equipment and procedures) to control and extinguish a fire on-site.

6. Communications Tests and Drills Communications with the State (Division of Emergency Management and Department of Health and Rehabilitative Services), and County (St. Lucie and Martin County Departments of Public Safety) governments within the plume exposure pathway Emergency Planning Zone (EPZ) will be tested monthly. Communications with the NRC via the Emergency Notification System (ENS) will be tested monthly. On an annual basis, communications to the State Emergency Operations Center (EOC) and the EOCs in St. Lucie and Martin Counties, will be tested. As part of the annual test, certain information will be exchanged. It will be determined whether or not the contents of the drill messages were understood.

Communication drills will be conducted with the FPL'ffsite Emergency Response Organization once per calendar quarter. This drill may be performed as part of the annual exercise or associated with an actual declared emergency.

At least one communication drill per year, involving information exchange to the off-site response agencies (state, counties, etc.), will be unannounced. Since the details of the annual exercise are held confidential, the unannounced communications drill can be conducted in conjunction with the annual exercise.

Page 8 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS

8.0 INSTRUCTIONS

(continued) 8.2 Conducting Drills

1. The Nuclear Plant Supervisor (NPS) will evaluate the plant conditions and ascertain that the drill will not adversely affect plant equipment or operations.

2. The Plant General Manager will designate specific members of the plant staff to act as controllers and evaluators during the drill. These controllers and evaluators will be familiar with the procedures and proper actions to be taken associated with their post during the drill. Additionally, briefings will be conducted to indicate what purpose the drill will serve and what specific areas the controllers and evaluators should be concerned with.

These controllers and evaluators will be posted throughout the plant area to observe and record the actions of plant personnel during the drill and to verify alarm audibility.

3. At the termination of the drill, the NPS will announce over the PA system that the drill is over. This will be repeated along with any required instructions.

8.3 Evaluation of Drills and Exercises Following a drill, the Emergency Planning Coordinator will assimilate all information and data concerning the emergency procedure drill, hold a critique on the drill, and present a summary of the critique to the Facility Review Group (FRG).

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

2. Following an exercise, the Manager Nuclear Emergency Preparedness, Emergency Preparedness Coordinator, plant management, FPL controllers and evaluators and principal participants in the exercise will meet to discuss and evaluate the exercise.

The evaluation will be based on the ability of participants to follow emergency procedures, the adequacy of emergency procedures, and the adequacy of emergency equipment and supplies.

Page 9 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS

8.0 INSTRUCTIONS

(continued) 8.3 (continued)

3. The Emergency Planning Coordinator will prepare a written report of the exercise evaluation. The report which will include suggested corrective actions, will be submitted to the FRG for review.

4. Plant management will be responsible for necessary changes in the Plant Emergency Procedures and for recommending and/or submitting changes in the Emergency Plan to the Manager - Nuclear Emergency Preparedness.

8.4 Emergency Preparedness Program Maintenance Items

1. The Emergency Planning Coordinator will ensure all onsite Emergency Preparedness Program maintenance items are accomplished and will complete appropriate checklists from Appendix A, EP Maintenance Checklists.

Page 10 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS APPENDIX A EP MAINTENANCECHECKLISTS Checklist 1 of 5 (YEAR)

Quarterl EP Maintenance Items: INITIAL/ DATE

1. FPL Offsite ERO Communications Drill A. Qtr 1 Date~~

B. Qtr 2 Date~~

C. Qtr 3 Date~~

D. Qtr 4 Date~~

2. Phonelist Verification and Update A. Qtr 1 Date~ /

B. Qtr 2 Date~~

C. Qtr 3 Date~~

D. Qtr 4 Date~~

Reviewed by Protection Services Supervisor S OPS DATE DOCT DOCN sYs COMP ITM

Page 11 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 M'AINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS APPENDIX A EP MAINTENANCECHECKLISTS Checklist 2 of 5 (Page 1 of 2)

(YEAR)

~

Annual/Semi-Annual EP Maintenance Items: INITIAL/ DATE

1. Exercise Dates A. Practice B. Evaluated

2. Offsite Agencies Communications Drill A. Date~~

3. Unannounced Communications Drill A. Date~~

4. Radiological Monitoring Drill A. Date / /

5. Medical Drill A. Date~~

6. Offhours Call-Out Phone Test/Drill A. Date / / Time

7. Emergency Plan Review

8. Emergency Plan Implementing Procedure Review

9. HP Drill (Jan-Jun) Date~~

(Jul-Dec) Date~~

Page 12 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS APPENDIX A EP MAINTENANCE CHECKLISTS Checklist 2 of 5 (Page 2 of 2)

(YEAR)

Annual/Semi-Annual EP Maintenance Items: INITIAL/ DATE NOTE Months indicated for items below are suggested completion periods; actual completion periods may vary.

10. Prompt and track the annual training of TSC, OSC and Security Team personnel A. (Mar) Transmit annual TSC and OSC training population lists to PSL Technical Training Supervisor B. (Nov) Solicit verification of TSC and OSC training completion from PSL Technical Training Supervisor C. (Nov) Solicit verification of Security Team training completion from PSL Security Supervisor D. (Dec) Review training completion feedback and remove any members from positions for which required training has not been maintained. ERO changes are to be effective on Jan. 1 of the new year.

11. Annual EP Coordinator inspection of emergency kits, TSC equipment cabinets and TSC document cabinets Reviewed by Protection Services Supervisor

/R14

Page 13 of 16 t ~

ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS APPENDIX A EP MAINTENANCE CHECKLISTS Checklist 3 of 5 (YEAR)

Drill Items: INITIAL/ DATE

1. Drill Type

2. Select Drill Date A. Date~~

3. Obtain Drill Approval A. Approved B, Advise offsite, as requested

4. Develop Drill Package to Include:

A. Purpose B. Objectives C. Simulations D. Messages

5. Evaluate Drill Performance

6. Review Drill Critique Items and Recommended Corrective Actions with FRG.

A. FRG Date~~

Reviewed by Protection Services Supervisor

Page 14 of 16 ST, LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14 i MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS APPENDIX A EP MAINTENANCE CHECKLISTS Checklist 4 of 5 (YEAR)

Exercise Items: INITIAL/ DATE

1. Exercise Date Selection:

A. Practice Date ~~

B. Evaluated Date ~~

2. Support Personnel Assigned A. Scenario Development B. Controllers/Evaluators

3. Exercise Objectives Submitted to NRC (75 Days)

A. Date~~

4. Exercise Scenario Submitted to NRC (45 Days)

A. Date~~

5. Controller Training A. Practice Ex. Date~~

B. Evaluated Ex. Date~~

6. Post Exercise Critique A. Practice Ex. Date~~

B. Evaluated Ex. Date~~

Critique Report Review A. Practice Ex., FRG Date~~

B. Evaluated Ex., FRG Date~~

Reviewed by Protection Services Supervisor

Page 15 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14

'MAINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS APPENDIX A EP MAINTENANCECHECKLISTS Checklist 5 of 5 (Page 1 of 2)

Annual Reviews:

I. Emergency Plan (Year)

Revision No.: Date Reviewed:~~

II. Emergency Plan Implementing Procedures PCR Revision No. Date Reviewed Y/N EPIP 3100021E Duties and Responsibilities of the Emergency'oordinator EP IP 3100022E Classification of Emergencies EPIP 3100023E Onsite Emergency Organization and Call Directory EP IP 3100024E Natural Emergencies EPIP 3100025E Fire Emergencies EPIP 3100026E Criteria for and Conduct of Evacuations EPIP 3100027E Reentry EPIP 3100029E Duties of an Individual Who Discovers and Emergency Condition EPIP 3100032E Onsite Support Centers EPIP 3100033E Offsite Dose Calculations EP IP 3100034E Maintaining Emergency Preparedness-Emergency Response Plan Training EPIP 3100035E Offsite Radiological Monitoring EP IP 3100050E Maintaining Emergency Preparedness-Emergency Exercises, Drills, Tests, and Evacuations HP-90 Emergency Equipment HP-200 HP Emergency Organization HP-201 Emergency Personnel Exposure Control HP-202 Environmental Monitoring During Emergencies HP-203 Personnel Access Control During Emergencies HP-204 In Plant Radiation and Contamination Surveys during Emergencies

Page 16 of 16 ST. LUCIE PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 3100050E, REVISION 14

'tv7AINTAININGEMERGENCY PREPAREDNESS - EMERGENCY EXERCISES DRILLS TESTS AND EVALUATIONS APPENDIX A EP MAINTENANCE CHECKLISTS Checklist 5 of 5 (Page 2 of 2)

II. Emergency Plan Implementing Procedures (continued)

PCR Revision No. Date Reviewed Y/N HP-205 Emergency Inplant Air Sampling HP-206 Analysis of Emergency Inplant Air Samples HP-207 Monitoring Evacuated Personnel During Emergencies HP-208 Personnel Decontamination During Emergencies C-110 Collecting Initial Set of Post Accident Samples and Guidelines for Establishing Post Accident Water and Gas Inventory Control C-111 Establishing Remote Analysis Laboratory, Counting Laboratory, and Counting Procedures for Accident Samples Reviewed by Protection Services Supervisor

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