Text

Revised Emergency Plan Implementing Procedures, EPIP-01, Revision 5, Table of Contents - EPIP-01, Revision 10, Attachment 13
	ML022470250
Person / Time
Site:	Saint Lucie
Issue date:	08/26/2002
From:	Jernigan D; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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Procedure No.

ST. LUCIE PLANT EPIP-01 EMERGENCY PLAN Current Revision No.

IMPLEMENTING PROCEDURE 5 F PL SAFETY RELATED Effective Date 08101/02

Title:

CLASSIFICATION OF EMERGENCIES Responsible Department: EMERGENCY PLANNING REVISION

SUMMARY

Revision 5 - Clarified EALs under alert. (J. R. Walker, 07/25/02)

Revision 4 - Revised lAW revision to E-Plan (R40). Revised initiating condition for RCS leakage. Added EALs under security threat initiating condition. Added definitions for EAL and IC. Added guidance for multiple and dual unit events. Made editorial and administrative changes. (J.R. Walker, 05/23/02)

Revision 3 - Added PMAI references, added definitions for OCA, PA and power block, clarified classification guidance and made editorial/administrative changes.

(J. R. Walker, 02/09/01)

Revision 2 - Clarified initiating conditions and emergency action levels to correspond to changes in the PSL emergency plan in accordance with PMAI PM99-09-154, defined classification table and made editorial changes. (J. R. Walker, 10/13/00)

Revision I - Revised to RCS EAL for alert based on NESP007 guidance. (J. R. Walker, 04/21/00)

PSL 0

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PROCEDURE PRODUCTION Revision FRG Review Date Approved By Approval Date S OPS 0 J. Scarola 12/15/97 DATE 0 12/15/97 Plant General Manager DOCT PROCEDURE Revision Approved By Approval Date DOCN EPIP-01 Revision FRG Review Date 5 Dick Rose 07/26/02 SYS 5 07/25/02 Plant General Manager COM COMPLETED N/A ITM 5 Designated Approver NIA Designated Approver (Minor Correction)

REVISION NO.. PROCEDURE TITLE: PAGE' 5 CLASSIFICATION OF EMERGENCIES 2 of 32 PROCEDURE NO EPIP-01 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 P U R P O S E ...................................................................................................... 3

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS... 3 3.0 RESPONSIBILITIES .................................................................................. 4 4.0 DEFINITIONS ........................................................................................... 5 5.0 INSTRUCTIONS ........................................................................................ 9 ATTACHMENTS ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE ............................. 13

REVISION NO* PROCEDURE TITLE. PAGE' 5 CLASSIFICATION OF EMERGENCIES 3 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT 1.0 PURPOSE This procedure provides instructions on the classification of emergencies at St.

Lucie Plant.

Emergency classifications in order of increasing seriousness are:

0 Unusual Event

Alert

Site Area Emergency 0 General Emergency Specific criteria are provided to assure proper escalation and de-escalation between emergency classification levels.

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

T Indicates a step that requires a sign off on an attachment.

2.1 References

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

2. E-Plan Implementing Procedures (EPIP 00-13)

3. C-200, Offsite Dose Calculation Manual (ODCM)

4. AP 0010502, Oil and Hazardous Material Emergency Response Plan

5. ¶j NUREG-1022, Section 3.1.1

PROCEDURE TITLE. PAGE:

REVISION NO:

5 CLASSIFICATION OF EMERGENCIES 4 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT 2.1 References (continued)

6. %2 NRC IEN No. 85-80, Timely Declaration of an Emergency Class, Implementation of an Emergency Plan, and Emergency Notifications, October 15, 1985

7. ¶3 NRC EPPOS No. 2, Emergency Preparedness Position (EPPOS) on Timeliness of Classification of Emergency Conditions, August, 1995

8. ¶4 PMAI PM98-01-017, Loss of Seismic Monitoring Capability 2.2 Records Required The basis for classifying an emergency condition shall be recorded in appropriate emergency logs.

2.3 Commitment Documents

§1 CR 00-0614 (RCS leakage during shutdown cooling)

§2 PMAI PM99-09-154 (IC and EAL changes submitted under FPL letter L-98-2000).

3.0 RESPONSIBILITIES 3.1 Nuclear Plant Supervisor (NPS)

1. The Nuclear Plant Supervisor is responsible to promptly classify abnormal situations into one of the four defined categories.

2. If an emergency has been declared, the Nuclear Plant Supervisor is responsible for assuming the position of Emergency Coordinator and retaining this position until relieved.

3.2 Emergency Coordinator (EC)

The Emergency Coordinator is responsible to continually evaluate changes in plant conditions against the classification table in this procedure.

PROCEDURE TITLE PAGE.

REVISION NO:

5 CLASSIFICATION OF EMfRGENCIES 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT 4.0 DEFINITIONS 4.1 Emergency Action Level (EAL)

1. A pre-determined, site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be:

an instrument reading; an equipment status indicator; a measurable parameter (on-site or off-site); a discrete, observable event; results of analyses; entry into specific emergency operating procedures; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.

4.2 Emergency Classes

1. Unusual Event This classification is represented by off-normal events or conditions at the plant for which no significant degradation of the level of safety of the plant has occurred or is expected. Any releases of radioactive material which may have occurred or which may be expected are minor and constitute no appreciable health hazard.

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

3. Site Area Emergency This classification is composed of events which involve actual or likely major failures of plant functions needed for protection of the public combined with a potential for significant uncontrolled releases of radioactivity from the plant.

4. General Emergency This classification is composed of events which involve actual or imminent substantial core degradation and potential loss of containment integrity combined with a likelihood of significant uncontrolled releases of radioactivity from the plant.

PROCEDURE TITLE PAGE.

REVISION NO.:

5 CLASSIFICATION OF EMERGENCIES 6 of 32 PROCEDURE NO EPIP-01 ST. LUCIE PLANT 4.3 Classification Table A composite of Initiating Conditions (ICs) and their Emergency Action Levels (EALs) used to evaluate off normal/emergency conditions resulting in declaration of one of the four Emergency Classes, as appropriate. The Table is arranged in the following categories:

1. Events Affecting Primary Pressure A. Abnormal Primary Leak Rate B. Abnormal Primary/Secondary Leak Rate C. Loss of Secondary Coolant

2. Abnormal Radiation, Contamination and Effluent Releases A. Uncontrolled Effluent Release B. High Radiation Levels in Plant

3. Fires, Explosions

4. Accident Involving Fuel A. Fuel Element Failure B. Fuel Handling

5. Natural Emergencies A. Earthquake B. Hurricane C. Tornado D. Abnormal Water Level

6. Miscellaneous Events A. Increased Awareness or Potential Core Melt

7. Electrical Malfunctions A. Loss of Power

REVISION NO: PROCEDURE TITLE. PAGE.

5 CLASSIFICATION OF EMERGENCIES 7 of 32 PROCEDURE NO

EPIP-01 ST. LUCIE PLANT 4.3 Classification Table (continued)

8. Degradation of Control Capabilities A. Loss of Plant Control Functions B. Loss of Alarms, Communications, Monitoring

9. Hazards to Station Operation A. Aircraft, Missile B. Turbine Failure C. Toxic or Flammable Gas

10. Security Threat 4.4 Initiating Condition (IC)

1. One of a predetermined subset of nuclear power plant conditions where either the potential exists for a radiological emergency, or such an emergency has occurred.

4.5 Plant - The St. Lucie Plant, Unit 1 and Unit 2 4.6 Site - A general term referring to the location of the St. Lucie Nuclear Power Plant.

Other terms related to the site are given below:

I. Owner Controlled Area - That portion of FPL property surrounding and including the St. Lucie Nuclear Power Plant which is subject to limited access and control as deemed appropriate by FPL.

2. Protected Area - The area (within the Owner Controlled Area) occupied by the nuclear units and associated equipment and facilities enclosed with the security perimeter fence. The area within which accountability of personnel is maintained in an emergency.

REVISION NO.: PROCEDURE TITLE PAGE 5 CLASSIFICATION OF EMERGENCIES 8 of 32 PROCEDURE NO

EPIP-01 ST. LUCIE PLANT 4.6 Site (continued)

3. §2 Power Block - Structures, systems or components in the areas listed below that support the production of power. This includes any equipment needed for the direct generation of power or necessary for safe operation and/or shutdown of one or both of the reactors.

A. Reactor Containment and Shield Buildings B. Reactor Auxiliary Buildings including the following areas:

1. Refueling Water Tank (RWT)

2. Component Cooling Water (CCW) platform area

3. Diesel Generator Buildings and Fuel Oil Storage Tanks

4. Fuel Handling Building

5. Primary Water Tank and Pumps C. Intake Area D. Discharge Canal & Headwall E. Ultimate Heat Sink Structure F. Fire Protection System including the fire pumps and the City Water Storage Tanks (CWST), but not including parts of the system associated with the North or South Service Buildings or other outlying facilities.

G. Turbine Buildings (all levels)

H. Condensate Storage Tanks (CST)

I. Main, Auxiliary and Startup Transformers J. Steam Trestles K. Turbine Lube Oil Storage Tanks L. Gas House

PROCEDURE TITLE PAGE REVISION NO*

5 CLASSIFICATION OF EMERGENCIES 9 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 Direct Initial Investigative and Mitigating Actions to Address the Event

1. If the event involves entry into the Off-Normal Operating Procedures (ONOPs) or Emergency Operating Procedures (EOPs), Then perform steps per ONOPs or EOPs until appropriate or directed to classify event.

2. If the event involves a release of hazardous materials to the environment, Then respond per AP 0010502, Oil and Hazardous Material Emergency Response Plan.

3. If the event involves a release of radioactive material to the environment, Then direct Chemistry personnel to implement EPIP-09, Off-site Dose Calculations.

END OF SECTION 5.1

REVISION NO.: PROCEDURE TITLE PAGE:

5 CLASSIFICATION OF EMERGENCIES 10 of 32 PROCEDURE NO.'

EPIP-01 ST. LUCIE PLANT NOTE Initiating Conditions / Emergency Action Levels are applicable to all modes unless otherwise indicated.

5.2 Classifying the Event

1. ¶3 A goal of fifteen (15) minutes should be used for assessing and classifying an emergency once indications (Emergency Action Levels (EALs)) are available to Control Room Operators that an Initiating Condition (IC) has been met and/or exceeded.

A. This goal should allow time for determination of indications (leak rate, etc.) and detailed review of Attachment 1, Emergency Classification Table.

2. Use the best information available when working through the Emergency Classification Table. When confronted with conflicting information for which resolution is not apparent, classify the condition at the highest appropriate emergency class.

3. If, in the judgement of the Nuclear Plant Supervisor (NPS)/Emergency Coordinator (EC), a situation is more serious than indicated by instrument readings or other parameters, Then classify the emergency condition at the more serious level (i.e., at the highest appropriate emergency class).

4. Multiple and Dual Unit Events CAUTION There can not be two concurrent declared emergency classes under the St. Lucie Plant Radiological Emergency Plan.

A. 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, Then a new classification should NOT be declared. The event should be documented on a SNF as "Additional Information or Update" and issued as soon as practicable.

B. If one Unit is in a classified event and the other Unit enters into a more severe event in which a higher Emergency Class would apply, Then the new classification shall be declared and promptly, within the regulatory time limits, issued to the State, Counties and the NRC.

REVISION NO: PROCEDURE TITLE: PAGE 5 CLASSIFICATION OF EMERGENCIES 11 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT 5.2 Classifying the Event (continued)

5. ¶2 Ifan EAL was met and the condition completely cleared prior to an emergency classification being declared, Then:

A. Classify the event in accordance with Attachment 1.

B. Termination of the event

1. An event classified as an Unusual Event or Alert may be terminated at the time of declaration by the EC.

2. An event classified as a Site Area Emergency or General Emergency may only be downgraded and/or terminated by the Recovery Manager (RM).

END OF SECTION 5.2

REVISION NO

PROCEDIURE TITLE 1ý! I.

PAGE 5 CLASSIFICA, OF EMiRGENCIES 12 of 32 PROCEDURE NO:

EPIP-01 ST E PLANT I

I 5.3 ¶1, Classification of An Event Bas, Subsequent Information detailed nature (e.g., sampling

1. If subsequent information of a\ results) becomes available after the in' Ilassification has been made, Then reclassify as appropriate.

2. If results of a protracted review (i.e., Engineering Evaluation, CR disposition, etc.) of an event indicate that conditions were met for an Emergency Classification, and the condition has completely cleared prior to recognition of possible classification, Then notify NRC within one hour of discovery of the undeclared event.

A. Contact Emergency Preparedness for briefing of state and local agencies.

END OF SECTION 5.3

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REVISION NO" PROCEDURE TITLE:

5 CLASSIFICATION OF EMERGENCIES 13 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 1 of 20)

Sc A o o CAUTION

§2 Section 1 A should not be used for a steam generator tube leak / rupture ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS UNUSUAL EVENT A release has occurred or Is In oroaress Reactor Coolant System (RCS) Leakage RCS Leakaae GREATER THAN 50 qpm LOCA GREATER THAN capacity of 1A ABNORMAL PRIMARY charging pumps resultina In*

LEAK RATE 1. Unisolable RCS leakage as indicated by (Page 1 of 2) I RCS leakage GREATER THAN 1 Containment High Range Radiation Charging/letdown mismatch greater 1. RCS leakage greater than available monitor greater than 1.46 X 105 R/hr (If 10 gpm as Indicated by charging pump capacity occurring with than 50 gpm but less than available CHRRM inoperable, Post-LOCA Control Room observation charging pump capacity RCS pressure above HPSI shutoff A

head monitors greater than 1000 mR/hr)

OR OR OR

2. Unisolable measured RCS leakage OR B Inventory balance calculation 2. Performance of EPIP-09 (Off-site Dose.

InD Indicating greaterthan 50 gpm but less 2 RCS leakage greater than available o...... o ,,. =.Iu vy either

0. LUSS UT t' SUULUU~tIU Id1i,

UuW IU AND RCS leakage (saturated conditions) A, B, C or D below:.

Inability to reduce the leak rate to OR technical specification limits within

4. Containment High Range Radiation A 1000 mrem/hr (total dose rate) the timeframe of the action Monitors indicate 7 3 X 103 R/hr (If statement CHRRM Inoperable, Post-LOCA B 1000 mrem (total dose - TEDE)

NOTE monitors Indicate between 100 and For RCS Leakage In Section 1 1000 mR/hr) C 5000 mremlhr (thyroid dose rate) above, the (Notification of)

Unusual Event should be D 5000 mrem (thyroid dose - CDE) declared upon commencing a load reductionlmode change.

(continued on next page)

OR 2 Indication of leaking RCS safety or relief valve which causes RCS pressure to drop below setpoints" Unit 1 - 1600 psla

- Unit 2 - 1736 psla 1A ABNORMAL PRIMARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

REVISION NO.: PROCEDURE TITLE. PAGE*

5 CLASSIFICATION OF EMERGENCIES 14 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 2 of 20)

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1 A ABNORMAL PRIMARY Loss of 2 of the 3 fission product LEAK RATE bamers with imminent loss of the (Page 2 of 2) third (any two of the following exist and the third is Imminent)

1. Fuel element failure (confirmed DEQ 1-131 activity greater than 275 pCI/mL)

AND 2 LOCA or Tube rupture on unisolable steam generator.

AND

3. Containment Integrity Breached.

NOTE Also refer to Potential Core Melt Event / Class 6 A.

I.A. ABNORMAL PRIMARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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REVISION NO.: PROCEDURE TITLE.

5 CLASSIFICATION OF EMERGENCIES 15 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 3 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS Rapid gross failure of one steam Rapid gross failure of steam Loss of 2 of the 3 fission product 1B ABNORMAL RCS PRI/SEC Leakage barriers with imminent loss of the, generator tube (WITHIN charging generator tubes (GREATER THAN PRIMARY TO charging pump capacity) with a loss third (any two of the following exist SECONDARY LEAK 1. Measured RCS to secondary pump capacity) with loss of offsite power of offsite power and the third is imminent)

RATE leakage exceeds Tech Spec (Page 1 of 2) limits 1 Fuel element failure (confirmed AND 1 Measured RCS to secondary 1 Measured RCS to secondary leakage is greater than charging DEQ 1-131 activity greater than

2. Secondary plant activity is leakage greater than Tech. Spec 275 pCi/mL) detected Limits and within charging pump pump capacity.

AND AND capacity.

AND 2. Secondary plant activity is 2 LOCA or Tube rupture on detected unisolable steam generator.

2. Secondary plant activity is AND AND detected.

AND 3. Loss of both Non-Vital 4.16 KV 3 Containment integrity breached

3. Loss of both Non-Vital 4.16 KV buses buses (continued on next page)

(continued on next page)

NOTE Also refer to Potential Core Melt Event/Class 6 A 1 B. ABNORMAL PRIMARY TO SECONDARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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5 CLASSIFICATION OF EMERGENCIES PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 4 of 20)

ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS UNUSUAL EVENT Rapid failure of steam generator §2 Rapid failure of steam generator 1B. ABNORMAL tube(s) (GREATER THAN charging tubes (GREATER THAN charging PRIMARY TO pump capacity) with steam release in pump capacity)

SECONDARY LEAK progress RATE (Page 2 of 2) 1. Measured RCS to secondary leakage greater than charging 1. Measured RCS to secondary pump capacity. leakage greater than charging AND pump capacity.

2 Secondary plant activity is AND detected. 2 Secondary plant activity is detected AND

3. Secondary steam release in progress from affected generator (i e, ADVs, stuck steam safety(s) or unisolable leak )

1 B. ABNORMAL PRIMARY TO SECONDARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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5 CLASSIFICATION OF EMERGENCIES PROCEDURE NO, EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 5 of 20)

ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS UNUSUAL EVENT Maior steam leak with A release has occurred or is in Rapid depressunzation of secondary Malor steam leak with 1 C LOSS OF GREATER THAN 50 qpm SECONDARY plant GREATER THAN 10 .pm progress resulting in pnmary/secondary leakage pnmary/secondary leakage and fuel COOLANT damage indicated 1. Containment High Range (Page 1 of 2) 1 Rapid drop in either steam Radiation monitor greater than generator pressure to less than 1. Rapid drop in either steam generator pressure to less than 1. Rapid drop in either steam 1.46 X 105 R/hr (If CHRRM 600 psia generator pressure to less than inoperable, Post-LOCA monitors 600 psia greater than 1000 mRlhr)

AND 600 psia AND OR 2 Known pri/sec leak of greater

2. Known pn/sec leak of greater 2. Performance of EPIP-09 (Off-site than 10 gpm.

AND than 50 gpm. Dose Calculations) or measured AND dose rates from off-site surveys

3. Secondary plant activity is indicate site boundary (1 mile) detected. 3 Secondary plant activity is detected. exposure levels have been AND exceeded as indicated by either 4 Fuel element damage is indicated A, B, C or D below:

(Refer to Fuel Element Failure Total loss of feedwater Event/Class 4 A). A. 1000 mrem/hr (total dose rate)

1. No main or auxiliary feedwater flow available for greater than B 1000 mrem (total dose 15 minutes when required for TEDE) heat removal TLOF with once-through cooling AND initiated C 5000 mrem/hr (thyroid dose

2. Steam Generator levels are less rate) than 40% wide range 1. No main or auxiliary feedwater flow available. D 5000 mrem (thyroid dose AND CDE) 2 PORV(s) have been opened to facilitate core heat removal (continued on next page) i C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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REVISION NO: PROCEDURE TITLE' 5 CLASSIFICATION OF EMERGENCIES 18 of 32 PROCEDURE NO' EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 6 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS Loss of 2 of the 3 fission product I.C LOSS OF bamers with imminent loss of the SECONDARY third (any two of the following exist COOLANT and the third Is imminent)

(Page 2 of 2) 1 Fuel element failure (confirmed DEQ 1-131 activity greater than 275 pCI/mL)

AND

2. LOCA or Tube rupture on unisolable steam generator.

AND 3 Containment Integnty Breached NOTE Also refer to Potential Core Melt Event/Class 6 A 1 C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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PROCEDURE TITLE 5 CLASSIFICATION OF EMERGENCIES 19 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 7 of 20)

ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS UNUSUAL EVENT A release has occurred or is in A release has occurred or is in §2 A release has occurred or is in 2A UNCONTROLLED Radiological effluent limits exceeded progress resulting in:

progress that is 10 times the effluent progress resulting in EFFLUENT RELEASE limit 1 Plant effluent monitor(s) exceed 1. Containment High Range 1. Containment High Range alarm setpoint(s). Radiation Monitor greater than Radiation monitor greater than AND 1. Plant effluent monitor(s) 1 46 X 10'5 Rhr (IfCHRRM significantly exceed alarm 7.3 X 103 RPhr (Post-LOCA 2 Confirmed analysis results for monitors indicate between inoperable, Post-LOCA monitors gaseous or liquid release which setpoints. greater than 1000 mRlhr)

AND 100 and 1000 mR/hr, if CHRRM exceeds ODCM limits inoperable). OR

2. Confirmed analysis results for 2. Performance of EPIP-09 (Off-site gaseous or liquid release which OR

2. Measured Dose Rates or Offsite Dose Calculations) or measured exceeds 10 times ODCM limits dose rates from off-site surveys Dose Calculation (EPIP-09) worksheet values at one mile in Indicate site boundary (1 mile)

NOTE NOTE exposure levels have been excess of.

If analysis is not available within Ifanalysis is not available within exceeded as indicated by either A, one hour and it is expected that one hour and it is expected that A. 50 mrem/hr (total dose rate) B, C or D below.

release is greater than ODCM release is equal to or greater or 250 mremrhr (thyroid dose limit, classify as UNUSUAL than 10 times ODCM limit, rate) for 1/2 hour A 1000 mrem/hr (total dose rate)

EVENT. classify as ALERT OR B. 500 mrem/hr (total dose rate) B. 1000 mrem (total dose -TEDE) or 2500 mrem/hr (thyroid dose rate) for two minutes at C. 5000 mrem/hr (thyroid dose one mile rate)

D 5000 mrem (thyroid dose-CDE) 0DCM - refers to Chemistry Procedure C-200, Offsite Dose Calculation Manual (ODCM) 2A UNCONTROLLED EFFLUENT RELEASE COORDINATOR AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY

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5 CLASSIFICATION OF EMERGENCIES 20 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 8 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS High radiation levels or high airborne 2B HIGH RADIATION contamination which indicates a LEVELS IN PLANT severe degradation inthe control of radioactive materials

1. Any valid area monitor alarm from an unplanned source with 01 meter near or greater than full scale deflection (103 mR/hr)

OR 2 Unexpected plant Iodine or particulate airborne concentration of 1000 DAC as seen in routine surveying or sampling OR 3 Unexpected direct radiation dose rate reading or unexpected airborne radioactivity ;0 concentration from an unplanned source in excess of 1000 times normal levels.

2 B HIGH RADIATION LEVELS IN PLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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5 CLASSIFICATION OF EMERGENCIES 21 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 9 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS Uncontrolled fire §2 Fire compromising the function of NOTE

3. FIRE §2 Uncontrolled fire within the Power safety systems (e q, both trains Refer to Potential Core Melt Block lasting more than 10 minutes Event/Class 6 A

1. Potentially affecting safety rendered inoperable) systems AND 2 Requiring off-site support in the opinion of the NPS/EC NOTE 2 Explosion is defined as a rapid chemical reaction resultin in noise, heat and rapid expansion of as.

EXPLOSION Occurrence of an explosion within §2 Damage to structures/components in §2 Severe damage to safe shutdown the Owner Controlled Area the Protected Area by explosion equipment from explosion (e q , both which affects plant operation trains rendered inoperable

3. FIRE EXPLOSION AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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5 CLASSIFICATION OF EMERGENCIES PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 10 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENT/CLASS Fuel element failure with inadequate A release has occurred or is in Fuel element damage Fuel element failure 4.A. FUEL ELEMENT progress resulting in FAILURE core cooling

1. Process monitors or area 1. Process monitors or area 1 Containment High Range radiation surveys indicate 1. RCS DEQ 1-131 activity greater radiation surveys indicate than or equal to 275 pCi/mL Radiation monitor greater than increased letdown activity Increased letdown activity and AND 1.46 X 105 R/hr (IfCHRRM AND confirmed RCS Samples inoperable, Post-LOCA monitors indicating DEQ 1-131 activity 2 Highest CET per core quadrant 2 Confirmed RCS sample indicates greater than 10°F greater than 1000 mR/hr).

indicating* greater than or equal to OR 275 pCi/mL. superheat or 700°F.

2. Performance of EPIP-09 (Off-site A Coolant activity greater than Dose Calculations) or measured the Tech Spec limit for iodine dose rates from off-site surveys spike (Tech Spec indicate site boundary (1 mile)

Figure 3 4-1.). exposure levels have been OR exceeded as indicated by either A, B. Coolant activity greater than B, C or D below 100/E pCi/gram specific activity. A 1000 mrem/hr (total dose rate)

NOTE NOTE B 1000 mrem (total dose - TEDE)

Ifanalysis is not available within If analysis is not available one hour and it is expected that within one hour and it is C. 5000 mrem/hr (thyroid dose activity is greater than Tech expected that RCS activity for rate)

Spec limit, classify as DEQ 1-131 is greater than 275 UNUSUAL EVENT. pCi/mL, classify as an ALERT. D. 5000 mrem (thyroid dose CDE) 4.A FUEL ELEMENT FAILURE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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PROCEDURE TITLE*

5 CLASSIFICATION OF EMERGENCIES 23 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 11 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS Fuel handling accident which results §2 Malor damage to irradiated fuel in 4B FUEL HANDLING Containment or Fuel Handling ACCIDENT in the release of radioactivity to Containment or Fuel Handling Building Building.

1 Affected area radiation monitor

1. NPS/EC determines that an greater than 1000 mrem/hr.

Irradiated fuel assembly may AND have been damaged 2. Damage to more than one AND irradiated fuel assembly.

2. Associated area or process OR radiation monitors are in alarm. Major damage resulting from uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool 4 B FUEL HANDLING ACCIDENT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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REVISION NO: PROCEDURE TITLE.

5 CLASSIFICATION OF EMERGENCIES 24 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 12 of 20)

ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENT/CLASS UNUSUAL EVENT A confirmed earthquake has occurred I NOTE 5A EARTHQUAKE §2 A confirmed earthquake has occurred §2 A confirmed earthquake has occurred §2 Refer to Potential Core Melt Event I

1. A confirmed earthquake has Class 6 A

1. A confirmed earthquake has been 1. A confirmed earthquake has occurred which registered occurred which registered experienced within the Owner GREATER THAN 0.1g within the Controlled Area. GREATER THAN 0 05g within the Owner Controlled Area Owner Controlled Area and the plant OR not in Cold Shutdown.

2 ¶4 An earthquake Is detected by OR

2. A confirmed earthquake has OR plant seismic monitor 2. A confirmed earthquake has instruments or other means occurred that could or has caused trip of the turbine generator or occurred that has caused loss of any reactor. safety system function (e g , both trains Inoperable).

Humcane wamrin with winds NOTE 5B HURRICANE Humcane Warning

1. Confirmed hurricane warning is In Hurricane warning with winds near design basis

1. Confirmed hurricane warning is In GREATER THAN design basis

1. Plant not at cold shutdown.

I Refer to PotentialNOTE Class 6 A.

Core Melt Event!

effect and winds are expected to AND effect 2. Confirmed hurricane warning is in exceed 175 mph within the Owner Controlled Area effect and winds are expected to exceed 194 mph within the Owner Controlled Area.

NOTE NOTE NOTE At FPL's request, NOAA will provide an At FPL's request, NOAA will provide an accurate projection of wind speeds onsite accurate projection of wind speeds onsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the onset of hurricane 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the onset of hurricane force winds. If that projection is not force winds. Ifthat projection is not available within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of entering Into available within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of entering into the warning, classify the event using the warning, classify the event using current track and wind speeds to project current track and wind speeds to project onsite conditions. For example, projected onsite conditions. For example, projected onsite wind speed would be less than onsite wind speed would be less than maximum hurricane wind speed ifthe track maximum hurricane wind speed ifthe track is away from PSL. is away from PSL 5A EARTHQUAKE 5B HURRICANE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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PAGE' REVISION NO. PROCEDURE TITLE:

5 CLASSIFICATION OF EMERGENCIES 25 of 32 PROCEDURE NO..

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 13 of 20)

ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS UNUSUAL EVENT NOTE 5C TORNADO Notification of a tornado sighted in §2 Any tornado stnking the Power Refer to Potential Core Melt Event/

the Owner Controlled Area Block Class 6 A Abnormal water level conditions are Flood, low water, hurricane surge or Flood, low water, hurricane surge or 5.D. ABNORMAL WATER other abnormal water level other abnormal water level LEVEL expected or occumnri conditions causing failure of vital conditions equicpment 1 Low intake canal level of -10.5 ft MLW for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or more. 1. The storm drain capacity is exceeded during hurricane surge 1. Flood/surge water level reaching OR elevation +19 5 ft (turbine 2 Visual sightings by station or known flood conditions OR building / RAB ground floor) personnel that water levels are OR approaching storm drain system 2. Low Intake canal level of -10 5 ft MLW for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or more with 2. Low Intake canal level has capacity. caused the loss of all ICW flow emergency barrier valves open 5C TORNADO 5 D ABNORMAL WATER LEVEL AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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PAGE' REVISION NO* PROCEDURE TITLE*

5 CLASSIFICATION OF EMERGENCIES 26 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 14 of 20)

NOTE Activation of the Emergency Response Facilities does not require declaration of an emergency or entry into a specific emergency classification.

SITE AREA EMERGENCY I

GENERAL EMERGENCY EVENTICLASS UNUSUAL EVENT ALERT ludqement that Emergency Coordinator's ludgement that §z Emercnency Coordinator's ludgement that 6A INCREASED Emergency Coordinator's ludqement that §2 Emergency Coordinator's §2 plant conditions exist which are plant conditions exist that make release of AWARENESS OR plant conditions exist which warrant plant conditions exist which have a large amounts of radioactivity in a short potential to degrade the level of safety at siqnificantly degrading In an uncontrollable POTENTIAL CORE MELT Increased awareness on the part of the manner., penod appear possible or likely, (Any core (Page 1 of 2) operating staff andlor local authonties the plant melt situation) 1 The plant Is shutdown under abnormal 1 LOCA with failure of ECCS leading to conditions (e g, exceeding cooldown severe core degradation or melt.

rates or pnmary system pipe cracks are OR found during operation) 2 LOCA with Initially successful ECCS OR and subsequent failure of containment 2 Any plant shutdown required by heat removal systems for greater than Technical Specifications in which the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

required shutdown Is not reached OR within action limits. 3 Total loss of feedwater followed by failure of once-through-cooling (ECCS) to adequately cool the core OR 4 Failure of off-site and on-site power along with total loss of feedwater makeup capability for greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OR 5 ATWS occurs which results In core damage or causes failure of core cooling and make-up systems OR 6 Any major Internal or external event (e g , fire, earthquake or tomado substantially beyond design basis) which In the ECs opinion has or could cause massive damage to plant systems resulting In any of the above.

(continued on next page) 6A INCREASED AWARENESS OR POTENTIAL CORE MELT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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REVISION NO: PROCEDURE TITLE.

5 CLASSIFICATION OF EMERGENCIES 27 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 15 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENT/CLASS NOTES 6A. INCREASED 1. Most likely containment failure AWARENESS OR mode is melt-through with POTENTIAL CORE release of gases only.

MELT Quicker releases are expected (Page 2 of 2) for failure of containment isolation system

2. General Emergency must be declared for the above listed events The likelihood of corrective action (repair of AFW pump, etc ) should not be considered.

6A INCREASED AWARENESS OR POTENTIAL CORE MELT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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REVISION NO. PROCEDURE TITLE' 5 CLASSIFICATION OF EMERGENCIES 28 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 16 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENTICLASS I n--of off-site nnwer nr Inos nf all 62 Station Blackout (Total Loss of AC) §2 Station Blackout (Total Loss of AC) NOTE 7.A. LOSS OF POWER for GREATER THAN 15 minutes Refer to Potential Core Melt on-site AC power capability Event / Class 6A

1. Loss of off-site AC power AND 1. Loss of offsite AC power.

1. Loss of off-site AC power AND OR 2 Failure of both emergency diesel generators to start or load. 2 Sustained failure of both 2 Loss of capability to power at least emergency diesel generators to one vital 4.16 kv bus from any start or load.

available emergency diesel AND generator.

3. Failure to restore AC power to at Loss of all on-site DC power least one vital 4.16 kv bus within 15 minutes

1. Drop in A and B DC bus voltages to less than 70 VDC.

Loss of all vital on-site DC for greater than 15 minutes 1 Sustained drop in A and B DC bus voltages to 70 VDC for greater than 15 minutes.

7 A LOSS OF POWER AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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REVISION NO: PROCEDURE TITLE.

5 CLASSIFICATION OF EMERGENCIES 29 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 17 of 20)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENT/CLASS Loss of Plant Control Functions Cntical Loss of Plant Control Functions NOTE 8A LOSS OF PLANT Refer to Potential Core Melt Event CONTROL FUNCTIONS 1. Loss of any function or system Class 6 A.

1. Complete loss of any function needed for plant cold shutdown. which, in the opinion of the OR Emergency Coordinator, precludes

2. Failure of the Reactor Protection placing the plant in Hot Shutdown.

System to bring the reactor OR subcntical when needed 2 Failure of the RPS to trip the reactor OR when needed and operator actions

3. Control Room is evacuated (for other fail to bring the reactor subcritical than dnll purposes) with control OR established locally at the Hot 3. Control Room is evacuated (for Shutdown Control Panel other than drill purposes) and control cannot be established locally at the Hot Shutdown Control Panel within 15 minutes.

Loss of Shutdown Cooling

1. Complete loss of functions needed to maintain cold shutdown.

A. Failure of shutdown cooling systems, resulting in loss of cold shutdown conditions.

AND B RCS subcooling can NOT be maintained greater than 0°F.

8A LOSSOFPLANT CONTROL FUNCTIONS AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

I. I C C REVISION NO. PROCEDURE TITLE: PAGE:

5 CLASSIFICATION OF EMERGENCIES 30 of 32 PROCEDURE NO EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 18 of 20)

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Loss of alarms/monitoring 8 B. LOSS OF ALARMS I §2 v Significant loss of effluent monitonng §2 Loss of alarms COMMUNICATION / capability, communications, indication and alarm panels, etc, 1. Unplanned loss of most (greater 1. Inability to monitor* a significant MONITORING transient in progress which impairs ability to perform than 75%) or all safety system accident or emergency assessment annunciators.

AND

1. Loss of effluent or radiological 2. Plant transient in progress monitonng capability requiring plant shutdown OR 2 Loss of all primary and backup communication capability wth offsite locations OR 3 Unplanned loss of most (greater than 75%) or all Safety System annunciators for greater than 15 minutes.

Monitoring means loss of ERDADS, QSPDS and/or the inability to determine any one of the following.

reactivity control, core cooling, RCS status or containment integnty.

8.B. LOSS OF ALARMS /

COMMUNICATION /

MONITORING AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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5 CLASSIFICATION OF EMERGENCIES 31 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 19 of 20)

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 9 A AIRCRAFT I MISSILE Unusual aircraft activity §2 Aircraft/missile impact §2 Damage to vital systems from aircraft/missiles 1 Aircraft crash in the Owner 1. Aircraft crash into the Power Block.

Controlled Area or unusual aircraft OR 1. Aircraft crash into the Power activity over facility that In the 2 Visual or audible indication of Block damaging vital plant opinion of the NPS/EC, could missile impact on the Power Block systems.

OR threaten the safety of the plant or personnel. 2. Damage resulting in loss of safe shutdown equipment from any missile 9 B. TURBINE FAILURE Turbine rotating component failure Visual indication that the turbine causing rapid plant shutdown casing has been penetrated by blading 9 C. TOXIC OR Unplannedluncontrolled toxic or Entry of toxic or flammable gas into S2Toxic or flammable gas has diffused areas potentially affecting plant Into vital areas compromising the FLAMMABLE GAS flammable gas release in the Owner Controlled Area that could affect operation function of safety related equipment plant/personnel safety (e .q, both trains rendered inoperable) 9.A. AIRCRAFT / MISSILE 9 B TURBINE FAILURE 9 C. TOXIC OR FLAMMABLE GAS AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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REVISION NO.: PROCEDURE TITLE: PAGE 5 CLASSIFICATION OF EMERGENCIES 32 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 20 of 20)

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 10 SECURITY THREAT A SECURITY ALERT has been A SECURITY EMERGENCY has A SECURITY EMERGENCY A successful takeover of the plant been called by the Secunty Force as involving imminent occupancy of the includina the Control Room or anY called by the Secunty Force in response to one or more of the items defined in the Safeguards control room or other area(s) vital to other area(s) vital to the operation of listed below. Contingency Plan the operation of the reactor as the reactor (as per the Secunty Plan) defined in the Safeguards 1 Bomb threat Contingency Plan 2 Attack threat 3 Security threat

4. Protected Area intrusion attempt 5 Sabotage attempt 6 Internal disturbance

7. Civil disturbance 8 Vital Area Intrusion

9. Secunty Force stnke 10 Credible site-specific Security threat notification 10 SECURITY THREAT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

T --

Procedure No.

ST. LUCIE PLANT EPIP-02 Current Revision No.

EMERGENCY PLAN IMPLEMENTING PROCEDURE 10 FPL SAFETY RELATED Effective Date 08/01102

Title:

DUTIES AND RESPONSIBILITIE LF-T EMERGENCY COORDINA Q Responsible Department: EMERGENCY PLANNING 0<

REVISION

SUMMARY

PROCEDURE PRODUCTION Revision 10 - Clarified duties of DCS as phonetalker. Clarified checklists regarding steps not necessary in TSC. Made editorial/administrative changes. (J. R. Walker, 07/26102)

Revision 9 - THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN. Added responsibility for information services to update checklists in CRs, deleted basis of exposure guidelines, added statement on EC coverage during a prolonged event, deleted emergency declaration checklist, revised emergency class checklists, added reference to EPIP-07 and made editorial and administrative changes. (J. R. Walker, 06/11/01)

Revision 8 - Revised off-site assembly area to Jensen public beach parking area in accordance with revision 38 of the E-Plan and made administrative changed. (J. R. Walker, 10/13/00)

Revision 7 - Deleted policy reference per PMAI, clarified windspeed for unit shutdown, revised re-entry guidelines and made editorial changes. (J. R. Walker, 09/21/00)

Revision 6 - THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN. Deleted information and instructions for off-site notifications and PARs. Relocated to new EPIP-08 off-site notifications and protective action recommendations. Addressed early activation of emergency response facilities per PMAI PMOO-13-122. Made administrative and editorial changes. (Donna Calabrese, 05/31/00)

I Approved By Approval Date I S OPS Revision FRG Review Date J. Scarola 12/15/97 DATE 0 12/15197 Plant General Manager DOCT PROCEDURE Approved By Approval Date DOCN EPIP-02 Revision FRG Review Date 10 07/25/02 D. Rose 07/26/02 SYS Plant General Manager COM COMPLETED N/A ITM 10 Designated Approver N/A Designated Approver (Minor Correction)

REVISION NO: PROCEDURE TITLE: PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 2 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PUR PO SE ................................................................................................. 3

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS... 3 3.0 RESPO NSIBILITIES .................................................................................. 5 4.0 DEFIN ITIO NS ............................................................................................. 6 5.0 INSTRUCTIO NS ........................................................................................ 7 5.1 General Overview ........................................................................... 7 5.2 Unusual Event Declaration Checklist ............................................. 11 5.3 Alert Declaration Checklist ............................................................ 14 5.4 Site Area Emergency Declaration Checklist .................................. 19 5.5 General Emergency Declaration Checklist .................................... 25 ATTACHMENTS ATTACHMENT 1 INITIAL NOTIFICATION FLOW ............................................. 31 ATTACHMENT 2 CRITERIA FOR EVACUATION ............................................ 32 ATTACHMENT 3 TURNOVER GUIDELINES ................................................... 33 ATTACHMENT 4 FIELD OPERATOR RE-ENTRY GUIDELINES .................... 35 ATTACHMENT 5 EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSO NNEL ...................................................................... 36

REVISION NO.: PROCEDURE TITLE: PAGE.

10 DUTIES AND RESPONSIBILITIES OF THE 3 of 36 PROCEDURE NO.: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 1.0 PURPOSE 1.1 This procedure provides guidance and instructions to be followed by the Emergency Coordinator when an emergency occurs that requires the implementation of the Radiological Emergency Plan for St. Lucie Plant.

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

T Indicates a step that requires a sign off on an attachment.

2.1 References

1. St. Lucie Plant Updated Final Safety Analysis Report (UFSAR) Unit 1 and Unit 2 (Section 9.5.A.7.2)

2. §1 St. Lucie Plant Radiological Emergency Plan (E-Plan)

3. St. Lucie Plant Physical Security Plan

4. St. Lucie Plant Safeguards Contingency Plan

5. E-Plan Implementing Procedures (EPIP 00-13)

6. 10 CFR 50, Domestic Licensing of Production and Utilization Facilities.

7. NUREG/BR-0150, Vol. 1, Response Technical Manual (USNRC).

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.

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

REVISION NO

PROCEDURE TITLE: PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 4 of 36 PROCEDURE NO" EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 2.2 Records Required

%10 A copy of the checklists or data generated by this procedure shall be maintained in the plant files in accordance with QI-17-PSL-1, Quality Assurance Records. Records include:

1. Emergency Class Checklists 2.3 Commitment Documents

1. ¶1 PMAI PM96-04-165, "ITR 96-006" (Unusual Event Declared Due to Dropped Rod)

2. 12 NRC Inspection Report 91-01, Closure of IFIs 89-31-03 and 89-31-01

3. %3 PMAI PM96-09-185, Condition Report CR-96-1750 (Off-site Notification Using Commercial Phone)

4. %5 PMAI PM96-05-233, (Off-site Notification Process).

5. ¶6 Condition Report CR 96-2389, (Off-site Dose Calculations).

6. ¶7 Condition Report CR 98-1536 (EC Responsibilities Remain in the Control Room).

7. ¶8 PMAI PM98-09-006 (Control of NLOs Under E-Plan).

8. ¶9 Condition Report CR 99-1406 (Field Operator Dosimetry Under E-Plan).

9. ¶10 PMAI PM99-10-191, Condition Report CR 99-1656 (Quality Records, Downpower Guidance Due to Hurricanes).

10. ¶Ti PMAI PM99-10-142, Condition Report CR 99-1647 (EC Turnover).

11. ¶12 PMAI PM99-09-016, (PARs Based on FMT Data, Completion of NRC Notification Form).

12. ¶13 PMAI PMOO-01-043, (Gai-Tronics E-Plan Alarm).

13. ¶14 PMAI PMOO-03-122, (Early Activation of ERFs).

14. ¶15 Condition Report CR 02-0333, (Role of the Duty Call Supervisor). 0)

REVISION NO.: PROCEDURE TITLE: PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 5 of 36 PROCEDURE NO EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 3.0 RESPONSIBILITIES 3.1 The Nuclear Plant Supervisor (NPS) and the shift operating staff represent the first line of response to any developing emergency condition. The primary responsibility of the NPS is to control the condition as well as possible.

3.2 The NPS upon declaration of an emergency classification becomes the Emergency Coordinator (EC). The NPS remains the EC until the position is turned over.

Specific Responsibilities of the EC are:

Direction of the on-site emergency organization to bring the emergency under control.

Notification of off-site agencies within specific time limits as mandated by regulations.

Changes in Emergency Classification based on changing conditions.

Protective Action Recommendations (PARs) until turnover to the Recovery Manager.

Interfaces with the Nuclear Regulatory Commission (NRC) Reactor Safety Operations Coordinator (RSOC) when the NRC site team arrives at the TSC.

3.3 Information Services maintains user copies, in the Unit 1 and Unit 2 Control Rooms, of the following checklists used for implementing the Emergency Plan:

Unusual Event Declaration Checklist

Alert Declaration Checklist Site Area Emergency Declaration Checklist 0 General Emergency Declaration Checklist

REVISION NO: PROCEDURE TITLE: PAGE.

10 DUTIES AND RESPONSIBILITIES OF THE 6 of 36 PROCEDURE NO.: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 4.0 DEFINITIONS 4.1 §1 Duty Call Supervisor (DCS) - The Duty Call Supervisor is a designated and trained supervisor assigned from the nuclear plant staff to provide 24-hour response to any emergency upon notification by the Nuclear Plant Supervisor. The Duty Call Supervisor (DCS) is responsible for notifying the Emergency Response Organization and, as requested, Plant management in the event of an emergency.

4.2 Owner Controlled Area Evacuation (= Site Evacuation) - The evacuation from the owner controlled area of all personnel except those required to place the plant in a safe condition, the Emergency Response Organization (ERO), and Security personnel to fulfill responsibilities for evacuation.

4.3 Release (during any declared emergency)

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

OR

2. 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.

REVISION NO.: PROCEDURE TITLE PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 7 of 36 PROCEDURE NO' EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 General Overview I- ¶T7,11 Upon Declaration of an emergency classification the NPS becomes the EC.

To ensure access to the EC for direction and control decisions and so that the responsibilities of the position can be successfully completed, the EC position shall remain, initially in the affected Control Room and then in the Technical Support Center (TSC), when it goes operational.

Prior to the TSC being operational or in cases when there is a prolonged event such as a hurricane, the duties and responsibilities of the EC, while a Control Room position, may be turned over to another qualified EC:

If both Units are in classified events, the EC should locate in the Unit's Control Room with the highest classified event. If the site is in a dual Unit event, the EC should locate in the Unit 1 Control Room (due to proximity to the TSC).

If the TSC is activated, Then the EC position is turned over to an EC qualified member of plant management and the position relocated to the TSC. The prospective EC receives a turnover (refer to Attachment 3, Turnover Guidelines) from the Control Room EC and then reports to the TSC. Following verification of TSC operational readiness, the prospective EC accepts EC responsibility from the Control Room EC. The TSC EC may temporarily turnover responsibility to the TSC OPS Coordinator as the need arises.

2. To meet the above responsibilities, plus others described in this procedure, the EC will likely need to delegate many tasks. Although delegated, the completion of these tasks is still the responsibility of the EC.

The EC shall not delegate the following responsibilities prior to Emergency Operations Facility (EOF) being declared operational:

A. Classification of the emergency.

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

PROCEDURE TITLE PAGE REVISION NO.:

10 DUTIES AND RESPONSIBILITIES OF THE 8 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.1 General Overview (continued)

2. (continued)

C. Recommendation of protective actions for the public.

Once the EOF is operational and proper turnover has been conducted, the Recovery Manager (RM) will assume responsibility for off-site notifications to the state and local authorities and for recommending off-site protective actions.

3. Order of Succession If the NPS is incapacitated, Then the EC shall be (in order of succession):

A. Assistant Nuclear Plant Supervisor (ANPS) (from the affected unit)

B. Nuclear Watch Engineer (NWE)

C. Any other member of the plant staff with an active SRO license.

4. Watch Relief A. The EC shall grant permission for watch relief, including his/her own, only when it is safe in his/her judgement to do so.

5. ¶114 Early Activation of Emergency Response Facilities It may be useful to have technical and/or operational support available early in an emergency prior to when the Technical Support Center (TSC),

Operational Support Center (OSC), or Emergency Operations Facility (EOF) is required to be operational. Activation of any of these facilities does not require declaration of an emergency class or entry into a specific emergency classification. If early activation of one or more of the facilities is desired, then follow these guidelines:

A. This is an option during normal working hours only.

B. A page announcement should be made to request that appropriate Emergency Response Organization personnel to report to the

[identify what facility/facilities is/are to be activated early].

C. Turnover of EC responsibilities is done in accordance with Step 5.1.1, above.

REVISION NO.* PROCEDURE TITLE* PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 9 of 36 PROCEDURE NO. EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.1 General Overview (continued)

5. (continued)

D. The E-Plan Activation Alarm is used only when the Emergency Response Facilities (ERFs) are to be activated in accordance with the requirements of the Emergency Plan (i.e., at the Alert or higher emergency level) and is provided for in the checklist included in this procedure.

E. Staff augmentation due to actual facility activation is to be done in accordance with the Alert Declaration Checklist, Site Area Emergency Declaration Checklist or the General Emergency Declaration Checklist which are part of this procedure.

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

B. 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:

Emergency Response Facility (ERF) activation Local or Site Evacuation Site or Radiation Controlled Area (RCA) access Operator field activities Unit shutdown

7. Severe Weather Considerations

¶10 If a hurricane warning is in effect, and either one or both Unit(s) is/are in Mode 1, 2 or 3, Then use the following criteria for unit shutdown:

REVISION NO: PROCEDURE TITLE: PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 10 of 36 PROCEDURE NO.: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.1 General Overview (continued)

7. (continued)

NOTE Sustained hurricane force winds are sustained winds of 74 mph (64 kt or 119 kph) or greater.

A. For storms projected to reach a Category 1 or 2, the Unit(s) shall be placed in HOT STANDBY (Mode 3) or below at least two (2) hours before the projected onset of sustained hurricane force winds within the Owner Controlled Area and both Units shall remain off-line for the duration of the hurricane force winds (or restoration of reliable offsite power).

B. For storms projected to reach Category 3, 4 and 5 prior to landfall, the Units shall be shut down to a temperature less than 350 degrees T ave. at least two (2) hours before the projected onset of sustained hurricane force winds within the Owner Controlled Area and both Units shall remain off-line for the duration of the hurricane force winds (or restoration of reliable offsite power).

C. Establish an acceptable update frequency with state and local officials.

8. Drill Messages A. During exercises, drills, or tests, ALL MESSAGES shall begin and end with THIS IS A DRILL or THIS IS AN EXERCISE or THIS IS A TEST.

END OF SECTION 5.1

REVISION NO.: PROCEDURE TITLE: PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 11 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.2 Unusual Event Declaration Checklist TIME / INITIAL Date: / /

CAUTION Notification to the State Warning Point (SWP) shall occur within 15 minutes of declaration of the emergency classification. ml NOTE

Steps should be performed in the order presented. When conditions I warrant, steps may be performed out of sequence.

PA announcements are provided as a guideline. Actual announcements may vary from the text provided.

Not Applicable (N/A) may be used for tasks / steps previously aMrrnmntlichal I ctikfiPri

1. Determine the following:

A. Shift Technical Advisor (STA) present Y/N B. Duty Call Supervisor (DCS) present Y/N Wind direction (from) ° C.

NOTE During any declared emergency, a release is occurring if one of the following is true:

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

OR

"* Health Physics detecting airborne radioactivity levels in excess of 25 percent Derived Air Concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

D. Release in progress Y/N I

2. Mobilize emergency team personnel (i.e., Fire Team, First Aid

/

Team) as required using Gai-tronics and boost function.

REVISION NO* PROCEDURE TITLE PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 12 of 36 PROCEDURE NO EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.2 Unusual Event Declaration Checklist (continued) TIME I INITIAL

3. The NPS shall declare the emergency to the Control Room staff and formally announce that he / she is the Emergency Coordinator.

4. Notify plant personnel using Gai-tronics and boost function as follows:

"Attention all plant personnel, Unit 1 / 2 has declared an UNUSUAL EVENT. All personnel are to limit radio and phone use and listen for future instructions and further information."

Repeat the announcement.

5. Notify the Shift Technical Advisor and the Duty Call Supervisor to report to the Control Room using Gai-tronics and boost function.

(N/A if already performed)

"Shift Technical Advisor report to the Unit 1 / 2 Control Room."

"Duty Call Supervisor report to the Unit 1 / 2 Control Room."

6. 16 If a release of radioactive material has occurred or is in progress, Then notify Chemistry to promptly implement EPIP-09, Off-site Dose Calculations, and report the results to the Emergency Coordinator (EC).

7. If a Chemist is unavailable, Then call-out a Chemist (this may be accomplished by the DCS).

8. If evacuation of an area is necessary (refer to Attachment 2, Criteria for Evacuation), Then initiate a local evacuation.

9. ¶15 Complete required notifications in accordance with Appendix A, Notifications from the Affected Control Room, in EPIP-08, Off-site Notifications and Protective Action Recommendations. The DCS may be utilized as a phonetalker.

State Warning Point I NRC /

REVISION NO.: PROCEDURE TITLE. PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 13 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.2 Unusual Event Declaration Checklist (continued) TIME / INITIAL

10. Ensure notification of the following: (this may be accomplished by the DCS)

Plant Management Security Nuclear Division Duty Officer (NDDO)

11. Utilize Attachment 3, Turnover Guidelines when relinquishing /

duties to the oncoming EC.

NOTE New notification forms shall be completed for all updates.

_¶2

12. ¶15 If a State / Local notification frequency has been negotiated, Then provide an update, as necessary utilizing a new notification form. The DCS may be utilized as a phonetalker.

(Repeat as necessary) /

/

I

/

13. If the event can be terminated, Then complete the notification forms (State, NRC) and notify the following: (this may be accomplished by the DCS)

State Warning Point (SWP) 1

/

Plant Management I

Security

/

NDDO

/

NRC

14. UNUSUAL EVENT Declaration Checklist complete (emergency I upgraded or event terminated).

END OF SECTION 5.2

REVISION NO: PROCEDURE TITLE: PAGE' 10 DUTIES AND RESPONSIBILITIES OF THE 14 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.3 Alert Declaration Checklist TIME / INITIAL Date: / /

! CAUTION Notification to the State Warning Point (SWP) shall occur within 15 minutes of declaration of the emergency classification.

NOTE

Steps should be performed in the order presented. When conditions warrant, steps may be performed out of sequence.

PA announcements are provided as a guideline. Actual announcements may vary from the text provided.

For assistance with exposure control, refer to:

"* Attachment 4, Field Operator Re-entry Guidelines

"* Attachment 5, Exposure Limits for Emergency Response Personnel

Not Applicable (N/A) may be used for tasks / steps previously accomplished / satisfied.

1. Determine the following:

A. Shift Technical Advisor (STA) present Y/N B. Duty Call Supervisor (DCS) present Y/N 0

C. Wind direction (from)

REVISION NO.: PROCEDURE TITLE: PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 15 of 36 PROCEDURE NO' EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.3 Alert Declaration Checklist (continued) TIME / INITIAL

1. (continued)

NOTE During any declared emergency, release is occurring if one of the a

following is true:

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

OR

" Health Physics detecting airborne radioactivity levels in excess of 25 percent Derived Air Concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

D. Release in progress Y/N E. E-Plan Alarm sounded and Emergency Response Facilities (ERFs) activated Y/N

2. Mobilize emergency team personnel (i.e., Fire Team, First Aid Team) as required using Gai-tronics and boost function.

3. The NPS shall declare the emergency to the Control Room staff /

and formally announce that he / she is the Emergency Coordinator. /

4. ¶2 If a release of radioactive material is in progress, Then review personnel access with Health Physics personnel and notify Security personnel with any special instructions.

5. ¶13 Sound the Emergency Plan (E-Plan) Activation Alarm.

REVISION NO: PROCEDURE TITLE: PAGE.

10 DUTIES AND RESPONSIBILITIES OF THE 16 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.3 Alert Declaration Checklist (continued) TIME I INITIAL

6. Notify plant personnel using Gai-tronics and boost function as follows:

"Attention all plant personnel, Unit 1 / 2 has declared an ALERT. All emergency response personnel report at once to your assigned emergency response facility."

"All non-emergency response personnel report to your normal work location or contact your supervisor. Please limit radio and phone use and listen for further instructions and further information."

Repeat the announcement.

7. Notify the Shift Technical Advisor and the Duty Call Supervisor to report to the Control Room using Gai-tronics and boost function.

(N/A if already performed)

"Shift Technical Advisor report to the Unit 1 / 2 Control Room."

"Duty Call Supervisor report to the Unit I / 2 Control Room."

8. Initiate the call-out process in accordance with EPIP-03, Emergency Response Organization Notification / Staff Augmentation (this may be accomplished by the DCS).

9. ¶6 If a release of radioactive material has occurred or is in progress, Then notify Chemistry to promptly implement EPIP-09, Off-site Dose Calculations, and report the results to the Emergency Coordinator (EC).

10. If a Chemist is unavailable, Then call-out a Chemist (this may be accomplished by the DCS).

11. If evacuation of an area is necessary (refer to Attachment 2, Criteria for Evacuation), Then initiate a local evacuation.

REVISION NO.: PROCEDURE TITLE: PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 17 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.3 Alert Declaration Checklist (continued) TIME / INITIAL

12. ¶15 Complete required notifications in accordance with Appendix A, Notifications from the Affected Control Room, in EPIP-08, Off-site Notifications and Protective Action Recommendations. The DCS may be utilized as a..i C

phonetalker.

State Waming Point /

NRC /

13. Ensure notification of the following: (this may be accomplished by the DCS)

Plant Management /

Security /

Nuclear Division Duty Officer (NDDO) I

14. Initiate the Operations Department Accountability Aid for both Unit 1 and Unit 2 and provide this list to the TSC when requested.

(this may be accomplished by the DCS)

15. ¶9 Ensure Operations field personnel return to their assigned Control Room and obtain emergency Electronic Personal Dosimetry (EPD) from the HP Emergency Kit.

16. Utilize Attachment 3, Turnover Guidelines when relinquishing duties to the oncoming EC.

NOTE

¶2 New notification forms shall be completed for all updates.

17. ¶15 If State / Local notification has not been completed in the last 60 minutes, Then provide a routine update utilizing a new notification form. The DCS may be utilized as a phonetalker. (Repeat as necessary)

I I

I

REVISION NO.' PROCEDURE TITLE. PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 18 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.3 Alert Declaration Checklist (continued) TIME / INITIAL

18. If the event can be terminated, Then complete the notification forms (State, NRC) and notify the following: (this may be accomplished by the DCS)

State Warning Point (SWP) I I

Plant Management I

Security I

NDDO I

NRC

19. ALERT Declaration Checklist complete (emergency upgraded or I event terminated).

END OF SECTION 5.3

REVISION NO.: PROCEDURE TITLE: PAGE*

10 DUTIES AND RESPONSIBILITIES OF THE 19 of 36 PROCEDURE NO' EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.4 Site Area Emergency Declaration Checklist TIME / INITIAL Date: / /

CAUTION Notification to the State Warning Point (SWP) shall occur within 15 minutes of declaration of the emergency classification.

NOTE

Steps should be performed in the order presented. When conditions warrant, steps may be performed out of sequence.

Steps with an asterisk are NOT applicable in the TSC. 0 0

The DSC is available in the Control Room only.

05

All Gai-tronics alarms and announcements require Control Room assistance.

PA announcements are provided as a guideline. Actual announcements may vary from the text provided.

For assistance will exposure control, refer to:

"* Attachment 4, Field Operator Re-entry Guidelines

"* Attachment 5, Exposure Limits for Emergency Response Personnel

Not Applicable (N/A) may be used for tasks / steps previously accomplished / satisfied.

Determine the following:

A. Shift Technical Advisor (STA) present Y/N

, B. Duty Call Supervisor (DCS) present Y/N 0

C. Wind direction (from)

REVISION NO.: PROCEDURE TITLE: PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 20 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.4 Site Area Emergency Declaration Checklist (continued) TIME / INITIAL

1. (continued)

NOTE During any declared emergency, a release is occurring if one of the following is true:

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

OR

" Health Physics detecting airborne radioactivity levels in excess of 25 percent Derived Air Concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

D. Release in progress Y/N

E. E-Plan Alarm sounded and Emergency Response Facilities (ERFs) activated Y/N F. Site evacuated Y/N G. Site accountability Not Requested / In Progress / Complete

2. Mobilize emergency team personnel (i.e., Fire Team, First Aid Team) as required using Gai-tronics and boost function. /

3. The NPS shall declare the emergency to the facility staff and, as necessary, formally announce that he / she is the / 0 Emergency Coordinator.

4. ¶12 If a release of radioactive material is in progress, Then review personnel access with Health Physics personnel and

/

notify Security personnel with any special instructions.

5. 1113 Sound the Emergency Plan (E-Plan) Activation Alarm. (N/A /

if already preformed)

REVISION NO.: PROCEDURE TITLE: PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 21 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.4 Site Area Emergency Declaration Checklist (continued) TIME I INITIAL

6. Notify plant personnel using Gai-tronics and boost function as follows: (N/A if facilities already activated)

"Attention all plant personnel, Unit 1 / 2 has declared a SITE AREA EMERGENCY. All emergency response personnel report at once to your assigned emergency response facility."

Repeat the announcement.

7. Notify the Shift Technical Advisor and the Duty Call Supervisor to report to the Control Room using Gai-tronics and boost function.

(N/A if already performed)

"Shift Technical Advisor report to the Unit 1 / 2 Control Room."

"Duty Call Supervisor report to the Unit 1 / 2 Control Room."

REVISION NO.: PROCEDURE TITLE PAGE' 10 DUTIES AND RESPONSIBILITIES OF THE 22 of 36 PROCEDURE NO' EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.4 Site Area Emergency Declaration Checklist (continued) TIME / INITIAL NOTE Site Evacuation Guidance No release of radioactive material - send personnel home.

Current or prior release of radioactive material send personnel to the off-site assembly area.

"* North to Jaycee Park if wind is from 2710 through 1450 (clock-wise direction)

"* South to Jensen Public Beach Parking Area if wind is from 1460 through 2700 (clock-wise direction)

8. Sound the Site Evacuation Alarm. (N/A if already performed) /

9. Notify plant personnel using Gai-tronics and boost function as follows: (N/A if already performed)

"Attention all non-emergency response plant personnel, you are directed to commence evacuation of the Owner Controlled Area, report to your vehicles and (Choose one):

Proceed to your homes.

OR Proceed North / South away form the plant to Jaycee Park / Jensen Public Beach Parkinq Area for contamination check, accountability and further instructions."

Repeat the announcement. I

10. Initiate the call-out process in accordance with EPIP-03, Emergency Response Organization Notification / Staff Augmentation. (this may be accomplished by the DCS) (N/A if already performed)

I CD

11. ¶6 If a release of radioactive material has occurred or is in progress, Then notify Chemistry to promptly implement EPIP-09, Off-site Dose Calculations, and report the results to the Emergency Coordinator (EC). I

REVISION NO: PROCEDURE TITLE: PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 23 of 36 PROCEDURE NO.' EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.4 Site Area Emergency Declaration Checklist (continued) TIME / INITIAL

12. If a Chemist is unavailable, Then call-out a Chemist (this may be accomplished by the DCS).

13. ¶15 Complete required notifications in accordance with Appendix A, Notifications from the Affected Control Room, in EPIP-08, Off-site Notifications and Protective Action Recommendations. The DCS may be utilized as a phonetalker. CD State Warning Point /

NRC /

14. Ensure notification of the following: (this may be accomplished by the DCS)

Plant Management /

Security /

Nuclear Division Duty Officer (NDDO) I

15. Initiate the Operations Department Accountability Aid for both Unit 1 and Unit 2 and provide this list to the TSC when requested.

(this may be accomplished by the DCS) (N/A if already performed)

16. ¶9 Ensure Operations field personnel return to their assigned Control Room and obtain emergency Electronic Personal Dosimetry (EPD) from the HP Emergency Kit. (N/A if already performed) /

17. ¶8 Direct all Non-licensed Operators (NLOs), from both Units to report to the OSC (when operational) following evacuation of the Owner Controlled Area and completion of immediate Operator actions.

18. Verify with Security that the evacuation of the Owner Controlled Area has been completed and all personnel have been accounted for.

REVISION NO PROCEDURE TITLE: PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE PROCEDURE NO EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.4 Site Area Emergency Declaration Checklist (continued) TIME / INITIAL

19. Notify off-site agencies when evacuation is complete: (N/A if already performed)

State Warning Point /

/

NRC

20. Utilize Attachment 3, Turnover Guidelines when relinquishing /

duties to the oncoming EC.

NOTE

¶2 New notification forms shall be completed for all updates.

21. ¶15 If State / Local notification has not been completed in the last 60 minutes, Then provide a routine update utilizing a new notification form. The DCS may be utilized as a phonetalker. (Repeat as necessary) /

I

/

I

22. Turnover off-site interface responsibilities (notifications and Protective Action Recommendations (PARs)) to the Recovery Manager (RM) when the EOF goes operational. /

23. At the direction of the RM, coordinate termination of the I emergency and initiation of recovery planning.

24. SITE AREA EMERGENCY Declaration Checklist complete /

(emergency upgraded or event terminated).

END OF SECTION 5.4

REVISION NO.: PROCEDURE TITLE. PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 25 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.5 General Emergency Declaration Checklist TIME / INITIAL Date: / /

CAUTION

Protective Action Recommendations (PARs) are required for a General Emergency.

Notification to the State Warning Point (SWP) shall occur within 15 minutes of declaration of the emergency classification.

NOTE

Steps should be performed in the order presented. When conditions warrant, steps may be performed out of sequence.

Steps with an asterisk are NOT applicable in the TSC. 0 0

The DSC is available in the Control Room only.

All Gai-tronics alarms and announcements require Control Room assistance.

PA announcements are provided as a guideline. Actual announcements may vary from the text provided.

For assistance will exposure control, refer to:

"* Attachment 4, Field Operator Re-entry Guidelines

"* Attachment 5, Exposure Limits for Emergency Response Personnel

Not Applicable (N/A) may be used for tasks / steps previously accomplished / satisfied.

1. Determine the following:

A. Shift Technical Advisor (STA) present Y/N

B. Duty Call Supervisor (DCS) present Y/N 0

C. Wind direction (from)

REVISION NO.: PROCEDURE TITLE: PAGE.

10 DUTIES AND RESPONSIBILITIES OF THE 26 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.5 General Emergency Declaration Checklist (continued) TIME / INITIAL

1. (continued)

NOTE During any declared emergency a release is occurring if one of the following is true:

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

OR

" Health Physics detecting airborne radioactivity levels in excess of 25 percent Derived Air Concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

D. Release in progress Y/N

E. E-Plan Alarm sounded and Emergency Response Facilities (ERFs) activated Y/N F. Site Evacuation Alarm sounded and site evacuated Y/N G. Site accountability Not Requested / In Progress / Complete

2. Mobilize emergency team personnel (i.e., Fire Team, First Aid Team) as required using Gai-tronics and boost function. I

3. The NPS shall declare the emergency to the facility staff and, as necessary, formally announce that he / she is the Emergency Coordinator. I 0

4. ¶12 If a radioactive release is in progress, Then review personnel access with Health Physics personnel and notify Security personnel with any special instructions. I

5. ¶13 Sound the Emergency Plan (E-Plan) Activation Alarm.

(N/A if already preformed) I

REVISION NO.: PROCEDURE TITLE PAGE*

10 DUTIES AND RESPONSIBILITIES OF THE 27 of 36 PROCEDURE NO' EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.5 General Emergency Declaration Checklist (continued) TIME I INITIAL

6. Notify plant personnel using Gai-tronics and boost function as follows: (N/A if facilities already activated)

"Attention all plant personnel, Unit 1 / 2 has declared a GENERAL EMERGENCY. All emergency response personnel report at once to your assigned emergency response facility."

Repeat the announcement.

7. Notify the Shift Technical Advisor and the Duty Call Supervisor to report to the Control Room using Gai-tronics and boost function.

(N/A if already performed)

"Shift Technical Advisor report to the Unit 1 / 2 Control Room."

"Duty Call Supervisor report to the Unit 1 / 2 Control Room."

NOTE Site Evacuation Guidance No release of radioactive material - send personnel home.

Current or prior release of radioactive material send personnel to the off-site assembly area.

"* North to Jaycee Park if wind is from 271 0 through 1450 (clock-wise direction)

"* South to Jensen Public Beach Parking Area if wind is from 1460 through 2700 (clock-wise direction)

8. Sound the Site Evacuation Alarm. (N/A if already performed) /

REVISION NO' PROCEDURE TITLE: PAGE.

10 DUTIES AND RESPONSIBILITIES OF THE 28 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.5 General Emergency Declaration Checklist (continued) TIME / INITIAL

9. Notify plant personnel using Gai-tronics and boost function as follows: (N/A if site evacuated)

"Attention all plant personnel, Unit 1 / 2 has declare a GENERAL EMERGENCY, all non-emergency response plant personnel are directed to commence evacuation of the Owner Controlled Area, report to your vehicles and (Choose one):

Proceed to your homes.

OR Proceed North / South away form the plant to Jaycee Park / Jensen Public Beach Parkinq Area for contamination check, accountability and further instructions."

Repeat the announcement.

10. If a GENERAL EMERGENCY plant announcement has not been made, Then notify plant personnel using Gai-tronics and boost function:

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

Repeat the announcement.

11. Initiate the call-out process in accordance with EPIP-03, Emergency Response Organization Notification / Staff Augmentation. (this may be accomplished by the DCS) (N/A if already performed)

12. 16 If a radioactive release has occurred or is in progress, Then notify Chemistry to promptly implement EPIP-09, Off-site Dose Calculations, and report the results to the Emergency Coordinator (EC).

13. If a Chemist is unavailable, Then call-out a Chemist (this may be accomplished by the DCS).

REVISION NO' PROCEDURE TITLE: PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 29 of 36 PROCEDURE NO.: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT 5.5 General Emergency Declaration Checklist (continued) TIME / INITIAL

14. Complete required notifications in accordance with Appendix A, Notifications from the Affected Control Room, in EPIP-08, Off-site Notifications and Protective Action Recommendations. The DCS may be utilized as a phonetalker.

State Warning Point /

NRC /

15. Ensure notification of the following: (this may be accomplished by the DCS)

Plant Management /

Security /

Nuclear Division Duty Officer (NDDO) /

16. Initiate the Operations Department Accountability Aid for both Unit 1 and Unit 2 and provide this list to the TSC when requested.

(this may be accomplished by the DCS) (N/A if already performed)

17. T9 Ensure Operations field personnel return to their assigned Control Room and obtain emergency Electronic Personal Dosimetry (EPD) from the HP Emergency Kit. (N/A if already performed)

18. ¶8 Direct all Non-licensed Operators (NLOs), from both Units to report to the OSC (when operational) following evacuation of the Owner Controlled Area and completion of immediate Operator actions. (N/A if already performed)

19. Verify with Security that the evacuation of the Owner Controlled Area has been completed and all personnel have been accounted for. (N/A if already performed)

20. Notify off-site agencies when evacuation is complete: (N/A if already performed)

State Warning Point /

NRC /

REVISION NO: PROCEDURE TITLE PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 30 of 36 PROCEDURE NO EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT General Emergency Declaration Checklist (continued) TIME / INITIAL 5.5

21. Utilize Attachment 3, Turnover Guidelines when relinquishing duties to the oncoming EC. I NOTE

¶12 New notification forms shall be completed for all updates.

22. 115 If State / Local notification has not been completed in the last 60 minutes, Then provide a routine update utilizing a new notification form. The DCS may be utilized as a phonetalker. (Repeat as necessary) /

/

I

/

23. Turnover off-site interface responsibilities (notifications and Protective Action Recommendations (PARs)) to the Recovery Manager (RM) when the EOF goes operational. /

24. At the direction of the RM, coordinate termination of the /

emergency and initiation of recovery planning.

25. GENERAL EMERGENCY Declaration Checklist complete (event I terminated).

END OF SECTION 5.5

REVISION NO: PROCEDURE TITLE PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 31 of 36 PROCEDURE NO. EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 1 INITIAL NOTIFICATION FLOW (Page 1 of 1)

(1) Via State Hot Ring Down Telephone (HRD)

Legend (2) Via Emergency Notification System (ENS)

-Primary Notification Pathway (3) Medical & Fire Emergencies Only, As Needed

--- Alternate Notification Pathway (4) Via Plant Public Address System (PA)

(DiPSI EPLAN-F12-R35)

END OF ATTACHMENT 1

I- -..-. -

REVISION NO PROCEUK I IU I Lt-.

10 DUTIES AND RESPONSIBILITIES OF THE 32 of 36 PROCEDURE NO.: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 2 CRITERIA FOR EVACUATION (Page 1 of 1)

A. Criteria for Local Evacuation The need for Local Evacuation should 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 10-9 micro Ci/cc.

5. Removable radioactive surface contamination in an unposted area in 2 100 ft 2.

excess of 1000 dpm/100 cm beta-gamma over an area of

6. Removable radioactive surface contamination in an un osted area in 2 alpha over an area of 100 ft.

excess of 50 dpm/1 00cm

7. The Emergency Coordinator determines that a situation exists for which Local Evacuation is appropriate.

B. 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.

C. Refer to EPIP-07, Conduct of Evacuations / Assembly, for more information.

END OF ATTACHMENT 2

REVISION NO.: PROCEDURE TITLE* PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 33 of 36 PROCEDURE NO" EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 3 TURNOVER GUIDELINES (Page 1 of 2)

Upon arrival at the affected Control Room, the prospective Emergency Coordinator should review the following items/issues with the Control Room Emergency Coordinator (not in a particular order):

NOTE This information (1-10 below) should be reviewed with the DCS.

1. Type of accident or incident

2. Plant status

3. Equipment out-of-service

4. Operator actions underway

5. Radiological conditions

6. Meteorological conditions

7. Procedure status

8. Emergency Plan activities underway, including any on-site or off-site protective actions

9. Conditions and/or trends of concern

10. Personnel injuries or radiation exposures For an Alert or higher emergency, complete the following:

1. Prior to leaving Control Room verify the status of the following:

A. Emergency classification B. Off-site notifications

REVISION NO: PROCEDURE TITLE. PAGE 10 DUTIES AND RESPONSIBILITIES OF THE 34 of 36 PROCEDURE NO EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 3 TURNOVER GUIDELINES (Page 2 of 2)

2. Bring the following items to the Technical Support Center:

A. Copy of RCO log (entries from start of the event)

B. Completed notification forms (State and NRC)

C. Operations Accountability Aid (only if completed)

END OF ATTACHMENT 3

PROCEDURE TITLE. PAGE.

REVISION NO:

10 DUTIES AND RESPONSIBILITIES OF THE 35 of 36 PROCEDURE NO EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 4 FIELD OPERATOR RE-ENTRY GUIDELINES (Page 1 of 1)

CAUTION As specified in ADM-17.09, Invoking 10 CFR 50.54(x), the Emergency Coordinator (EC) may (with the concurrence of a licensed senior operator) waive re-entry requirements to place the plant in a safe shutdown condition or mitigate a release, if this immediate action is needed to protect the health and safety of the public.

1. Prior to evacuation and with the Operational Support Center (OSC) NOT operational.

Re-entry guidelines do not apply.

2. Prior to evacuation and with the OSC operational.

%18 Operators in the field should return to the Control Rooms and obtain an Electronic Personal Dosimeter (EPD) from the Health Physics Emergency Kit prior to returning to field.

3. 118 Evacuation ordered and with the OSC NOT operational.

Operator actions in the field must be viewed as re-entry activities. Operators shall return to the Control Rooms following the evacuation order. Operators shall obtain an Electronic Personal Dosimeter (EPD) from the Health Physics Emergency Kit, if not done previously. Re-entry into the plant requires:

A. The EC (initially the NPS) authorize the entry.

B. Maintenance of appropriate radiological and safety measures.

C. Tracking the whereabouts of the team.

4. Evacuation ordered and with the OSC operational A. NLOs, from both Units, are to report to the OSC once it is declared operational.

B. All field activities are re-entries and shall be coordinated and controlled by the OSC.

END OF ATTACHMENT 4

REVISION NO' PROCEDURE TITLE. PAGE:

10 DUTIES AND RESPONSIBILITIES OF THE 36 of 36 PROCEDURE NO: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 5

§1 EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 1 of 1)

NOTE

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.

For the following missions, the exposure limit is(l): Total Dose(2) THYROID(3')

(TEDE) (CDE)

Performance of actions that would not directly mitigate the event, minimize escalation, or minimize effluent releases. 5 REM 50 REM Performance of actions that mitigate the escalation to the event, rescue persons from a non-life threatening situation, minimize exposures or minimize effluent releases. 10 REM 100 REM Performance of actions that decrease the severity of the event or terminate the processes causing the event in an attempt to control effluent releases to avoid extensive exposure of large populations.

Also, rescue of persons from a life-threatening situation. 25 REM 250 REM Rescue of person from a life-threatening situation. (Volunteers(4) should be above the age of 45.) (5) (5)

(1) Exposure limits to the lens of the eye are 3 times the Total Dose (TEDE) values listed.

(2) Total Dose (TEDE) is the total whole body exposure from both external and internal (weighted) sources - Total Effective Dose Equivalent.

(3) 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).

(4) Volunteers 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.

(5) No upper limit for Total Dose (TEDE) and/or Thyroid Dose (CDE) exposure has been established because it is not possible to prejudge the risks that one person should be allowed to take to save the life of another. Also, no specific limit is given for thyroid exposure since in the extreme case, complete thyroid loss might be an 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.

END OF ATTACHMENT 5

Procedure No.

ST. LUCIE PLANT EPIP-03 EMERGENCY PLAN Current Revision No.

IMPLEMENTING PROCEDURE 9 FPL SAFETY RELATED Effective Date 08101102

Title:

EMERGENCY RESPONSE ORGA IZAXtý1PN NOTIFICATION / STAFF AUGME 10 Responsible Department: EMERGENCY PREPAREDNESS ) _

REVISION

SUMMARY

I PROCEDURE PRODUCTION Revision 9 - Clarified duties of DCS as phone talker and changed title revisions. (J. R.

Walker, 07/26/02)

Revision 8A - Changed President, Nuclear Division to Chief Nuclear Officer. (M. DiMarco, 10/22/01)

Revision 8 - Supported elimination of OSC paramedic position and made editorial and administrative changes. (G. Varnes, 08/08/00)

Revision 7 - Increased emphasis on callout process, changed callout sequence, added notes for emphasis, made administrative changes, and added autodialer checklist.

(Donna Calabrese, 04/27/00)

Revision 6 - Removed reference to the rotating maintenance shift supervisor from the definition / description of the duty call supervisor and revised security title from supervisor to specialist. (J. R. Walker, 07/01/99)

Revision 5 - Transferred EP responsibilities from the Training Manager to the Protection Services Manager. Made editorial changes and added new position -regulatory affairs. (J. R.

Walker, 06/17/99)

Revision 4 - Added 2 new positions to call tree to address Security org. and added editorial I administrative changes. (J. R. Walker, 2/23/99)

Revision FRG Review Date Approved By Approval Date S OPS 0 12/15/97, 1/30198 J. Scarola 01/30/98 DATE Plant General Manager DOCT PROCEDURE Revision FRG Review Date Approved By Approval Date DOCN EPIP-03 9 07/25/02 Dick Rose 07/26/02 SYS Plant General Manager COM COMPLETED N/A I ITM 9 Designated Approver N/A Designated Approver (Minor Correction)

REVISION NO.: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 2 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 P U R PO S E .................................................................................................. 3

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS... 3 3.0 RESPO NSIBILITIES ................................................................................... 5 4.0 D EFIN IT IO N S ........................................................................................... 6 5.0 INSTRUCTIO NS ...................................................................................... 7 5.1 Emergency Coordinator (EC) ........................................................... 7 5.2 Duty Call Supervisor (DCS) ............................................................ 8 5.3 ERO Members with Call Tree Duties ............................................. 10 5.4 ERO Members with no call-out duties ........................................... 12 ATTACHMENTS ATTACHMENT 1 EMERGENCY STAFFING CALL TREE .............................. 13 ATTACHMENT 2 FPL EMERGENCY RECALL SYSTEM (ERS) ACTIVATION C HEC KLIST ........................................................................ 24

REVISION NO: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 3 of 25 PROCEDURE NO: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 1.0 PURPOSE II NOTE

§2 The Staff Augmentation process is an essential part of the Emergency Plan in that it puts in place the resources necessary to mitigate an accident and protect the health and safety of the public.

This procedure provides instructions to:

1.1 Activate the St. Lucie Plant Emergency Response Organization (ERO) for staff augmentation in response to an emergency declaration.

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

'T Indicates a step that requires a sign off on an attachment.

2.1 References

1. §1 St. Lucie Plant Radiological Emergency Plan (E-Plan)

2. E-Plan Implementing Procedures (EPIP 00 - 13)

3. HP-200, Health Physics Emergency Organization

4. AP 0010120, Conduct of Operations

5. ADM-1 5.04, Fitness For Duty - Call-Out and For Cause Testing

6. St. Lucie Plant Emergency Response Directory (ERD)

7. QI-17-PSL-1, Quality Assurance Records

REVISION NO* PROCEDURE TITLE PAGE.

9 EMERGENCY RESPONSE ORGANIZATION 4 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 2.2 Records Required

1. None 2.3 Commitment Documents

1. ¶1 Condition Report CR 00-0544 - QA Audit QSL-EP-00-02:

Discrepancies with Primary and Backup ERO CaIlout Processes

2. ¶2 Condition Report CR 02-0333 (Role of Duty Call Supervisor)

REVISION NO.* PROCEDURE TITLE: PAGE 9 EMERGENCY RESPONSE ORGANIZATION 5 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 3.0. RESPONSIBILITIES 3.1 The Emergency Coordinator (EC) has the overall responsibility for the notification and call-out of the ERO as provided for in EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

3.2 The Duty Call Supervisor (DCS)

1. The Duty Call Supervisor reports to the affected Unit Control Room upon declaration of the emergency, If the unaffected Unit ANPS assumes the role of DCS, Then he / she shall fulfill the responsibilities without leaving the unaffected Control Room.

2. Complete the following as directed by the NPS / EC:

A. 112 Transmittal of off-site notifications (EPIP-08).

B. Staff augmentation (per this procedure).

C. Operations Department Accountability Aid.

3. Conduct a turnover with the TSC OPS Coordinator (NPS Communicator in the Control Room) regarding the status of communications and other tasks underway.

3.3 Members of the Emergency Response Organization (ERO):

1. §1 Advise the Protection Services Manager when his / her duties are changed such that he / she can no longer participate in the ERO.

2. Maintain a copy of the ERD readily available 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day (individuals with call-out duties only).

3. Make notifications, as required by their position, when notified by the DCS, in accordance with the instructions contained in the ERD.

4. When notified, report to the assigned Emergency Response Facility (ERF).

3.4 Protection Services Manager

1. §1 Ensure verification of the following for ERO personnel quarterly:

A. Personnel phone / beeper numbers B. Training qualifications in accordance with EPIP-12, Maintaining Emergency Preparedness, Radiological Emergency Plan Training.

PROCEDURE TITLE REVISION NO::

REVISION NO PROCEDURE TITLE*

9 EMERGENCY RESPONSE ORGANIZATION 6 of 25 PROCEDURE NO: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 3.5 ¶i The Emergency Preparedness Supervisor is responsible to ensure that both primary and backup staff augmentation methodologies are adequately maintained. The requirements for maintaining the augmentation methodologies are detailed in EPIP-13, Maintaining Emergency Preparedness - Emergency Exercises, Drills, Tests and Evaluations.

4.0 DEFINITIONS 4.1 Autodialer See FPL Emergency Recall System below.

4.2 §1 Duty Call Supervisor (DCS)

The Duty Call Supervisor is a designated and trained supervisor assigned from the nuclear plant staff to provide 24-hour response to any emergency upon notification by the Nuclear Plant Supervisor. The Duty Call Supervisor (DCS) is responsible for notifying the Emergency Response Organization and, as requested, plant management in the event of an emergency.

4.3 Emergency Response Organization (ERO)

A trained group of personnel that are designated to perform specific duties during emergencies.

4.4 St. Lucie Plant Emergency Response Directory (ERD)

A printed directory which provides guidance for performing a call-out of the Emergency Response Organization. The ERD contains the names, positions, home phone numbers, and pager numbers for the members of the ERO.

4.5 FPL Emergency Recall System (ERS)

A computer-based automated call-out system used to activate the ERO. This system is also referred to as the "autodialer".

PROCEDURE TITLE: PAGE:

REVISION NO:

9 EMERGENCY RESPONSE ORGANIZATION 7 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 Emergency Coordinator (EC)

1. Instructions for the EC are located in EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

END OF SECTION 5.1

REVISION NO.: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 8 of 25 PROCEDURE NO: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 5.2 Duty Call Supervisor (DCS)

1. As directed by the EC, initiate call-out of ERO members using Attachment 2, FPL Emergency Recall System (ERS) Activation Checklist.

NOTE Instructions for activation of the autodialer are located in the Duty Call Supervisor Notebook which is maintained in accordance with Appendix E to AP-0010120, Conduct of Operations.

2. If during normal working hours, Then activate autodialer only.

A. Do NOT call-out ERO members using the ERD.

3. If during off normal working hours, Then begin call-out of ERO members, as detailed in the ERD, after initiating the autodialer.

A. Notify Security Shift Specialist AND HP Shift Supervisor / On-shift Tech by plant radio or other prompt means.

B. Notify each of the following positions by cell / page / radio:

1. Emergency Coordinator

2. Recovery Manager

3. Nuclear Division Duty Officer C. If autodialer has NOT activated, Then continue to notify the following:

1. TSC Chemistry Supervisor

2. TSC EP Coordinator

3. EP Manager

4. EOF Emergency Technical Manager

5. TSC Coordinator with OSC.

NOTE Read and review Steps 5.2.3.D.1 - 5.2.3.D.5 below and mark appropriately for an actual emergency call-out drill or phone test prior to making the first call.

D. When the responder answers, CLEARLY STATE THE FOLLOWING:

1. This is (your name), functioning as Duty Call Supervisor.

REVISION NO.: PROCEDURE TITLE PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 9 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 5.2 Duty Call Supervisor (DCS) (continued)

3. D. (continued)

2. This is an / a (actual emergency / call-out drill / phone test) message.

3. St. Lucie Plant has declared an / a (ALERT / SITE AREA EMERGENCY I GENERAL EMERGENCY) OR is conducting a (call-out drill I phone test).

4. 1am calling you for the position of (state position from Step 5.2.3 above).

a. Are you fit for duty and able to respond?

(If YES: record name on call-out list and continue with questions).

(If NO: Terminate the call and go to next person for the position.)

b. What is your estimated drive time to your emergency response facility?

(Record estimated arrival time under ETA on call-out list).

5. Promptly complete your call tree section if applicable and report to your emergency response facility.

OR This is a phone test only, DO NOT report to your emergency response facility after completing your calls.

E. If autodialer activation is indicated, Then NOTIFY Security Shift Specialist and HP Shift Supervisor / On-shift Tech to suspend call out.

END OF SECTION 5.2

REVISION NO.: PROCEDURE TITLE' PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 10 of 25 PROCEDURE NO: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 5.3 ERO Members with Call Tree Duties

1. Maintain a current copy of the ERD for use at all times.

2. Perform manual call-outs as instructed by the DCS and ERD.

A. Begin at the top of your call list and proceed down the list until either:

An individual is contacted to fill each position OR All positions have been attempted once.

NOTE Read and review Steps 5.3.2.B.1 - 5.3.2.B.5 below and mark appropriately for an actual emergency, a call-out drill or phone test prior to making the first call.

B. When the responder answers, CLEARLY STATE THE FOLLOWING:

1. This is (your name), functioning as (ERO position title).

2. This is an / a (actual emergency / call-out drill / phone test) message.

3. St. Lucie Plant has declared an / a (ALERT / SITE AREA EMERGENCY I GENERAL EMERGENCY) OR is conducting a (call-out drill I phone test).

4. I am calling you for the position of (state position from ERD Call-out Phone List).

a. Are you fit for duty and able to respond?

(If YES: check name on call-out list and continue with questions).

(If NO: Terminate the call and go to next person for the position.)

b. What is your estimated drive time to your emergency response facility?

(Record estimated arrival time under ETA on call-out list).

REVISION NO: PROCEDURE TITLE' PAGE 9 EMERGENCY RESPONSE ORGANIZATION 11 of 25 PROCEDURE NO: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 5.3 ERO Members with Call Tree Duties (continued)

2. B. (continued)

5. Promptly report to your emergency facility.

OR This is a phone test only, DO NOT report to your emergency response facility.

C. Report to assigned emergency response facility upon completion of call-outs and furnish call-out data to facility manager.

If consumed alcohol in the past 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , Then report to Security prior to entering the site or EOF.

END OF SECTION 5.3

REVISION NO: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 12 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT 5.4 ERO Members with no call-out duties Report at once to your assigned emergency response facility.

If consumed alcohol in the past 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , Then report to Security prior to entering the site or EOF.

END OF SECTION 5.4

REVISION NO.: PROCEDURE TITLE: PAGE.

9 EMERGENCY RESPONSE ORGANIZATION 13 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY STAFFING CALL TREE (Page 1 of 11)

DUTY CALL SUPERVISOR (P1PFPIP-33/Att I I-RO)

REVISION NO: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 14 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT I EMERGENCY STAFFING CALL TREE (Page 2 of 11)

SECURITY OFFICER #1 TSC MECHANICAL REP - PST (3)*

TSC REACTOR ENGINEER*

I SECURITY OFFICER #1 TSC OPS COORDINATOR (2)

TSC SECURITY SUPERVISOR

MINIMUM STAFFING POSITION OR FIRST LINE ALTERNATE TO MINIMUM STAFFING POSITION (P/PSEPIP-"3/At 1.2-RO)

REVISION NO.: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 15 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY STAFFING CALL TREE (Page 3 of 11)

SECURITY OFFICER #2 MINIMUM STAFFING POSITION OR FIRST LINE ALTERNATE TO MINIMUM STAFFING POSITION (P/PSIEPIP-O3/AtI I 3-RO)

PROCEDURE TITLE:

REVISION NO::

REVISION NO PROCEDURE TITLE:

9 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT I EMERGENCY STAFFING CALL TREE (Page 4 of 11)

SECURITY OFFICER #3

_____-OSC SUPER VISORY/

MANAGER i

MANAGER OSC MECH OSC SUPERVISOR*!

. REENTRY SUPV

OSC I&C REENTRY SUPV

OSC ELEC REENTRY SUPV

OSC COORDINATOR WITH TSC OSC OPS REENTRY SUPV SECURITY OFFICER# 3 OSC SAFETY REP OSC ADMIN TECHI LOGKEEPER (2)

OSC PROTECTION

& CONTROL REP I OSC NMM STAFF REP OSC INFORMATION SERVICES REP ASSEMBLY AREA SUPERVISOR

MINIMUM STAFFING POSITION OR FIRST LINE ALTERNATE (p/PS1EPIP-O3Att I 4-RI)

TO MINIMUM STAFFING POSITION

REVISION NO.: PROCEDURE TITLE: PAGE' 9 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.: NOTIFICATION I STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY STAFFING CALL TREE (Page 5 of 11)

SECURITY OFFICER #4 EOF RM OPS ADVISOR/LOGKPR (2)*

EOF EOF HEALTH PHYSICS MANAGER MANAGER 'I PHYSICS EOF HEALTH SECURITY OFFICER# 4 EOF ERDADS OPERATOR

EOFDOSE ASSESSOR/FMT COORD. (3)

EOF EMERGENCY SECURITY MANAGER MINIMUM STAFFING POSITION OR FIRST LINE ALTERNATE TO MINIMUM STAFFING POSITION (PIPSIEPIP-O3/Afl I f-RO)

PROCEDURE TITLE: PAGE.

REVISION NO.:

9 EMERGENCY RESPONSE ORGANIZATION 18 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY STAFFING CALL TREE (Page 6 of 11)

NUCLEAR DIVISION DUTY OFFICER REGULATORY AFFAIRS RISK MANAGER (PPS/EPIP-O3IAttI 6-R1)

Co

I.

PROCEDURE TITLE:

REVISION NO.:

REVISION NO.: PROCEDURE TITLE:

9 EMERGENCY RESPONSE ORGANIZATION PROCEDURE NO.. NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT

____________________________ L ATTACHMENT I EMERGENCY STAFFING CALL TREE (Page 7 of 11)

TSC EP COORDINATOR (PiPSIEPIP-03/Att I 7-RO)

REVISION NO.: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 20 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT I EMERGENCY STAFFING CALL TREE (Page 8 of 11)

EP MANAGER EOF NUCLEAR LICENSING MANAGER EOF RAD STATUS BOARDS KEEPER EP MANAGER EOF HP TECH SUPPORT EOF ADMIN SUPERVISOR EOF ADMIN STAFF (3)

(PIPS/EPIP-O3/Att1 8-RO)

REVISION NO.: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 21 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT I EMERGENCY STAFFING CALL TREE (Page 9 of 11)

EOF EMERGENCY TECHNICAL MANAGER EOF EMERGENCY TECHNICAL MANAGER EOFNUCLEAR FUELS ENGINEER EOFNUCLEAR EOF CIVIL ENGINEER ENGINEER EOFSTATUS BOARD KEEPER (P/PS/EPIP-O3IAtt1 9-RO)

PROCEDURE TITLE. PAGE:

REVISION NO.:

9 EMERGENCY RESPONSE ORGANIZATION 22 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT I EMERGENCY STAFFING CALL TREE (Page 10 of 11)

Emergency Response Organization Positions List Position Title Position Title 100 Duty Call Supervisor 161 OSC Electrician (3) 101 Emergency Coordinator 162 OSC Mechanic (3) 102 TSC Supervisor 163 OSC I&C Specialist (3) 103 TSC HP Supervisor 166 OSC Dosimetry Technician 104 TSC Chemistry Supervisor 105 TSC Reactor Engineer 168 OSC Mechanical Foreman 106 TSC Communicator (3) 169 OSC NMM Staff Rep 107 TSC Elec Rep - Problem Solving Tm 170 OSC Safety Rep 108 TSC Mech Rep - Problem Solving Tm (3) 171 OSC Admin Tech / Logkeeper (2) 109* HP Shift Supervisor / On Shift Tech 172 Assembly Area Supervisor 110 TSC Ops Coordinator (2) 173 OSC Ops Reentry Supervisor 111 TSC Dose Assessor 174 OSC Protection and Control Rep 112 TSC HP Communicator (2) 175 OSC I&C Shop Supervisor 113 TSC SP Phonetalker (2) 176 Field Monitoring Team Driver (3) 114 TSC ERDADS Operator 177 OSC Information Services Rep 115 TSC Problem Solving Team Leader 180* Security Shift Specialist 116 TSC ERDADS Tech 181* Security Officer (4) 117 TSC I&C Rep - Problem Solving Tm 200 Recovery Manager 118 TSC SRO Rep - Problem Solving Tm 204 Risk Manager 119 TSC Security Supervisor 205 Governmental Affairs Manager 120 TSC Coordinator with OSC 209 EOF RM Ops Advisor / Lojkeeper (2) 121 TSC Administrative Staff (2) 213 EOF ERDADS Operator 122 TSC EP Coordinator 216 EOF Status Board Keeper 124 TSC EC Assistant I Logkeeper 230 EOF Emergency Technical Manager 151 OSC HP Tech (ALL) 231 EOF Project Engineer 152 OSC Electrical Reentry Supervisor 232 EOF Mechanical Engineer (2) 153 OSC I&C Reentry Supervisor 233 EOF Nuclear Engineer 154 OSC Mechanical Reentry Supervisor 235 EOF Nuclear Fuels Engineer 155 OSC Chemistry Supervisor 236 EOF Civil Engineer 156 OSC Electrical Chief 237 EOF I&C Engineer 157 OSC Supervisor / Manager 238 EOF Electrical Engineer (0 158 OSC Coordinator with TSC 240 EOF Health Physics Manager 159 OSC HP Supervisor 245 EOF Dose Assessor/ FMT Coord. (3) 160 OSC Chemist (3) 246 EOF HP Tech Support

Not ERO positions, but are needed to ensure automated call-out logic will function properly.

-I PROCEDURE TITLE: PAGE' REVISION NO.:

9 EMERGENCY RESPONSE ORGANIZATION 23 of 25 PROCEDURE NO: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY STAFFING CALL TREE (Page 11 of 11)

Emergency Response Organization Positions List Position Title Position Title 247 EOF Rad Status Boards Keeper 279 Regulatory Affairs 250 EOF Nuclear Licensing Manager 280 EOF Administrative Supervisor 255 EOF Communicator (4) 281 EOF Administrative Staff (3) 260 EOF Emergency Security Manager 290 EP Manager 270 EOF Emergency Information Manager 291 Governor's Advisor 271 Nuclear Division Duty Officer 294 St. Lucie County Technical Advisor 273 ElM / ENC Technical Advisor (2) 295 Martin County Technical Advisor 275 Governmental Affairs Assistant 300 Emergency Control Officer 276 Gov Affairs Rep (Tallahassee) 301 Chief Nuclear Officer 278 Aviator I I END OF ATTACHMENT 1

REVISION NO.: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 24 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT 2 FPL EMERGENCY RECALL SYSTEM (ERS) ACTIVATION CHECKLIST (Page 1 of 2)

Name:

I !*I I Unit:_

Date: _L /I_ Time:

Prior to making the call, determine the appropriate scenario to activate. Use scenario 30 during normal working hours, or use scenario 50 for an off-hours activation. You will be requested to enter the two digit scenario number during the call.

Scenario to be used:

NOTE When you call, enter the password (refer to the DCS Notebook) as soon as the system answers and begins talking. If you wait until the message is complete, you will not be able to connect to the system.

2. Call the Emergency Recall System at 8-694-4200 or 8-1-561-694-4200.

3. Enter the password as soon as the system answers.

Unit I - Refer to DCS Notebook Unit 2 - Refer to DCS Notebook WHEN THE SYSTEM STATES... YOU SHOULD ENTER... Circle One "Enter the scenario number you want to 30 - normal working hours work with" 50 - off-hours "That scenario is completed. Do you want 9 - to confirm the scenario to que it? Please press 9 for yes or 6 for 6 - to cancel no."

"Enter scenario status. Press 1 for I - for an emergency activation emergency, 2 for response drill, or 3 for 2 - to run a response drill, having telephone test." personnel respond to the facilities 3 - for a telephone test only, with no I_ response to the facilities

REVISION NO.: PROCEDURE TITLE: PAGE:

9 EMERGENCY RESPONSE ORGANIZATION 25 of 25 PROCEDURE NO.: NOTIFICATION / STAFF AUGMENTATION EPIP-03 ST. LUCIE PLANT ATTACHMENT 2 FPL EMERGENCY RECALL SYSTEM (ERS) ACTIVATION CHECKLIST (Page 2 of 2)

WHEN THE SYSTEM STATES (cont.) YOU SHOULD ENTER (cont.) Circle One "To record a custom message, enter **- This is an optional message. If you choose star, star (**), then record. To end to use it, you should make a single statement recording, hit star again. If you have no regarding the status of the emergency. Example:

information available or do not wish to "Alert based on greater than 50 gallon per minute record a message, enter zero, zero Reactor Coolant System leak."

followed by the pound (#) symbol." If a significant radiological release could affect site access, a message should be recorded similar to: "Enter the plant from the (north /

south)."

00# - no message "You have entered the following 9 - to confirm emergency message... _, which 6 - to cancel states _.... .Is that correct?

Press 9 for yes or 6 for no."

"Enter a 911 event code if it's an actual 911 - actual emergency activation emergency, an 811 event code for a 811 - for a response drill response drill, or a 711 event code for a 711 - for a telephone test telephone."

"You entered . Is that correct? 9 - to confirm Press 9 for yes or 6 for no." 6 - to cancel "At the end of this step you have chosen 9 - to activate the autodialer to start scenario - as a . Are 6 - to cancel and hang up you certain this is what you want to do?

Please press 9 for yes, 6 for no."

4. Initiate the manual call-out process in accordance with EPIP-03, Emergency Response Organization Notification / Staff Augmentation.

5. To verify that the system has activated, use one of the following:

- report received on the telecopy machine in either Control Room, or

- report of appropriate pager activation from any Emergency Response Organization member.

6. If verification is not received within 10 minutes, Then continue the manual call-out in accordance with EPIP-03.

END OF ATTACHMENT 2

Procedure No.

ST. LUCIE PLANT EPIP-04 EMERGENCY PLAN Current Revision No.

IMPLEMENTING PROCEDURE 10 FPL SAFETY RELATED Effective Date 08101102

Title:

ACTIVATION AND OPERATION F-T-I TECHNICAL SUPPORT CEN f z

Responsible Department: EMERGENCY PREPAREDNESS 0C REVISION

SUMMARY

PODUCTIONNPROC Revision 10 - Referenced EPIP-08 for act. notif. methods. Deleted duplicate information.

Clarified instructions for using commercial phone. Deleted priority requirements. Added EC review/approval to Attachment A. Added SRO approval for 50.54(x) on Attachment 12B.

Made editorial/administrative changes. (J. R. Walker, 07/18/02)

Revision 9 - Updated instructions for obtaining EPIP list on Lotus Notes. Added instructions for establishing/terminating the videolink. Added back EC sign-off to Attachment 12B, inadvertently removed in last revision. Added information on where to get ERO link password.

(J. R. Walker, 10/11/01)

Revision 8 - Reduced paperwork required to request re-entry teams, streamlined re-entry, and streamlined problem solving team paperwork. (Donna Calabrese, 04/26/01)

Revision 7 - Revised mandatory functions to include classification and PARs, removed references to STA, revised responsibilities of the TSC EC Assist/Logkeeper and TSC Chemistry Supervisor, and made editorial and administrative changes. (J. R. Walker, 12/07/00)

Revision 6 - Changed responsibility for filling in the State Notification Form from the TSC HRD Communication to the TSC EC Assist/Logkeeper. Made editorial and administrative changes. Revised TSC briefing guidance lAW CR 00-0429. Added new PST Tracking form.

(Donna Calabrese, 05/31/00)

I Revision FRG Review Date Approved By Approval Date S OPS 0 12/15/97 J. Scarola 12/15/97 DATE Plant General Manager DOCT PROCEDURE Revision FRG Review Date Approved By Approval Date DOCN EPIP-04 10 07/18/02 D. Rose 07/18/02 SYS Plant General Manager COM COMPLETED N/A ITM 10 Designated Approver N/A Designated Approver (Minor Correction)

REVISION NO: PROCEDURE TITLE PAGE.

10 ACTIVATION AND OPERATION OF THE 2 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ...................................................................................................... 4

2.0 REFERENCES

/ RECORDS REQUIRED I COMMITMENT DOCUMENTS ....... 6 3.0 RESPONSIBILITIES ....................................................................................... I".. 8 4.0 DEFINITIONS ............................................................................................... 10 5.0 INSTRUCTIONS ........................................................................................... 11 ATTACHMENTS ATTACHMENT 1 TSC EMERGENCY RESPONSE ORGANIZATION AND SHIFT STAFFING ............................................................. 13 ATTACHMENT 2 TSC EC ASSIST / LOGKEEPER CHECKLIST ................. 14 ATTACHMENT 2A TYPICAL INFORMATION TO BE INCLUDED IN THE EC LO G BO O K ....................................................................... 16 ATTACHMENT 3 TSC SUPERVISOR CHECKLIST ..................................... 17 ATTACHMENT 3A TSC ERO SHIFT STAFFING AND ACCOUNTABILITY RO STER .......................................................................... 21 ATTACHMENT 3B TSC MINIMUM STAFFING REQUIREMENTS .................. 22 ATTACHMENT 3C TSC FACILITY BRIEFINGS ............................................. 23 ATTACHMENT 3D GUIDELINES FOR RELOCATION OF THE TSC .............. 25 ATTACHMENT 4 TSC COMMUNICATOR CHECKLIST .............................. 28 ATTACHMENT 4A COMMUNICATIONS GUIDELINES .................................. 32 ATTACHMENT 4B SAFETY FUNCTIONS EQUIPMENT STATUS - UNIT 1 ....... 37

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10 ACTIVATION AND OPERATION OF THE 3 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT TABLE OF CONTENTS (continued)

SECTION PAGE ATTACHMENTS (continued)

ATTACHMENT 5 TSC ERDADS OPERATOR CHECKLIST. .41 ATTACHMENT 5A ERDADS DATA ACQUISITION ......................................... 43 ATTACHMENT 5B ERDADS DATA POINTS ................................................. 46 ATTACHMENT 6 TSC ADMINISTRATIVE STAFF CHECKLIST ................... 54 ATTACHMENT 7 TSC COORDINATOR WITH OSC CHECKLIST ............... 58 ATTACHMENT 7A RE-ENTRY LOG .............................................................. 59 ATTACHMENT 8 TSC OPS COORDINATOR CHECKLIST .......................... 60 ATTACHMENT 9 TSC REACTOR ENGINEER CHECKLIST ........................ 64 ATTACHMENT 9A INITIATING AND TERMINATING THE ERDS LINK ...... 67 ATTACHMENT 10 TSC CHEMISTRY SUPERVISOR CHECKLIST ................ 69 ATTACHMENT 11 TSC DOSE ASSESSOR CHECKLIST .............................. 72 ATTACHMENT 11A OFF-SITE RADIOLOGICAL ASSESSMENT ..................... 74 ATTACHMENT 11B PROTECTIVE ACTION RECOMMENDATIONS ............... 75 ATTACHMENT 12 TSC PROBLEM SOLVING TEAM CHECKLIST ................ 76 ATTACHMENT 12A PST ACTIVITIES LIST ...................................................... 78 ATTACHMENT 12B PROBLEM SOLVING TEAM WORKSHEET ..................... 79 ATTACHMENT 13 TSC SECURITY SUPERVISOR CHECKLIST ................... 80

REVISION NO: PROCEDURE TITLE: PAGE.

10 ACTIVATION AND OPERATION OF THE 4 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT 1.0 PURPOSE 1.1 Discussion This procedure provides instructions for the activation and operation of the Technical Support Center (TSC).

1.2 Location and Description The TSC is on the 62 foot elevation of the Unit 1 Reactor Auxiliary Building (RAB). The TSC is located adjacent to the Unit 1 Control Room and is enclosed in the same habitability envelope. The TSC has emergency communications equipment, precalculated emergency data, pertinent reports, plans, procedures and drawings available for use. Should the Unit 1 Control Room envelope require evacuation, alternate locations for the TSC have been identified as follows:

1. South Service Building

2. Nuclear Training Center 1.3 TSC Functions

1. Mandatory Functions A. Classification of emergencies in accordance with EPIP-01, Classification of Emergencies.

NOTE The following tasks become the responsibility of the Emergency Operations Facility (EOF) when manned and fully operational.

B. Relief to the Control Room for off-site communications to the State and local agencies and the NRC in accordance with EPIP-08, Off-site Notifications and Protective Action Recommendations.

C. Performance of off-site dose calculations in accordance with EPIP-09, Off-site Dose Calculations, or the Class A computer model.

D. Protective Action Recommendations (PARs) in accordance with EPIP-08.

REVISION NO.: PROCEDURE TITLE' PAGE:

10 ACTIVATION AND OPERATION OF THE 5 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT 1.3 TSC Functions (continued)

2. Additional Functions A. Management of emergency mitigation activities.

B. Technical support in determining current and projected plant status and providing in-depth diagnostic and engineering assistance to the Control Room.

C. Direct the re-entry activities of the Operational Support Center (OSC).

D. Coordination with the Emergency Operations Facility (EOF) regarding emergency status, corrective and protective actions, off site interface, radiological conditions, core damage assessment, etc.

1.4 Minimum Staffing

1. The following is the list of the minimum positions needed for TSC operation:

- Emergency Coordinator

- TSC Supervisor

- TSC Dose Assessor

- TSC Reactor Engineer

- TSC Elec Rep - PST (Problem Solving Team)

- TSC Mech Rep - PST

- (3) TSC Communicator (HRD, ENS, EOF) 1.5 §2 Activation Activation of the TSC is the responsibility of the Emergency Coordinator (EC) and is required for an Alert or higher declared emergency. Arrangements have been made to staff the TSC in a timely manner.

1.6 Operations The TSC has sufficient space to accommodate the Florida Power & Light Company (FPL) response organization and designated representatives of the Nuclear Regulatory Commission (NRC) Site Team. Arrangements have been made which allow for continuous operation, as necessary.

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10 ACTIVATION AND OPERATION OF THE 6 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

T Indicates a step that requires a sign off on an attachment.

2.1 References

1. §1 St. Lucie Plant Technical Specifications Unit 1 and Unit 2 (Section 6.10.1)

2. St. Lucie Plant Updated Final Safety Analysis Report (UFSAR) Unit 1 and Unit 2

3. §2 St. Lucie Plant Radiological Emergency Plan (E-Plan)

4. §3 St. Lucie Plant Topical Quality Assurance Report (TQAR)

5. E-Plan Implementing Procedures (EPIP 00-13)

6. HP-200 Series Procedures

7. ADM-1 7.09, Invoking 10 CFR 50.54(x)

8. ADM-1 7.11, 10 CFR 50.59 Screening

9. St. Lucie Plant Emergency Response Directory (ERD)

10. QI-17-PSL-1, Quality Assurance Records

11. ERDADS Reactor Operator's Manual (8770-12058)

12. St. Lucie Plant Severe Accident Management Guidelines (SAMGs)

REVISION NO: PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 7 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT 2.1 References (continued)

13. §4 Fitness for Duty Rule, 10 CFR 26

14. NUREG 1394, Emergency Response Data System (ERDS)

15. Condition Report 01-0169 (TSC / Unit 1 CR HVAC Charcoal Filtration Change Out) 2.2 Records Required

1. The following shall be retained following a plant emergency:

Checklists, data and paperwork generated per this procedure.

Log books maintained during the plant emergency.

2. §1 Recorded information shall be forwarded to Emergency Planning following the event, for review and archival in accordance with Technical Specification 6.10.1 and QI-17-PSL-1.

2.3 Commitment Documents

1. T1 PMAI PM97-04-142, Training Drill Critique 1/24/97, (ERDADS screen mimics and full staffing guidance)

2. ¶2 Condition Report 97-1389, (Emergency Supplies)

3. ¶4 PMAI PM96-09-185, Condition Report CR 96-1750 (Off-site Notification Using Commercial Phone)

4. ¶5 Condition Report 00-0429 (TSC Briefing)

5. ¶6 Condition Report 01-0078 (Re-entry Paperwork and Response Time Expectations)

REVISION NO' PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 8 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT 3.0 RESPONSIBILITIES 3.1 Emergency Coordinator (EC)

1. The responsibilities for this position are provided in EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

3.2 TSC EC Assist/Logkeeper

1. Initiates and maintains the EC Logbook.

2. Provides assistance to the EC to ensure EC responsibilities are met, particularly off-site notifications and Protective Action Recommendations (PARs).

3. Performs duties as directed/assigned by the EC.

3.3 TSC Supervisor

1. Provides command and control of TSC activities.

2. Supervises the TSC staff particularly the communicators and administrative personnel.

3. Coordinates activities to ensure adequate support of the EC.

4. Ensures communications are performed with off-site agencies until the EOF is activated.

5. Ensures the communication flow is maintained within the facility and with the Control Room, OSC and EOF.

6. Coordinates facility briefings.

7. Arranges for long term operation of the TSC.

3.4 TSC Coordinator with the OSC

1. Serves as the coordinator with the OSC.

2. Provides the OSC with requests for Re-entry Teams.

3. Tracks the re-entry activities of the OSC.

4. Updates the TSC regarding OSC team status and corrective actions.

REVISION NO.' PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 9 f 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT 3.5 TSC OPS Coordinator NOTE This position is filled by two persons, one located in the affected unit's Control Room, the other in the TSC.

1. Provides expertise in plant operations to the EC in the TSC.

2. Provides communications assistance to the NPS in the affected Control Room.

3. Ensures the unaffected unit's Control Room is kept apprised of the status of the emergency.

4. Maintains communication flow between the TSC and the affected Control Room concerning status of operations.

5. Serves as primary Severe Accident Management Guidelines (SAMGs) decision maker.

3.6 TSC Reactor Engineer

1. Monitors critical safety functions for indications of core status.

2. Assists Nuclear Fuels personnel in the EOF in assessment of core damage.

3. Assists in Severe Accident Management Guidelines (SAMGs) evaluation.

3.7 TSC Chemistry Supervisor

1. Directs dose assessment activities in the TSC.

2. Assists the EC with Protective Action Recommendations (PARs).

3. Keeps the EC apprised of chemistry related issues.

4. Assists the Chemistry Supervisor in the OSC.

3.8 TSC HP Supervisor (TSCHPS)

1. The responsibilities for this position are provided in HP-200, Health Physics Emergency Organization.

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10 ACTIVATION AND OPERATION OF THE 10 of 82 PROCEDURE NO" TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT 3.9 TSC Security Supervisor

1. Establishes and maintains site accountability.

2. Arranges site access for the NRC Site Team.

3. Controls on-site security operations throughout the emergency.

3.10 TSC Problem Solving Team (PST)

1. Evaluates plant conditions and provides recommendations to the EC.

2. Anticipates component failures and accident consequences.

3. Researches affected systems and components.

4. Develops mitigation strategies and/or countermeasures.

5. Performs Severe Accident Management w

Guidelines (SAMGs)

. o evaluatiion.

4.0 DEFINITIONS 4.1 Facility Status

1. Activation - the request to staff and establish an Emergency Response Facility (ERF).

2. Operational - when sufficient personnel (i.e., minimum staff) are available to accomplish mandatory facility functions such as off-site notifications and dose calculations.

3. Fully Staffed - the complete complement of personnel is present in the facility.

4.2 FPL Emergency Recall System (ERS) - the call-out system used as a means of off hours call-out, as described in EPIP-03, Emergency Response Organization/Staff Augmentation.

4.3 Videolink - a closed circuit audio/visual communications link originating in the TSC with feeds to the OSC and the EOF allowing the EC briefings to be available in all the Emergency Response Facilities (ERFs).

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10 ACTIVATION AND OPERATION OF THE 11 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT 5.0 INSTRUCTIONS NOTE

"* This section provides general information and instructions for all TSC responders.

"* Position specific checklists are included as attachments to this procedure.

"* Individuals specifically designated as members of the TSC Emergency Response Organization (ERO) are identified in the ERD.

5.1 When notified, TSC emergency responders are to report to the facility as quickly as possible.

5.2 The initial responder to the TSC should do the following:

1. Unlock the facility with a key from the NPS or Assistant Nuclear Plant Supervisor (ANPS). If these persons are unavailable, break the glass to the keybox next to the door and remove the key.

2. Turn on the facility lights.

3. Open all facility equipment / document storage cabinets.

5.3 Upon arrival at the facility, each TSC emergency responder should perform the following:

1. Sign-in on:

A. the status board on the South (rear) wall of the facility in the space corresponding to your position and B. the TSC ERO Shift Staffing and Accountability Roster.

2. Obtain your specific position notebook from the storage cabinet.

3. Place your name on your position (player) badge (located in the position notebook) with a dry erase marker or in any other non permanent manner.

4. Make your workstation/location operational.

5. Notify your supervisor or the TSC Supervisor of your readiness status.

REVISION NO' PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 12 of 82 PROCEDURE NO TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT 5.4 §3 Only controlled copies of nuclear safety-related procedures, drawings and other available plant information shall be used. Non-controlled documents or drawings should be verified with a controlled copy prior to use in the TSC.

5.5 During facility briefings, stop what you are doing, pay attention and contribute, as requested.

5.6 Upon termination of the event:

1. All TSC personnel should return their workstations/locations to a normal state and assist in restoring the facility to a ready condition.

2. Collect all significant information and documentation, such as completed EPIPs and attachments, logs, notification forms and other notes and data sheets (not bound in the position notebooks), and provide this material to the TSC Supervisor.

END OF SECTION 5.0

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10 ACTIVATION AND OPERATION OF THE 13 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 1 TSC EMERGENCY RESPONSE ORGANIZATION AND SHIFT STAFFING (Page 1 of 1)

I TSC Staff 113TSC SP Phonetalker 13 I 1'4 TSC ERDADS Oper ITSC SP 1, L Phonetalker 116TSC ERDADS Tech 121 TSC Admir Staff (2)

(Located In the.

Control Room) 106 TSC Communicator (3)

(ENS Comm)

(HRD Comm)

(EOF Comm) 120 TSC r* OS Coordinator - Coordinator with OSC l IwithTSC (Not a required position ) (Located in the OSC)

I [ I I

fi6 TSC OPS 110 TSC OPS 105 ITSC React:d 103 TSC HP 115 TSC PST 104 TSC Chemistry 119 TSC Securty q... I Coordinator EnoineerSuperisor Leader Supervisor Supervisor (Located In the Control Room ) 112 TSC HP Comm (2) O107 TSC Elec Rep-PST (HPN Comm) 0108 TSC Mech Rep-PST (2) rTSCDose[

(FMT Comm) (Note 1) 1 17TSC I&C Rep-PST (PIPS/EPIP-O4IAttI-RO.

1 18TSC SRO Rep-PST Autodialer positton numbers are fisted with position titles

30 minute response goal, per NUREG 0654, Table B-1

60 minute response goal, per NUREG 0654, Table B-1 Note 1- Only one person tn the TSC Mech Rep-PST position is required as minimum staff Note 2- The Dose Assessor function will be performed by the on-shift ChemisL Indicates minimum staffing positions that must be filled in order to declare the facility operational END OF ATTACHMENT 1

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10 ACTIVATION AND OPERATION OF THE 14 of 82 PROCEDURE NO TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 2 TSC EC ASSIST / LOGKEEPER CHECKLIST (Page 1 of 2)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL

1. Refer to section 5.0 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION

1. Remove the EC Logbook from the EC position notebook and initiate the EC Log (use Attachment 2A, Typical Information to be Included in the EC Logbook).

2. Review the requirements of EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

3. Steps to occur continually while the facility is in operation:

a. Maintain the EC Logbook.

b. Assist the EC in the completion of the requirements of EPIP-02.

c. Prior to the Emergency Operations Facility going operational, assist the EC in completion of the State Notification Form, including determination of Protective Action Recommendations (PARs), as necessary in accordance with EPIP-08, Off-site Notifications and Protective Action Recommendations.

d. Verify that the EC approves all off-site notification forms.

e. Remind the EC of time limits for notification of off-site agencies.

f. Ensure checklists/paperwork are properly completed.

g. Provide EC a summary of recent log entries for facility briefings.

REVISION NO

PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 15 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 2 TSC EC ASSIST I LOGKEEPER CHECKLIST (Page 2 of 2)

B. 3. (continued) INITIAL

h. Support EC as needed or requested.

i. Assist the Emergency Notification System (ENS)

Communicator in responding to requests for information from the NRC.

C. FACILITY CLOSEOUT AND RESTORATION NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Ensured all facility activities closed out.

2. Closed out the EC Log, returned the Logbook to the EC position notebook and returned the notebook to the storage cabinet.

3. Ensured all paperwork collected.

4. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

5. Returned position notebook to storage cabinet.

END OF ATTACHMENT 2

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10 ACTIVATION AND OPERATION OF THE 16 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 2A TYPICAL INFORMATION TO BE INCLUDED IN THE EC LOGBOOK (Page 1 of 1)

Maintaining concise, detailed logs during an emergency event is important. Following the event, all information recorded will be needed to provide a clear picture of actions taken.

A. The following information should be included in the EC Logbook:

1. Key events (e.g., classification changes, injuries, etc.).

2. Status changes in equipment, radiological conditions, personnel, etc.

3. Decisions made or actions taken.

4. Other items of significance.

B. Log entry requirements:

1. Time of entry.

2. Use ink.

3. Write/print legibly.

4. Use concise and accurate wording.

5. Strike through and initial changes.

6. Do not remove pages from the log.

END OF ATTACHMENT 2A

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10 ACTIVATION AND OPERATION OF THE 17 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 3 TSC SUPERVISOR CHECKLIST (Page 1 of 4)

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5.0 of this procedure (included in the position notebook) and review the general instructions.

2. Determine operational readiness of the TSC by verifying the following:

a. Minimum staff available (use to Attachment 3A, TSC ERO Shift Staffing and Accountability Roster).

b. Communications equipment, procedures and other supplies are available, checked and ready to use.

0 Commercial phone as backup to State/County and NRC Notifications (DO NOT test call HRD or ENS).

Extension phones in TSC.

Procedure, drawing, tech manual cabinets unlocked.

Instruct personnel to verify their position notebook procedures against the posted revision numbers.

c. Minimum staff prepared to accomplish mandatory facility functions.

3. Recommend to the EC that the TSC should be declared operational. Operational at

REVISION NO.: PROCEDURE TITLE PAGE*

10 ACTIVATION AND OPERATION OF THE 18 of 82 PROCEDURE NO. TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 3 TSC SUPERVISOR CHECKLIST (Page 2 of 4)

A. (continued) INITIAL NOTE T1 Unless authorized by the EC, facility staffing should be in accordance with Attachment 3A, TSC ERO Shift Staffing and Accountability Roster.

4. Review additional staffing status with the EC.

5. TSC fully staffed.

6. Ensure that the EC log, completed notification forms and checklists and any other pertinent information have been faxed to the EOF.

B. FACILITY OPERATION

1. Initiate the TSC Logbook.

NOTE The TSC Reactor Engineer 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).

2. Ensure ERDADS Link with the NRC (ERDS) established/

attempted.

3. 12 Obtain food and water supply for the Unit I Control Room/TSC personnel.

4. ¶2 Obtain food and water supply for the Unit 2 Control Room personnel.

5. Arrange for long term staffing (use Attachment 3A, TSC ERO Shift Staffing and Accountability Roster).

6. As directed by the EC, initiate steps for relocation of the TSC (use Attachment 3D, Guidelines for Relocation of the TSC).

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10 ACTIVATION AND OPERATION OF THE 19 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 3 TSC SUPERVISOR CHECKLIST (Page 3 of 4)

B. (continued) INITIAL

7. Steps to occur continually while the facility is in operation:

a. Maintain the TSC Logbook.

b. Manage/supervise activities of TSC Communicators (HRD, ENS, EOF, HPN, Sound-Powered Phonetalker, FMT).

c. Manage/supervise activities of the TSC Administrative Staff.

d. Maintain low noise levels in the facility.

e. Coordinate overall support functions of the TSC.

f. Conduct briefings in accordance with Attachment 3C, TSC Facility Briefings.

g. Ensure the OSC is kept well informed regarding emergency status and plant conditions (an audio/video link may be used for this purpose).

h. Ensure the EOF is kept well informed regarding emergency status and plant conditions (an audio/video link may be used for this purpose).

C. FACILITY CLOSEOUT AND RESTORATION NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. All communications links terminated.

2. All communications paperwork collected.

3. All facility activities closed out.

4. All documents, equipment and supplies returned to pre-activation condition and/or location.

I I REVISION NO: PROCEDURE TITLE. PAGE:

10 ACTIVATION AND OPERATION OF THE 20 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 3 TSC SUPERVISOR CHECKLIST (Page 4 of 4)

C. (continued) INITIAL

5. Closed out TSC Logbook.

6. Provided all completed paperwork (not bound in the position notebook(s)) to Emergency Planning.

7. Returned position notebook to storage cabinet.

END OF ATTACHMENT 3

( C (..

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10 IACTIVATION 1 AND OPERATION OF THE TECHNICAL SUPPORT CENTER 1 21 of 82 PROCEDURE NO.:

EPIP-04 ST. LUCIE PLANT ATTACHMENT 3A TSC ERO SHIFT STAFFING AND ACCOUNTABILITY ROSTER (Page 1 ofl1)

Shift1 .2 _ ,, Hours To POSITION NAME BADGE NO. POSITION NAME BADGE NO.

3 3 (Minimum Staff in Bold) (Minimum Staff in Bold)

Emergency Coordinator TSC HP Supervisor TSC Supervisor TSC HP Comm TSC Reactor Engineer TSC HP Comm TSC Dose Assessor _ TSC Chem Supervisor TSC Communicator 4 TSC OPS Coord (TSC)

TSC Communicator 4 TSC OPS Coord (CR)_

TSC Communicator 4 TSC SP Phonetalker (TSC)_

TSC Elec Rep-PST TSC SP Phonetalker (CR)

TSC Mech Rep-PST TSC Coordinator with OSC TSC Mech Rep-PST TSC ERDADS Operator TSC Mech Rep-PST TSC ERDADS Tech TSC I&C Rep-PST TSC Admin Staff TSC SRO Rep-PST TSC Admin Staff TSC PST Leader TSC Security Supv TSC EC Assist / Logkeeper TSC EP Coord (not required)_

1 Long term staffing, refer to the St. Lucie Plant Emergency Response Directory (ERD) for position alternates.

2 Long term staffing includes the Control Rooms, attach list to this sheet.

3 Refer to Attachment 3B, TSC Minimum Staffing Requirements, to this attachment for temporary alternates for minimum staff positions.

4 TSC Communicator position fills the following positions:

a. TSC ENS Communicator

b. TSC HRD Communicator

c. TSC EOF Communicator 5 Position may be relieved when the EOF goes operational and takes the lead for dose assessment.

END OF ATTACHMENT 3A

REVISION NO.: PROCEDURE TITLE: PAGE' 10 ACTIVATION AND OPERATION OF THE 22 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 3B TSC MINIMUM STAFFING REQUIREMENTS (Page 1 of 1)

Area' Position Title and ID No. 2 # in Qualifications/

Major Functional Position Temporary Alternate Senior Mgmt. Rep. Emergency Coordinator, 101 1 Senior Manager with Emergency Coordinator qualifications Off-site Dose Assessment TSC Dose Assessor, 111 1 Member of Chemistry Department Core/Thermal Hydraulics TSC Reactor Engineer, 105 1 Member of the Reactor Engineering Cor__ eraHyrauicTCeato Engineer,_____________

15 _ 1 Department or current or prior STA TSC responder with

- STA or equivalent background for ENS Notification/Communication TSC Communicator, 106 3 Communicator

- Technical/operational background for I_ HRD or EOF Communicator Electncal TSC Elec Rep - PST, 107 1 Electrical Engineer or Electrical Maintenance Supervisor Mechanical Engineer or Mechanical Mechanical TSC Mech Rep - PST, 108 1 MenancEnSupersor Maintenance Superviisor Facility Command and TSC Supervisor, 102 1 TSC Coordinator with OSC Control I I I 1 This function(s) may be accomplished dunng the first 75 minutes of an emergency by an individual(s) meeting the corresponding listed qualifications.

2 These Emergency Response Organization (ERO) positions were established to accomplish the indicated function(s).

END OF ATTACHMENT 3B

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PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 23 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT

¶5 ATTACHMENT 3C TSC FACILITY BRIEFINGS (Page 1 of 2)

NOTE Briefings should be carried by the Videolink.

A. GENERAL GUIDELINES

1. Coordinated by the TSC Supervisor or his/her designee:

a. Establish a frequency (e.g., approximately every 30 minutes).

Frequency of briefings may be changed (e.g., decreased during a protracted event or increased during rapidly changing conditions).

b. Set criteria (i.e., attendance, noise and activity level, collection and circulation of information, etc.).

2. TSC Supervisor should announce the start of the briefing and then turn the briefing over to the EC.

3. TSC Supervisor should assist the EC during the briefing.

a. Ensure that the EC receives any updated information. Coordinate this with the TSC EC Assistant/Logkeeper.

b. Ensure that the EC repeats any questions that are asked from the floor to ensure that the OSC and EOF members have heard them.

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10 ACTIVATION AND OPERATION OF THE 24 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 3C TSC FACILITY BRIEFINGS (Page 2 of 2)

B. GENERAL FORMAT - the following information should be included in facility briefings.

NOTE It is not necessary to have all department representatives participate in each briefing. Use discretion in this area to avoid unnecessary repetition of information.

1. Initial status and summary to include:

a. Time of the briefing.

b. Emergency Classification.

c. Plant status (affected unit, unaffected unit).

d. Radiological conditions (e.g., release in progress, contaminated areas, etc.).

e. Status of protective actions (e.g., site evacuation, actions underway by the public, etc.).

f. Status of activities underway in the facility.

g. Priority activities/primary focus.

2. Input/update information from other departments:

a. Operations (including EOP actions, discussion of SAMGs).

b. Health Physics (including field monitoring activities).

c. Reactor Engineering (including status of the reactor core).

d. Problem Solving Team (including SAMGs).

e. TSC Coordinator with the OSC (including re-entry activity status).

3. Major activities underway in other facilities.

4. Concerns or questions.

END OF ATTACHMENT 3C

NO.: PROCEDURE TITLE:

REVISION NO.:

REVISION PROCEDURE TITLE:

10 ACTIVATION AND OPERATION OF THE 25 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 3D GUIDELINES FOR RELOCATION OF THE TSC (Page 1 of 3)

If habitability of the Unit 1 Control Room is challenged (e.g., due to fire/smoke) and evacuation is required, the TSC will need to be relocated. The following guidelines are provided to assist in this endeavor.

A. Emergency Coordinator

1. Transfer the responsibilities of the EC as follows:

a. Classification of the emergency - NPS NOTE The EOF, once operational, has responsibility for recommending protective actions and for off-site notifications.

b. Protective Action Recommendations (PARs) - NPS

c. Decision to notify off-site officials and the content of notification messages - NPS

d. Request the unaffected Control Room ANPS to support the NPS in off-site notifications.

2. Conduct a transfer of EC responsibilities with the NPS (via phone conversation) once the alternate TSC is prepared to go operational.

B. TSC Supervisor

1. In conjunction with the EC and the TSC HP Supervisor, determine the appropriate area to relocate the TSC. Choose one of the following:

a. South Service Building

b. Nuclear Training Center

2. Direct the evacuation by briefing TSC personnel on location, travel route, materials to take and any immediate actions prior to leaving the facility (e.g., formally terminate communications, turn off equipment, etc.)

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B. (continued)

3. Re-establish command and control of TSC functions as quickly as possible.

a. Transfer the responsibility for off-site notifications from the unaffected Control Room (if this responsibility has not been transferred to the EOF) to the communicators in the relocated TSC.

C. All TSC Personnel

1. Formally discontinue communications.

2. Gather position notebooks and other pertinent materials.

3. Travel per the prescribed route to the alternate TSC location.

4. Assist Security in re-establishing accountability as quickly as possible.

5. Re-establish TSC functions as quickly as possible.

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Suggested Arrangements and Equipment Availability at Alternate TSC Locations:

Communications SOUTH SERVICE BUILDING NUCLEAR TRAINING CENTER HRD Phone EP area Simulator ENS Phone Any commercial phone Any commercial phone HPN Phone Any commercial phone Any commercial phone EOF Phone Any commercial phone Any commercial phone FMT Radio EP area Simulator Dose Assessment Class A Model EP area Technical Training area second floor TSC Functions Command and EP area Conference room and Control Supervisor offices second floor Problem Conference room Engineering area Solving Team third floor second floor Other Open cubicles Cubicles second floor END OF ATTACHMENT 3D

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10 ACTIVATION AND OPERATION OF THE 28 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4 TSC COMMUNICATOR CHECKLIST (Page 1 of 4)

NOTE

1. This checklist applies to the following Communicator positions in the TSC:

HRD Communicator ENS Communicator EOF Communicator Sound-powered Phonetalker (CRITSC)

2. The responsibilities of the TSC HP Communicators are provided as follows:

HPN Communicator - in HP-200, Health Physics Emergency Organization FMT Comm/Coord - in EPIP-10, Off-site Radiological Monitoring

3. When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

NOTE Communicator positions should be filled in the following order:

1. Hot Ring Down (HRD) Phone

2. Emergency Notification System (ENS)

3. EOF

4. Sound-powered Phone (CR)

5. Sound-powered Phone (TSC)

2. Filling the position of

3. Review appropriate information in Attachment 4A, Communications Guidelines.

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10 ACTIVATION AND OPERATION OF THE 29 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4 TSC COMMUNICATOR CHECKLIST (Page 2 of 4)

B. FACILITY OPERATION

1. Steps to occur continually while the facility is in operation:

HRD Communications

a. Assist the EC with State and County notifications by:

1. Reviewing the State Notification Form for completeness.

2. As necessary, ensuring Protective Action Recommendations (PARs) match the completed PAR Worksheet (see Attachment 3, Determination of Protective Action Recommendation (PARs) in EPIP-08, Off-site Notifications and Protective Action Recommendations).

3. Ensure the EC has approved the form.

b. Transmit the notification form in accordance with Appendix B, Notifications from the Technical Support Center (TSC), EPIP-08.

c. Request the TSC EC Assist/Logkeeper log notification times.

d. Following turnover of notification responsibility to the EOF HRD Communicator, identify availability to the TSC Supervisor. Be prepared to provide assistance as requested.

ENS Communications

a. If necessary, transmit an initial NRC Notification Form in accordance with EPIP-08.

b. At an Alert or higher emergency classification, request the NRC to establish the ENS conference bridge.

c. Maintain an open line of communication and a transmission log.

d. Request the TSC EC Assist/Logkeeper:

1. Provide assistance in responding to requests for information from the NRC.

2. Log notification times, as appropriate.

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10 ACTIVATION AND OPERATION OF THE 30 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4 TSC COMMUNICATOR CHECKLIST (Page 3 of 4)

B. 1. (continued)

ENS Communications (continued)

e. Log all questions asked by NRC.

f. Obtain answers to questions from appropriate TSC staff member (e.g., HP, Chemistry, Reactor Engineering, etc.), as necessary.

g. Obtain EC approval prior to providing additional information to the NRC.

EOF Communications

a. Maintain an open line of communication with the EOF.

b. If ERDADS is out of service, use Attachment 4B, Safety Functions Equipment Status and Radioactive Gaseous Source Terms, to obtain plant parameter and radiological data via the Sound powered Phonetalker and share the information with the EOF (via the TSC Communicator in the EOF).

c. Provide clarification of any discrepant information as requested by the EOF.

Sound-powered Phonetalker

a. Provide an open line of communication between the affected Control Room and the TSC.

b. Provide fan status for dose assessment.

c. Provide clarification of data and/or obtain additional data as requested by the TSC.

d. If ERDADS is out of service, use Attachment 4B, Safety Functions Equipment Status and Radioactive Gaseous Source Terms, to obtain plant parameter and radiological data.

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10 ACTIVATION AND OPERATION OF THE 31 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4 TSC COMMUNICATOR CHECKLIST (Page 4 of 4)

C. FACILITY CLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. All communications links (HRD, ENS, EOF, Sound-powered phone) terminated.

2. All communications paperwork collected.

3. All phone equipment returned to pre-activation condition.

4. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

5. Returned position notebook to storage cabinet.

END OF ATTACHMENT 4

REVISION NO.: PROCEDURE TITLE PAGE:

10 ACTIVATION AND OPERATION OF THE 32 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4A COMMUNICATIONS GUIDELINES (Page 1 of 5)

NOTE If communications are associated with drill or exercise, the statement "This is a drill" should precede and follow the actual message.

A. GENERAL GUIDELINES

1. Always speak clearly, firmly and with normal tone when using any communication system.

2. The sender and receiver should be clearly identified.

3. Message text:

a. Communication must be free of ambiguity. Slang terms should not be used. Avoid the use of words that sound alike; for example, avoid increase and decrease, use raise and lower instead.

b. Communications must be specific. Use noun names for plant equipment, not acronyms; for example Low Pressure Safety Injection Pump instead of LPSI.

c. The phonetic alphabet should be used to identify specific train, bus, channel or equipment designations, not just letter identifier; for example, refer to the 1AIpha heater drain pump, not the 1A heater drain pump. The following is the phonetic alphabet to be used:

A Alpha J Juliet S Sierra B Bravo K Kilo T Tango C Charlie L Lima U Uniform D Delta M Mike V Victor E Echo N November W Whiskey F Foxtrot 0 Oscar X X-ray G Golf P Papa Y Yankee H Hotel Q Quebec Z Zulu I India R Romeo

d. The phonetic alphabet should not be used for stringed letter references, acceptable acronyms or location symbols; for example, AB bus, AC or DC, TSC, respectively.

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10 ACTIVATION AND OPERATION OF THE 33 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4A COMMUNICATIONS GUIDELINES (Page 2 of 5)

A. (continued)

4. Acknowledgement and confirmation (3-way communication) - messages shall be comprised of proper transmission, acknowledgement, and confirmation.

a. The message is properly transmitted from the originator to the receiver.

b. The message receiver should acknowledge the communication by giving functional repeat-back to the message originator. The repeat-back can be provided by either paraphrasing or explaining the message in one's own words, or by verbatim repeat-back. In all cases, verbatim repeat-back should be used for equipment identifiers.

c. Ifthe message receiver does not understand the message he/she should ask for the message to be repeated.

d. Ifan incorrect repeat-back is given, the message originator should immediately correct the miscommunication with a statement such as, 'WRONG", followed by restating the correct message.

e. The message originator should confirm the acknowledgement (repeat-back) with a statement such as, "That is correct".

5. The Call Sign should be used periodically when using the Local Government Radio (LGR).

6. Prior to transmission, ensure that information has been verified and approved by the appropriate authority, as necessary.

7. Ensure that any incoming pertinent information is provided to the TSC Supervisor and the Emergency Coordinator or designee.

8. Maintain documentation of any significant information provided or received.

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10 ACTIVATION AND OPERATION OF THE 34 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4A COMMUNICATIONS GUIDELINES (Page 3 of 5)

B. COMMUNICATIONS SYSTEMS

1. State Warning Point (SWP) Hot Ring Down Phone (HRD)

a. This is the primary communications pathway to the State Warning Point and St. Lucie and Martin Counties.

b. A self-verifying phone system which is initiated by entering the 3 digit code corresponding to the desired location of contact. The codes appear on a list in a pull-out drawer attached to the base of the phone or in the St. Lucie Plant Emergency Response Directory (ERD). A confirmation ring-back (double tone) will be heard if the dialed terminal is successfully contacted. When the party answers, begin transmission by depressing the "push-to-talk" bar in the handset. Release the "push-to-talk" bar to receive response.

2. NRC Emergency Notification System (ENS)

a. This is the primary communications pathway to the NRC.

b. Part of the NRC Emergency Telecommunications System (ETS).

Initiate contact by dialing (direct, no access code needed) one of the phone numbers provided on the phone or in the ERD. This will become an open line of communication at the Alert or higher emergency class. The EOF will join the conference bridge.

3. EOF Direct-line Telephone

a. This is a direct line to the Emergency Operations Facility (EOF).

Initiate contact by removing the handset from the cradle which will cause the phone in the EOF to ring. When the phone is answered, begin transmission. This link can also be initiated from the EOF.

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B. (continued)

4. Sound-powered Phone

a. As the name implies, these phone (headsets) are powered by sound.

b. The Unit 1 phone jack is located near the Dose Assessment Status Board; the Unit 2 phone jack is located next to the Chronology Status Board in the rear of the room.

c. Once the headsets have been connected in both the affected Control Room and the TSC, transmission can begin by speaking into the mouthpiece.

5. Commercial Telephone

a. This is the first alternate communications pathway to the State Warning Point and St. Lucie, Martin Counties, and NRC.

NOTE An access code (i.e., 9 or 8-1) is not required when using a "direct dial" phone. 1

b. Dial 9 for a Fort Pierce exchange; dial 8-1-Area Code for all other numbers. An authorization code is needed for long distance calls.

6. Emergency Satellite Communications System (ESATCOM)

a. This is a second alternate communications pathway to the State Warning Point and St. Lucie and Martin Counties.

b. To initiate transmission, lift the handset and depress the "push-to talk" bar in the handset. Wait 3-5 seconds to hear a beep before starting to talk. The red light on the phone is a power indicator, when lit, power is available.

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10 ACTIVATION AND OPERATION OF THE 36 of 82 PROCEDURE NO TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4A COMMUNICATIONS GUIDELINES (Page 5 of 5)

B. (continued)

7. Local Government Radio (LGR) - Call Sign: Kilo November Golf Romeo 8-7-4 (KNGR874).

a. This is the third alternate communications pathway to the State Warning Point.

b. A backup communication system to the Counties and indirectly to the State. A table radio, Motorola Command Series, provides two channels, the primary F2 (39.180 MHz, State Channel 1) and the secondary F1 (39.100 MHz, State Channel 2). Channel selection can be made by depressing the "FI/F2" button (the radio is set to monitor F2). The radio can be operated either by depressing the "transmit" button on the console or be removing the handset and depressing the "push-to-talk" bar in the handset. The "xmit" light is lit during transmission. (Preference should be given to using the handset).

8. Satellite Telephone

a. Instructions for use of the satellite telephone are provided in the phone's briefcase.

b. The phone is stored in a supply cabinet in the TSC.

0 END OF ATTACHMENT 4A

REVISION Nu.. PROCEDURE TITLE' 6- (

PAGE:

10 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER 37 )f 82 PROCEDURE NO:

EPIP-04 ST. LUCIE PLANT

______________ I I ATTACHMENT 4B SAFETY FUNCTIONS EQUIPMENT STATUS - UNIT I ffl (Page 1 of 4)

ERDADS SF1 Screen Mimic 1 PLANT PARAMETERS SAFEGUARDS CONTAINMENT BALANCE OF PLANT REACTOR PWR (WR) _ % PUMP STATUS (ON/OFF) PRESSURE PSIG ELECTRICAL PLANT HPSIA ON/OFF REACTOR VSL LEVEL % HPSIB ON/OFF LEVEL (NR) _ FEET ((-7) TO 0) 4.16 KV A3 VOLTS LPSI A ON/OFF RCS PRESSURE (NR)... PSIA (1500-2500) LPSI B ON/OFF LEVEL (WR) -_---FEET((-I) TO 26) 4.16 KV B3 VOLTS CHRG A ON/OFF RCS PRESSURE (LR) ___PSIA (0-1600) CHRG B ON/OFF TEMPERATURE DIESEL GENERATORS CHRG C ON/OFF PRESSURIZER LEVEL % CCW A ON/OFF ATMOSPHERE DEG F DIG A VOLTS CCW B ON/OFF CET TEMPERATURE DEG F CCW C ON/OFF SUMP DEG F DIG A AMPS AFW A ON/OFF HOT LEG A TEMP DEG F AFW B ON/OFF RADIATION LEVEL DIG B VOLTS AFW C ON/OFF HOT LEG B TEMP DEG F CHHRM RIHR DIG B AMPS AUX FEED FLOW (GPM)

COLD LEG Al TEMP DEG F POST/LOCA MR/HR TANK STATUS A- B C COLD LEG A2 TEMP DEG F HPSI FLOW (GPM) PARTICULATE CPM RWT FEET Al A2 COLD LEG B1 TEMP DEG F B1_ B2 GASEOUS CPM CST FEET COLD LEG B2 TEMP DEG F LPSI FLOW (GPM) HYDROGEN CONCENTRATION BAMT A %

Al A2 LMTNG SBCOOL MRGN DEG F B1 B2 A ANALYSER __. BAMT B %

SITS LEVEL (%) B ANALYSER % HVAC STATUS (ON/OFF)

SIG A PRESSURE PSIG Al A2 B1 B2 SIG A LEVEL (WR) % CONTAINMENT COOLERS (ON/OFF) HVE 4A ON/OFF SITS PRESS (PSIA) HVE 4B ON/OFF S/G B PRESSURE PSIG Al A2 CNTMT COOLER A ON/OFF HVE 8A ON/OFF B1 B2 HVE 8B ON/OFF S/G B LEVEL (WR) % CNTMT COOLER B ON/OFF HVE 9A ON/OFF SAFEGUARDS SIGNALS HVE 9B ON/OFF CNTMT PRESS (WR) ... PSIG SIAS A YES/NO CNTMT COOLER C ON/OFF HVE 10A ON/OFF SIAS B YES/NO HVE 10B ON/OFF CONTAINMENT TEMP DEG F MSIS A YES/NO CNTMT COOLER D ON/OFF MSIS B YES I NO

REVISION NO.: PROCEDURE TITLE: PAGE' 10 ACTIVATION AND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4B RADIOACTIVE GASEOUS SOURCE TERMS - UNIT I (Page 2 of 4)

I ERDADS RG1 Screen Mimic 10 METER 57.9 METER WIND SPEED MPH MPH WIND DIRECTION DEG DEG AIR TEMP DEG DEG F F

DIFF TEMP DEG F / 50 METER CHANNEL MAIN STEAM VALUE UNITS CHANNEL CONTAINMENT VALUE UNITS 05-01 A MAIN STM MR/HR 58 A HI RANGE R/HR 05-02 B MAIN STM MR/HR 59 B HI RANGE RJHR PRESSURE PSIG CHANNEL ECCS1A VALUE UNITS CHANNEL PLANTVENT VALUE UNITS 02-05 LOW RANGE uC/cc 01-05 LOW RANGE uC/cc 02-07 MID RANGE uC/cc 01-07 MID RANGE uC/cc 02-09 HI RANGE uC/cc 01-09 HI RANGE uC/cc 02-10 FLOW SCFM 01-10 FLOW SCFM CHANNEL ECCS lB VALUE UNITS CHANNEL FUEL BLDG VALUE UNITS 03-05 LOW RANGE uC/cc 04-05 LOW RANGE uC/cc 03-07 MID RANGE uC/cc 04-07 MID RANGE uC/cc 03-09 HI RANGE uC/cc 04-09 HI RANGE uC/cc 03-10 FLOW SCFM 04-10 FLOW SCFM

.1 k Y.

K\ F --

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10 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER 39 of 82 PROCEDURE NO EPIP-04 ST. LUCIE PLANT ATTACHMENT 4B RADIOACTIVE GASEOUS SOURCE TERMS - UNIT 2 ffl (Page 3 of 4)

ERDADS SF2 Screen Mimic 2 PLANT PARAMETERS SAFEGUARDS CONTAINMENT BALANCE OF PLANT REACTOR POWER (WR) PUMP STATUS (ON/OFF) PRESSURE PSIG ELECTRICAL PLANT RX VSL HEAD LEVEL % HPSI A ON/OFF HPSI B ON/OFF LEVEL (NR) -FEET ((Q7) TO 0) 4 16 KVA3 __VOLTS RX VSL PLENUM LEVEL % LPSI A ON/OFF LPSI B ON/OFF LEVEL (WR) __.__FEET ((-1) TO 26) 4.16 KV B3 VOLTS RCS PRESSURE (NR) ___PSIA (1500-2500)

CHRG A ON/OFF RCS PRESSURE (LR) _ PSIA (0-750) CHRG B ON/OFF TEMPERATURE DIESEL GENERATORS CHRG C ON/OFF PRESSURIZER LEVEL % CCW A ON/OFF ATMOSPHERE DEG F D/G A VOLTS CET TEMPERATURE DEG F CCW B ON/OFF CCW C ON/OFF SUMP DEG F D/G A AMPS HOT LEG A TEMP DEG F AFW A ON/OFF AFW B ON/OFF RADIATION LEVEL D/G B VOLTS HOT LEG B TEMP DEG F AFW C ON/OFF CHHRM _ RHR DIG B AMPS COLD LEG Al TEMP DEG F AUX FEED FLOW (GPM)

COLD LEG A2 TEMP DEG F POST/LOCA MR/HR TANK STATUS A- B C COLD LEG B1 TEMP DEG F HPSI FLOW (GPM) PARTIC CPM RWT FEET COLD LEG B2 TEMP DEG F Al A2 81 B2 GASEOUS CPM CST FEET LMTNG SBCOOL MRGN DEG F LPSI FLOW (GPM) HYDROGEN CONCENTRATION BAMT A __%

S/G A PRESSURE PSIG Al A2 B1 B2 AANALYSER % BAMT B .%

S/G A LEVEL (WR) %

SIT'S LEVEL (%) B ANALYSER % HVAC STATUS (ON/OFF)

S/G B PRESSURE PSIG Al A2 S/G B LEVEL (WR) _ % 81 B2 CONTAINMENT COOLERS (ON/OFF) HVE 4A ON/OFF SITS PRESS (PSIA) HVE 4B ON/OFF CNTMT PRESS (WR) PSIG Al A2 CNTMT COOLER A ON/OFF HVE 8A ON/OFF CONTAINMENT TEMP DEG F B1 B2 HVE 8B ON/OFF CNTMT COOLER B ON/OFF HVE 9A ON/OFF SAFEGUARDS SIGNALS HVE 9B ON/OFF SIAS A YES NO CNTMT COOLER C ON/OFF HVE 10A ONIOFF SIAS B YES NO HVE 10B ON/OFF MSIS A YES /NO CNTMT COOLER D ON/OFF MSIS B YES NO

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10 ACTIVATION AND OPERATION OF THE 40 of 82 PROCEDURE NO. TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 4B RADIOACTIVE GASEOUS SOURCE TERMS - UNIT 2 11 (Page 4 of 4)

ERDADS RG2 Screen Mimic 2

10 METER 57.9 METER WIND SPEED MPH MPH WIND DIRECTION -DEG DEG CURRENTTEMP DEG F DEG F DIFF TEMP DEG F CHANNEL MAIN STEAM VALUE UNITS CHANNEL CONTAINMENT VALUE UNITS 631 A MAIN STM MR/HR 40 A HI RANGE R/HR 632 B MAIN STM MR/HR 41 B HI RANGE RIHR 633 BACKGROUND MR/HR PRESSURE PSIG CHANNEL ECCS 2A VALUE UNITS CHANNEL PLANT VENT VALUE UNITS 601 LOW RANGE uC/cc 621 LOW RANGE uC/cc 602 MID RANGE uC/cc 622 MID RANGE uC/cc 603 HI RANGE uC/cc 623 HI RANGE uC/cc 604 EFFLUENT uC/SEC 624 EFFLUENT uC/SEC CHANNEL ECCS 2B VALUE UNITS 611 LOW RANGE uC/cc 612 MID RANGE uC/cc 613 HI RANGE uC/cc 614 EFFLUENT uC/SEC END OF ATTACHMENT 4B

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10 ACTIVATION AND OPERATION OF THE 41 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5 TSC ERDADS OPERATOR CHECKLIST (Page 1 of 2)

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION

1. Check out ERDADS terminals and determine operability status.

If ERDADS is inoperable or printouts are not available, Then assist the Sound-powered Phonetalker in collecting plant parameter and radiological data by completing Attachment 4B, Safety Functions Equipment Status and Radioactive Gaseous Source Terms.

2. Steps to occur continually while the facility is in operation:

a. Call up EPIP screens and additional data as requested, refer to Attachment 5A, ERDADS Data Acquisition.

b. Provide the following printouts to the TSC Administrative Staff.

1. Safety Functions Equipment Status (SF 1/2).

2. Radioactive Gaseous Source Terms (RG 1/2).

3. Other screens as requested.

c. Support dose assessment by providing requested data from ERDADS.

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10 ACTIVATION AND OPERATION OF THE 42 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5 TSC ERDADS OPERATOR CHECKLIST (Page 2 of 2)

B. 2. (continued) INITIAL

d. Observe ERDADS data during interval between report printing for significant changes and trends, report changes to appropriate members of the TSC staff.

e. Refer to Attachment 5B, ERDADS Data Points, for a description of ERDADS data points.

C. FACILITY CLOSEOUT AND RESTORATION SNOTE All paperwork completed in the position notebook should remain in the position notebook.

1. ERDADS system returned to preactivation condition.

2. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

3. Returned position notebook to storage cabinet.

END OF ATTACHMENT 5

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10 ACTIVATION AND OPERATION OF THE 43 of 82 PROCEDURE NO' TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5A ERDADS DATA ACQUISITION (Page 1 of 3)

1. DATA ACQUISITION A. ERDADS - Emergency Response Data Acquisition and Display System, the following information is available on the display screens indicated.

1. Meteorological Data Display: SMD (Site Meteorological Data)

2. Plant Parameter Data -

Display: in the TSC - SF (1/2) (Safety Functions and Equipment Status)

3. Radiological Data Display: RG (112) (Radiation Gaseous Source Terms) RBS (Health Physics Evaluation Screen - containment radiation levels and trends) R11 (Area Radiation Monitors, Unit 1) R21 (Area Radiation Monitors, Unit 2)

4. Chemistry Data Display: R12 (S/G Blowdown, Steam Jet Air Ejector, Unit 1)

R22 (S/G Blowdown, Steam Jet Air Ejector, Unit 2)

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1. DATA ACQUISITION (continued)

A. (continued)

5. To access data

a. Press "CLEAR"

b. Type in "Pup Unit (1/2)"

c. Press "EXEC"ute, top of screen will read "Unit change is complete" or "Current Unit is same as entered Unit"

d. Press "EPIP"

e. The "PAGE UP" and "PAGE DOWN" keys will cause the following display sequence:

SMD - RG (112) - SF (1/2) - RBS - EF (1/2) - SMD

6. To go directly to a screen

a. Press "CLEAR"

b. Type in screen designation, e.g., "RGI"

c. Press "DISPLAY" B. Sound-powered Phonetalker - The Sound-powered Phonetalker can be utilized as a primary source of information or as an alternate method to ERDADS.

1. Primary source - status of fans needed for dose assessment exhaust fans 6, 7, 8, 9, 10, 15, 16 and 17.

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10 ACTIVATION AND OPERATION OF THE 45 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5A ERDADS DATA ACQUISITION (Page 3 of 3)

I1. ERDADS - COLOR/SYMBOL CONVENTIONS Color/Symbol Explanation 1 Numeric value in white on dark green Data value is valid and within the background instrument range.

Numeric value blinking (yellow on blue/ Value may be yellow on blue background red on white) (urgent alarm) or red on white background (critical alarm), indicates an alarm setting has been exceeded, the alarm must be acknowledged in the Control Room (operators are unable to acknowledge ERDADS alarms in the Simulator Control Room), the value will continue to blink until acknowledged; the value will continue to update.

Preceded by a numeric value in white on "BAD" (blue on white) a blue background signifying a suspect value indicating that one or several inputs to this composite point is/are out of instrument range, when all inputs to the point are out of range the word "BAD" replaces the numeric value.

"FAILED" Point is from a single instrument and the value is out of range.

"NO DATA" Point does not have input to ERDADS, usually point available on one unit, but not the other.

1Based on Table 4.1 in the ERDADS Reactor Operator's Manual (8770-12058)

END OF ATTACHMENT 5A

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10 ACTIVATION AND OPERATION OF THE 46 of 82 PROCEDURE NO TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5B 912 ERDADS DATA POINTS (Page 1 of 8)

The following data point descriptions for St. Lucie Plant correspond with the data normally tracked on the plant parameters status board. Consult ERDADS Manual, as necessary, for verification of point IDs, point names or description information.

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION Avg RCS T QTA541-1/2 Average This parameter is the average of the "A" and "B steam Hot (HLA and generator inlet temperature It is also referred to as the HLB) average hot leg temperature The individual "A" and "B" (deg F) hot leg temperatures are denved by choosing between current narrow and wide range sensor values The choice depends on the current values, qualities and direction of the rates of change of the instrumentation values, as well as two pairs of overlapping switching limits and the most recent range utilized The outputs from the calculation consist of the choice of range, the associated value and rate of change together with the quality of each RCS Pressure QA0501-1/2 RCS Average This parameter is a Reactor Coolant System (RCS)

WR (psia) Pressure wide range instrument It derived from Pressurizer Pressure signals PT1 107-2 and PT1 108-2 which are linear. These signals are processed by an average with expanded quality algorithm This function obtains the average of all values with a good status It also sets the quality of the result based on the number of values with good status, versus the total number of inputs. The possible status values are.

"* Greater than 50% of inputs have good status, result is good

"* Only one good value and the total inputs are 3 or more, the result is poor.

"* When there are no good data values, but there are some with poor or suspect, the result is poor

"* The result is suspect for all other cases except all bad, in this case the result is bad

REVISION NO: PROCEDURE TITLE. PAGE 10 ACTIVATION AND OPERATION OF THE 47 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5B fI2 ERDADS DATA POINTS (Page 2 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION RCS QA0001-1/2 PRZR LVL Average This parameter is pressurizer level It is derived from Pressurizer Pressunzer Level control signals LT 111OX-2 and Level (%) LT111OY-2 which are linear. These two signals are processed by an average with expanded quality algonthm. This function obtains the average of all values with a good status It also sets the quality of the result based on the number of values with good status, versus the total number of inputs. The possible status values are:

"* Greater than 50% of all inputs have good status, result is good

"* Only one good value and the total inputs are 3 or more, the result is poor.

"* When there are no good data values, but there are some with poor or suspect, the result is poor.

"* The result is suspect for all other cases except all bad, in this case the result is bad The top of the heaters is 73 98 inches above the lower top centerline Charging Flow FT2212-1/2 RCS N/A This parameter is reactor coolant system makeup flow to Regen Hx CHG/MU It is converted to engineering units using a linear (GPM) equation Subcooling QA0005-1/2 Submargin Minimal This parameter is derived from eight subcooled Margin (deg F) values, TMARHEAD-A-1/2, TMARRCS-B-1/2, TMARUR-A-1/2,TMARHEAD-B-1/2, TMARCET-A-112 TMARUR-B-1/2, TMARRCS-A-1/2 and TMARCET-B-1/2, which are provided by the Qualified Safety Parameter Display System (QSPDS). They are processed by a signal auctioneenng minimum algorithm This function finds the highest usable data value in a specified group. Each data value of the group and its quality is examined and the following quantities are obtained

1. Lowest usable data value, 2 Point number of the lowest usable data value, 3 Number of usable data values, and 4 Lowest quality of the usable data

For two or more usable data values, the result is the highest usable value and the quality is the lowest quality of the usable data

For only one usable data value, the result is set to that value and the quality is poor.

0 For no usable data, the value of the result is set to the highest of all the (bad) data and the quality is bad

REVISION NO: PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 48 of 82 PROCEDURE NO.. TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5B U12 ERDADS DATA POINTS (Page 3 of 8)

POINT POINT TYPE DESCRIPTION NAME CALCULATION Avg Core Exit QA0003-112 Temp Average This parameter is denved from 45 Unit I detectors, or Temperature Core Ex. 56 Unit 2 detectors located just above the upper fuel (deg. F) alignment plate. The Qualified Safety Parameter Display System (QSPDS) provides the values They are processed by an average with expanded quality algonthm. This function obtains the average of all values with a good status. It also sets the quality of the result based on the number of values with good status, versus the total number of inputs. The possible status values are*

"* Greater than 50% of all inputs have good status, result is good.

"* Only one good value and the total inputs are 3 or more, the result is poor.

"* When there are no good data values, but there are some with poor or suspect, the result is poor

"* The result is suspect for all other cases except all bad, in this case the result is bad.

Reactor Vessel Unit 1: Minimum The reactor vessel level for Unit 1 0A0004-1 is Level (%) QA0004-1 derived from the reactor vessel levels RLEV-A-1 and RLEV-B-1 which are provided by the Qualified Safety Unit 2. Parameter Display System. The ERDADS select the RLEV H-2 lowest of the two values For only one good data RLEV P-2 value, the result is set to that value and the quality is poor.

The reactor vessel level for Unit 2 is displayed as reactor plenum level RLEVPB-2 and reactor head level RLEVHB-2 which is provided by the "B" side Qualified Safety Parameter Display System (QSPDS).

These two parameters are displayed with no calculations being performed by the ERDADS computer system The QSPDS obtains these values from the heated and unheated junction thermocouples located inside the reactor. They are positioned between the head and upper fuel alignment plate in the reactor internals

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10 ACTIVATION AND OPERATION OF THE 49 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5B f12 ERDADS DATA POINTS (Page 4 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION ReactorVessel Unit 1 Level Information Head and Plenum together Level %

(continued) Location*

(* in. to fuel) Level Value if Sensor alignment plate) Segment (%M Uncovered (%M None 100 1 186 / 20 80 2 144318 19 61 3 108 18 43 4 71518 14 29 5 50518 10 19 6 29518 7 12 7 195/8 5 7 8 105/8 7 0 Unit 2 Level Information Head and Plenum together Location*

(* in. to fuel) Level Value if Sensor alignment plate) Segment (%) Uncovered (%M None 100 1 170 Y 52 48 2 140% 28 20 3 111 1/8 20 0 None 100 4 985/8 18 82 5 745/8 21 61 6 535/8 20 41 7 325/8 19 22 8 125/8 22 0

REVISION NO: PROCEDURE TITLE: PAGE:

10 ACTIVATION AND OPERATION OF THE 50 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5B U2 ERDADS DATA POINTS (Page 5 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION HPSI Total HSITTLF-112 HPSI Flow Sum This parameter measures total HPSI flow and is Flow (GPM) denved from HPSI Header Flow signals FT3311-112.

FT3321-1/2, FT3331-1/2 and FT3341-1/2 which are square roots The signals are processed with a sum of inputs algonthm This function obtains the algebraic sum of values with a good status LPSI Total Flow QA0908-1/2 LPSI Flow Sum This parameter measures total LPSI flow and is (GPM) denved from LPSI Header Flow signals FT3312-1/2, FT3322-1/2, FT3332-1/2 and FT3342-1/2 which are square roots These signals are processed by an algorithm which provides a sum of the inputs This function obtains the algebraic sum of values with a

_good status.

Containment TE07-3B-1I2 Cntmnt N/A This parameter is a containment temperature Temp. (deg F) Temp instrument It is converted to engineenng units using a linear equation Containment OA0507-1/2 Cntmnt Average This parameter measures containment pressure and Pressure WR Press is a wide range indicator. It is derived from Wide (psig) Range Containment Pressure signals PT07-4A1-1/2 and PT07-4B1-1/2 which are linear. They are processed by an average with expanded quality algonthm. This function obtains the average of all values with a good status It also sets the quality of the result based on the number of values with good status, versus the total number of inputs The possible status values are,

"* Greater than 50% of all inputs have good status, result is good

"* Only one good value and the total inputs are 3 or more, the result is poor.

"* When there are no good data values, but there are some with poor or suspect, the result is poor.

"* The result is suspect for all other cases except all bad, in this case the result is bad

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10 ACTIVATION AND OPERATION OF THE PROCEDURE NO.: TECHNICAL SUPPORt CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5B 112 ERDADS DATA POINTS (Page 6 of 8)

POINT PT 10 POINT TYPE NOTES DESCRIPTION NAME CALCULATION Containment QAOOO8-112 Cntmnt Maximum This parameter is a containment sump wide range Sump Level Smp WR instrument. It is denved from Containment Sump WR (Ft) Level signals LT07-13A-112 and LT07-13B-1/2 which are linear. They are processed by a signal auctioneering maximum algorithm. This function finds the highest usable data value in the specified group Each data value of the group and its quality is examined and the following rules are used

" For two or more usable data values, the result is the highest usable data value and the quality is the lowest quality of the usable data

" For only one usable data value, the result is set to that value and the quality is poor.

"* For no usable data, the value of the result is set to the highest of all the (bad) data and the quality is bad Containment CH2-1/2 H2 Conc Average This parameter is a containment hydrogen average Hydrogen (%) concentration measurement. Itis derived from Hydrogen Concentration signals A-HYDROGEN-1/2 and B-HYDROGEN-1/2 which are linear. These signals are processed by an average with expanded quality algonthm This function obtains the average of all values with a good status It also sets the quality of the result based on the number of values with good status, versus the total number of inputs The possible status values are

"* Greater than 50% of all inputs have good status, result is good

"* Only one good value and the total inputs are 3 or more, the result is poor.

SG Level A WR LT9012-1/2 SG Level A N/A This parameter is the "A" steam generator wide range

(%) level instrument Itis converted to engineenng units using a linear equation LTCL =Lower Tap Center Line The lower tap is 19 5 inches above the bottom of the U tubes.

SG Level B WR LT9022-1/2 SG Level B N/A This parameter is the "B"steam generator wide range

(%) level instrument Itis converted to engineenng units using a linear equation LTCL =Lower Tap Center Line. The lower tap is 19 5 inches above the bottom of the U tubes.

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10 ACTIVATION AND OPERATION OF THE 52 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5B t2 ERDADS DATA POINTS (Page 7 of 8)

POINT POINT TYPE DESCRIPTION NAME CALCULATION SG Pressure A 0A0021-1/2 SG Pres IA Redundant Sensor This parameter is the "A" steam generator pressure.

(psig) Algorithm It is derived from three Steam Generator Pressure Signals, PT8013A-1/2, PT8013B-112 and PT8013C-1/2, which are linear These signals are processed by a redundant sensor algorithm. This function obtains the average of the current values that have a good status and are close to the statistical majonty SG Pressure B QA0022-1/2 SG Pres /B Redundant Sensor This parameter is the "B" steam generator pressure (psig) Algorithm It is denved from three Steam Generator Pressure Signals, PT8023A-1/2, PT8023B-1/2 and PT8023D-1/2, which are linear. These signals are processed by a redundant sensor algorithm. This function obtains the average of the current values that have a good status and are close to the statistical majonty Refueling RWTAL-1/2 BWST Average This parameter measures refueling water tank level.

Water Tank Level It is derived from three inputs. They are LT07-2A-1/2, Avg Level (Ft.) LT07-2B-1/2 and LT07-2C-112 These points are processed by an average with expanded quality algonthm This function obtains the average of all values with a good status It also sets the quality of the result based on the number of values with good status, versus the total number of inputs The possible status values are

Greater than 50% of all inputs have good status, result is good

Only one good value and the total inputs are 3 or more, the result is poor.

When there are no good data values, but there are some with poor or suspect, the result is poor.

The result is suspect for all other cases except all bad, in this case the result is bad Tank bottom refers to zero gallons.

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10 ACTIVATION AND OPERATION OF THE 53 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 5B 52 ERDADS DATA POINTS (Page 8 of 8)

POINT PT ID POINT TYPE NOTES DESCRIPTION NAME CALCULATION CHRRM. Unit 1: Cntmnt Maximum The high containment radiation instruments for Unit 1 Channel (RIHR) Rad are the "A" side monitor RE 26-58-1 and the "B" side RE 26-58-1 monitor RE 26-59-1. These monitors are only range (A Channel) checked and flagged bad if out of range Both detectors are located at the 90 foot containment RE 26-59-1 elevation and are positioned at 0 and 180 degrees B Channel)

Unit 2. The high containment radiation instruments for Unit 2 are the "A" side monitor RIM 26-40-2 and the "B" side RIM 26-40-2 monitor RIM 26-41-2. These monitors are only range (A Channel) checked and are flagged bad if out of range Both detectors are located at the 90 foot containment RIM 26-41-1 elevation and are positioned at 0 and 180 degrees.

(B Channel) I END OF ATTACHMENT 5B

REVISION NO.: PROCEDURE TITLE: PAGE:

10 ACTIVATION AND OPERATION OF THE 54 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 6 TSC ADMINISTRATIVE STAFF CHECKLIST (Page 1 of 4)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

2. Verify procedures by posting revision numbers on the status board. Post all procedures (EPIP, HP, Chem.). Consult Control Copy 5 in the TSC document cabinets or follow the steps below to print out an EPIP list:

a. On the Nuclear Notes Page, PSL Notes Applications, CLICK on "Procedures".

b. On the PSL Documents page, CLICK on "Procedures".

c. On the "Search" toolbar, CLICK the far right tab labeled "More".

d. In the lower middle portion of the expanded "Search" toolbar, CLICK on "Load Search".

e. SELECT "Group Search (Shared)" from the drop down menu.

f. In the "Search for" line, TYPE "EP" (where the "XX" is).

g. CLICK on "Search" or HIT "Enter".

h. EPIP list is now displayed (procedures are not in any particular order).

To print the list, Click on "Print Index".

3. Telecopy the EC Log, completed notification forms and checklists, and any other pertinent information to the EOF.

REVISION NO.: PROCEDURE TITLE: PAGE.

10 ACTIVATION AND OPERATION OF THE 55 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 6 TSC ADMINISTRATIVE STAFF CHECKLIST (Page 2 of 4)

A. FACILITY ACTIVATION (continued) INITIAL

4. ESTABLISH the Videolink as follows:

a. Using the key on the keychain labeled "Videolink" in the administrative supplies, UNLOCK the electronic cabinet in the Problem Solving Team area.

b. DIAL the leftmost dial (#1), on the Shure Professional Microphone Mixer, to zero. This will eliminate the "test tone".

c. DIAL the TSC PA Volume dial on the Radio Shack TSC PA Controller to the second or third setting (dot) to establish microphone volume level.

d. SET the television to channel 13 to monitor the videolink in the TSC.

B. FACILITY OPERATION NOTE Information should be updated every 15-30 minutes and not longer than 60 minutes.

1. Synchronize the facility clock(s) with ERDADS. In case of ERDADS failure, synchronize with the affected Control Room.

2. Steps to occur continually while the facility is in operation:

a. Obtain the following ERDADS data sheets (printouts) from the ERDADS Operator:

1. Safety Functions Equipment Status (SF 1/2).

2. Radioactive Gaseous Source Terms (RG 1/2).

b. Update status boards with new ERDADS data.

c. Request the sound-powered phonetalker to obtain any information/data not provided by the ERDADS printouts.

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10 ACTIVATION AND OPERATION OF THE 56 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 6 TSC ADMINISTRATIVE STAFF CHECKLIST (Page 3 of 4)

B. FACILITY OPERATION (continued) INITIAL

2. (continued)

d. Verify all data has been accurately transferred to the status board.

e. Update the sequence of events board following each facility briefing and as needed. Provide relevant information concerning items such as:

1. Change in classification.

2. Significant change in plant condition.

3. Status of plant system(s) of concern.

4. Injured personnel status.

5. Other items of relevant interest.

f. Update dose assessment and field monitoring data as information is provided by Chemistry and HP, respectively.

g. Make corrections, when identified, by circling the corrected data.

h. When all status board columns/blanks are filled, erase the first two columns/blanks, enter new data with a different colored marker leaving a space between the new and the old data.

I. Provide any incoming telecopy materials to the TSC Supervisor or as designated on the cover page.

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10 ACTIVATION AND OPERATION OF THE 57 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 6 TSC ADMINISTRATIVE STAFF CHECKLIST (Page 4 of 4)

C. FACILITY CLOSEOUT AND RESTORATION INITIAL

1. Status boards have been cleaned and returned to preactivation condition.

2. Videolink has been terminated as follows:

a. DIAL the TSC PA Volume dial on the Radio Shack TSC PA Controller to the minimum setting.

b. DIAL the leftmost dial (#1) on the Shure Professional Microphone Mixer to about 8.5 to establish the "test tone". The needle on the VU Gauge should be just into the red area for adequate "test tone" level.

c. SET the television to the FPL channel.

d. LOCK the electronics cabinet and RETURN key to the administrative supplies box.

3. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

4. Returned position notebook to storage cabinet.

END OF ATTACHMENT 6

REVISION NO.: PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 58 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 7 TSC COORDINATOR WITH OSC CHECKLIST (Page 1 of 1)

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION

1. Establish contact with the OSC Coordinator with the TSC (in the OSC).

2. Steps to occur continually while the facility is in operation:

a. Track all requests for Re-entry Teams using Attachment 7A, Re-entry Log.

b. Communicate re-entry requests to the OSC Coordinator with the TSC per Attachment 7A, Re-entry Log.

c. Update the OSC Status Board with Re-entry Team information.

C. FACILITY CLOSEOUT AND RESTORATION

1. Closed out all Re-entry Teams entered in the Re-entry Team Log and the status board.

2. Status board has been cleaned and returned to preactivation condition.

3. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

4. Returned position notebook to storage cabinet.

END OF ATTACHMENT 7

REVISION NO: PROCEDURE TITLE PAGE:

10 ACTIVATION AND OPERATION OF THE 59 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 7A

¶6 RE-ENTRY LOG (Page 1 of 1)

TASK REQUEST (TSC)

The TSC fills in this section and communicates the information to the OSC.

El Investigate El Repair Dl Other A. Description B. 0l EC Review/Approval, as necessary. 0 C TSC

Contact:

Phone:

TEAM ASSIGNMENT (OSC)

The OSC fills in this section and communicates the information to the TSC.

D. Team No: E. Re-entry Supv.:

F. Time Out: G. Time In:

TASK REQUEST (TSC)

The TSC fills in this section and communicates the information to the OSC.

El Investigate El Repair El Other A. Description B. El EC Review / Approval, as necessary.

C. TSC

Contact:

Phone:

TEAM ASSIGNMENT (OSC)

The OSC fills in this section and communicates the information to the TSC.

D. Team No: E. Re-entry Supv.:

F. Time Out: G. Time In:

PSL-F086 Effective Date: 07131/02 END OF ATTACHMENT 7A

REVISION NO: PROCEDURE TITLE' PAGE 10 ACTIVATION AND OPERATION OF THE 60 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 8 TSC OPS COORDINATOR CHECKLIST (Page 1 of 4)

NOTE

1. This position is filled by two persons, one located in the affected Control Room, the other in the TSC. The position in the Control Room is also known as the NPS Communicator.

2. When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL NOTE The first person to arrive at the TSC should report to the affected Control Room to relieve the Duty Call Supervisor.

1. Filling position in:

2. (TSC position only) Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION

1. Establish communications with counterpart.

2. In the TSC, establish the OPS Conference Bridge as follows:

a. Obtain contact phone numbers for:

1. OPS Coordinator in the Control Room

2. OSC OPS Re-entry Supervisor

3. Problem Solving Team

4. Other participant

b. Call the OPS Coordinator

1. State: "stay on the line"

2. Depress the conference button

REVISION NO

PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 61 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 8 TSC OPS COORDINATOR CHECKLIST (Page 2 of 4)

B. 2. (continued) INITIAL

c. Call the OSC OPS Re-entry Supervisor

1. State: "stay on the line"

2. Depress the conference button

d. Call the Problem Solving Team

1. State: "press handsfree/mute button"

2. Depress the conference button

e. Call any other participant

1. State: "stay on the line"

2. Depress the conference button

f. Hail all parties to verify bridge successfully established.

3. Initiate the OPS Logbook. (TSC only)

4. Steps to occur continually while the facility is in operation:

TSC

a. Provide expertise in plant operations to the EC.

b. Maintain communication flow between the TSC and the affected Control Room concerning status of operations.

c. Maintain OPS Logbook.

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10 ACTIVATION AND OPERATION OF THE 62 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 8 TSC OPS COORDINATOR CHECKLIST (Page 3 of 4)

B. 4. (continued) INITIAL

d. Severe Accident Management Guidelines (SAMG) actions

1. Perform evaluations in accordance with ADM-1 7.09, Invoking 10 CFR 50.54(x), as needed.

2. Review/approve actions as outlined in Attachment 12B, Problem Solving Team Worksheet.

3. Communicate SAMG actions to the affected Control Room(s).

Control Room

a. Provide communications assistance to the NPS.

b. Monitor procedure use and keep the TSC informed.

c. Investigate questions/concerns as requested by the TSC.

d. Update the unaffected unit's Control Room with emergency status.

e. Gather Severe Accident Management Guidelines (SAMG) instructions/information from the TSC OPS Coordinator.

1. If the TSC is unable to telecopy, Then use Attachment 12B, Problem Solving Team Worksheet, to record SAMG instructions/ information.

f. Communicate SAMG actions to the NPS.

g. Provide feedback to the TSC OPS Coordinator regarding SAMG actions.

REVISION NO: PROCEDURE TITLE PAGE.

10 ACTIVATION AND OPERATION OF THE 63 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 8 TSC OPS COORDINATOR CHECKLIST (Page 4 of 4)

C. FACILITY CLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Phone connection terminated.

2. Closed out the OPS Logbook.

3. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

4. Returned position notebook to storage cabinet.

END OF ATTACHMENT 8

REVISION NO: PROCEDURE TITLE. PAGE' 10 ACTIVATION AND OPERATION OF THE 64 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 9 TSC REACTOR ENGINEER CHECKLIST (Page 1 of 3)

NOTE When necessary or appropriate, steps in this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION

1. Establish the ERDADS link with the NRC Emergency Response Data System (ERDS) (use Attachment 9A, Initiating and Terminating the ERDS Link).

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10 ACTIVATION AND OPERATION OF THE 65 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 9 TSC REACTOR ENGINEER CHECKLIST (Page 2 of 3)

B. (continued) INITIAL

2. Steps to occur continually while the facility is in operation:

CAUTION Be aware of the following conditions. These Emergency Action Levels (EALs) are associated with Initiating Conditions (ICs) used in the classification of emergencies (EPIP-01, Classification of Emergencies).

The Emergency Coordinator needs to know if any of these conditions exist.

1. Dose Equivalent Iodine (DEQ) 1-131 activity greater than 275 pCi/ml.

2. CHHRM readings greater than 7.3E+03 R/hr OR greater than 1.46E+05 R/hr.

3. Post LOCA Monitor readings greater than 100 mR/hr OR greater than 1000 mR/hr.

4. Step increase in radiation monitor readings in the Plant Vent and/or Fuel Handling Building.

5. Loss of subcool margin resulting in saturated conditions.

6. Highest Core Exit Thermocouple (CET) per core quadrant indicates greater than 100F superheat or 700°F.

7. Damage to more than one irradiated fuel assembly.

8. Uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.

a. Monitor critical plant parameters for indications of core status.

b. Assist Nuclear Fuels personnel in the EOF in the assessment of core damage in accordance with EPIP-1 1, Core Damage Assessment.

c. Assist in Severe Accident Management Guidelines (SAMG) activities as a SAMG Evaluator.

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10 ACTIVATION AND OPERATION OF THE 66 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 9 TSC REACTOR ENGINEER CHECKLIST (Page 3 of 3)

C. FACILITY CLOSEOUT AND RESTORATION INITIAL NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Core damage assessment activities terminated.

2. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

3. Returned position notebook to storage cabinet.

END OF ATTACHMENT 9

REVISION NO.: PROCEDURE TITLE: PAGE.

10 ACTIVATION AND OPERATION OF THE 67 of 82 PROCEDURE NO. TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 9A INITIATING AND TERMINATING THE ERDS LINK (Page 1 of 2)

NOTE There is a laminated card in the supply box for the Problem Solving Team that provides the password and keystrokes for initiating and terminating the ERDS Link.

This attachment 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).

INITIATING 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 ## XXXXXXXX (the Xs stand for the password issued to Operations Support Engineering). 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.

4. 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 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.

REVISION NO

PROCEDURE TITLE: PAGE 10 ACTIVATION AND OPERATION OF THE 68 of 82 PROCEDURE NO' TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 9A INITIATING AND TERMINATING THE ERDS LINK (Page 2 of 2)

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.

", 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 ## XXXXXXXX (the Xs stand for the password issued to Operations Support Engineering). 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.

4. 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 terminate 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 EXEC key.

END OF ATTACHMENT 9A

REVISION NO: PROCEDURE TITLE. PAGE:

10 ACTIVATION AND OPERATION OF THE 69 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 10 TSC CHEMISTRY SUPERVISOR CHECKLIST (Page 1 of 3)

NOTE When necessary or appropriate, steps in this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION

1. Initiate the Chemistry Logbook.

2. Steps to occur continually while the facility is in operation:

NOTE Dose assessment shall be a primary responsibility of the EOF once it becomes operational.

a. Supervise dose assessment activities.

b. Review all dose projection printouts.

c. Advise the EC of dose projection results.

d. Assist the EC in evaluating off-site dose estimates for PARs.

e. Assist the TSC EC Assist/Logkeeper/EC in determining the "Off-site Release Significance Category" as called for on the State Notification Form, as necessary.

f. Provide technical support to the OSC Chemistry Supervisor.

REVISION NO.: PROCEDURE TITLE' PAGE:

10 ACTIVATION AND OPERATION OF THE 70 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 10 TSC CHEMISTRY SUPERVISOR CHECKLIST (Page 2 of 3)

B. 2. (continued)

CAUTION Be aware of the following conditions. These Emergency Action Levels (EALs) are associated with Initiating Conditions (ICs) used in the classification of emergencies (EPIP-01, Classification of Emergencies).

The Emergency Coordinator needs to know if any of these conditions exist.

1. Dose Equivalent Iodine (DEQ) 1-131 activity greater than 275 pCi/ml.

2. Result of analysis of a gaseous or liquid release is greater than ten (10) times the ODCM limit.

3. CHHRM readings greater than 7.3E+03 R/hr OR greater than 1.46E+05 R/hr.

4. Post LOCA Monitor readings greater than 100 mR/hr OR greater than 1000 mR/hr.

5. Step increase in radiation monitor readings in the Plant Vent and/or Fuel Handling Building.

6. Off-site dose calculation worksheet values at one (1) mile in excess of 50 mrem/hr (total dose - TEDE) or 250 mrem/hr (thyroid dose - CDE) for one half (1/2) hour OR 500 mrem/hr (total dose - TEDE) or 2500 mrem/hr (thyroid dose - CDE) for two (2) minutes.

7. Off-site dose calculation worksheet values indicate site boundary (one (1) mile) exposure levels have been exceeded as indicated by any of the following:

a. 1000 mrem/hr (total dose rate)

b. 1000 mrem (total dose -TEDE)

c. 5000 mrem/hr (thyroid dose rate)

d. 5000 mrem (thyroid dose - CDE)

g. Advise the EC on plant chemistry related matters.

h. Maintain chronological log of activities.

REVISION NO: PROCEDURE TITLE: PAGE:

10 ACTIVATION AND OPERATION OF THE PROCEDURE NO" TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 10 TSC CHEMISTRY SUPERVISOR CHECKLIST (Page 3 of 3)

B. 2. (continued) INITIAL

i. Review and verify radiological and protective action information entered on status boards.

C. FACILITY CLOSEOUT AND RESTORATION

1. Dose assessment activities terminated.

2. Closed out the Chemistry Logbook.

3. Provided all paperwork (not bound in the position notebook) to the TSC Supervisor.

4. Returned position notebook to storage cabinet.

END OF ATTACHMENT 10

REVISION NO.: PROCEDURE TITLE* PAGE:

10 ACTIVATION AND OPERATION OF THE 72 of 82 PROCEDURE NO' TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 11 TSC DOSE ASSESSOR CHECKLIST (Page 1 of 2)

NOTE When necessary or appropriate, steps in this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION NOTE

1. Initial operating instructions for use of the Class A Model are provided in EPIP-09, Off-site Dose Calculations.

2. If the computerized Class A Model is not available, dose projections shall be performed in accordance with EPIP-09.

1. Ensure all previous dose calculation paperwork is sent to the EOF.

2. Establish communication link with the EOF Dose Assessor.

3. Complete Class A Model QC Check.

4. Steps to occur continually while the facility is in operation:

a. Obtain input data for the Class A Model from the ERDADS Operator (RG 1/2 Screen).

b. Report dose projection results to the TSC Chemistry Supervisor.

c. Coordinate dose assessment with the EOF unless directed otherwise by the TSC Chemistry Supervisor.

REVISION NO.: PROCEDURE TITLE: PAGE:

10 ACTIVATION AND OPERATION OF THE 73 of 82 PROCEDURE NO.' TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 11 TSC DOSE ASSESSOR CHECKLIST (Page 2 of 2)

B. 4. (continued) INITIAL

d. Provide status board update information to the TSC Administrative Staff (use Attachment 11 A and Attachment 11B).

1. Using carbon paper, make a copy as data is entered into the form in either Attachment 11 A or 11 B.

Retain the original, provide the copy to the TSC Administrative Staff to update the status boards.

C. FACILITY CLOSEOUT AND RESTORATION

1. Dose projection activities terminated.

2. EOF communications linked terminated.

3. All documents, equipment and supplies returned to preactivation condition and/or location.

4. All paperwork collected.

5. Provided all completed paperwork (not bound in the position notebook) to the TSC Chemistry Supervisor.

6. Returned position notebook to storage cabinet.

END OF ATTACHMENT 11

. p 7 PAL K

REVISION Nu: PROCEDURE TITLE: PAG*

10 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER 74 of 82 PROCEDURE NO.:

EPIP-04 ST. LUCIE PLANT ATTACHMENT 11A OFF-SITE RADIOLOGICAL ASSESSMENT (Page 1 of 1)

OFFSITE DOSE RADIOLOGICAL ASSESSMENT STATUS AND TRENDS PARAMETER Unit Highest Downwind Sector Dose Rates Day # of Month Time of Day 2400 Downwind Sectors Dose Rate @ TEDE CDE TEDE CDE TEDE CDE TEDE CDE 1 mile mRem/hr 2 miles mRem/hr 5 miles mRem/hr 10 miles mRem/hr Wind Direction at 10 meter elev Degrees Downwind Sector Wind Speed at 10 meter elev mph 60 meter- 10 meter delta T Deg F Stability Class 10 meter Temperature Deg F Noble Gas Rel Rate Q/sec Iodine Rel Rate Cl/sec Noble Gas Total Ci Ci Iodine Total Ci Ci Contain Hi Range R/hr Vent Ci/sec ECCS A Ci/sec ECCS B Cl/sec Main Steam A mR/hr Main Steam B mR/hr TEDE = Total Dose CDE = Thyroid Dose END OF ATTACHMENT 11A

REVISION NO: PROCEDURE TITLE' PAGE' 10 ACTIVATION AND OPERATION OF THE 75 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 11B PROTECTIVE ACTION RECOMMENDATIONS (Page 1 of 1)

PROTECTIVE ACTION RECOMMENDATIONS REASON:

ISSUED BY: DATE/TIME:

S = SHELTER E = EVACUATE SECTOR 0 - 2 Miles 2 - 5 Miles 5 - 10 Miles A (N)

B (NNE)

C (NE)

D (ENE))

E (E F (ESE)

G (SE )

H (SSE)

J (S )

K (SSW)

L (SW)

M (WSW)

N (W )

P (WNW)

Q (NW)

R (NNW)

ADDITIONAL COMMENTS END OF ATTACHMENT 11B

REVISION NO: PROCEDURE TITLE: PAGE' 10 ACTIVATION AND OPERATION OF THE 76 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 12 TSC PROBLEM SOLVING TEAM CHECKLIST (Page 1 of 2)

NOTE

1. This checklist applies to the following Problem Solving Team (PST) positions:

TSC PST Leader (Engineering)

TSC Elec Rep - PST TSC I&C Rep - PST TSC Mech Rep - PST (3) TSC SRO Rep - PST

2. When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

B. FACILITY OPERATION NOTE

1. Refer to the Document Control Index for a listing of Tech Manuals available in the TSC.

2. The computer provides a LAN connection and access to the Total Equipment Database (TEDB).

1. Steps to occur continually while the facility is in operation:

a. Problem Solving Team Leader

1. Maintain command and control of all PST activities.

The form provided in Attachment 12A, PST Activities List may be used by the PST to track and communicate the status of PST activities.

2. Ensure all PST members are aware of and understand the status of equipment.

3. Maintain high level of inquiry and investigation by all PST members.

4. Track progress of all requests for PST assistance.

REVISION NO

PROCEDURE TITLE' PAGE 10 ACTIVATION AND OPERATION OF THE 77 of 82 PROCEDURE NO. TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 12 TSC PROBLEM SOLVING TEAM CHECKLIST (Page 2 of 2)

B. 1. a. (continued) INITIAL

5. Encourage development of multiple success paths.

6. Review all Worksheets (Attachment 12B).

b. Problem Solving Team Member

1. Participate as a member of the Problem Solving Team by providing technical support in your area of expertise.

2. Evaluate system and equipment failures.

3. Propose mitigative and corrective action(s) as promptly as possible.

4. Document recommendations on a form similar to Attachment 12B, Problem Solving Team Worksheet.

5. Serve as a Severe Accident Management Guidelines (SAMG) Evaluator.

6. Provide all recommendations to the EC.

C. FACILITY CLOSEOUT AND RESTORATION NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Returned all documents, equipment and supplies to preactivation condition and/or location.

2. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

3. Returned position notebook to storage cabinet.

END OF ATTACHMENT 12

/K' REVISION NU: PROCEDURE TITLE: PAG E:

10 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER 78 of 82 PROCEDURE NO:

EPIP-04 ST. LUCIE PLANT

___________ I &

ATTACHMENT 12A PST ACTIVITIES LIST (Page 1 of 1)

Item Problem Description Probable Cause PST Recommendation Status

-& 4 1* f 1 4 t

_____ 1 4. 4 1 I i t t I -t t T 4- 4 1 1

______ +/- L END OF ATTACHMENT 12A

REVISION NO: PROCEDURE TITLE PAGE 10 ACTIVATION AND OPERATION OF THE 79 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 12B

%6 PROBLEM SOLVING TEAM WORKSHEET (Page 1 of 1)

TO: PST

SUBJECT:

DATE & TIME RECEIVED: REQUESTER:

REQUEST:

RESPONSE

50.59 50.54(x) SAMG N/A X I (SRO Approval)

BY: VERIFIED:

PROBLEM SOLVING TEAM LEADER:

1lATF: & TIME: CD I~~~~ DATE&_____TIME:___

PST

Contact:

Ph. No.:

Status: Date: - / , Time:

EC Review:

END OF ATTACHMENT 12B

REVISION NO: PROCEDURE TITLE: PAGE.

10 ACTIVATION AND OPERATION OF THE 80 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 13 TSC SECURITY SUPERVISOR CHECKLIST (Page 1 of 3)

NOTE When necessary or appropriate, steps of this checklist may be performed out of sequence.

A. FACILITY ACTIVATION INITIAL

1. Refer to Section 5 of this procedure (included in the position notebook) and review the general instructions.

2. Verify that the Energy Encounter has been notified of the emergency. (consult the ERD Section 3.6, other company numbers, for the phone number)

B. FACILITY OPERATION

1. Establish access control for the TSC.

2. Contact the Control Rooms and request a completed "Operations Department Accountability Aid" be forwarded to the TSC.

3. Initiate facility accountability by requesting a completed copy of Attachment 3A, TSC ERO Shift Staffing and Accountability Roster from the TSC Supervisor.

4. Telecopy the completed Attachment 3A, TSC ERO Shift Staffing and Accountability Roster, and the "Operations Department Accountability Aid" forms to Security.

5. Contact the EOF Emergency Security Manager (ESM).

a. Establish responsibility/protocol for notification of off-site authorities regarding the status of site evacuation.

REVISION NO: PROCEDURE TITLE PAGE 10 ACTIVATION AND OPERATION OF THE 81 of 82 PROCEDURE NO: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 13 TSC SECURITY SUPERVISOR CHECKLIST (Page 2 of 3)

B. (continued) INITIAL

6. Upon declaration of a Site Area Emergency.

a. Start accountability at:

b. Start sweeps at:

1. Off-site work areas.

2. West forty and Fitness Center.

3. Owner Controlled Area.

a. Beach side.

b. River side.

4. On-site and Radiation Controlled Area.

5. Marine Research Center.

c. Accountability completed at

d. Sweeps completed at

7. Steps to occur continually while the facility is in operation:

I CAUTION Ensure the EC is aware of any actions required by the Security Plan (e.xi., alert or emergency declaration, suspension of safeguards, etc.

a. Advise the EC on Security related manners.

REVISION NO.: PROCEDURE TITLE: PAGE:

10 ACTIVATION AND OPERATION OF THE 82 of 82 PROCEDURE NO.: TECHNICAL SUPPORT CENTER EPIP-04 ST. LUCIE PLANT ATTACHMENT 13 TSC SECURITY SUPERVISOR CHECKLIST (Page 3 of 3)

B. 7. (continued) INITIAL

b. In conjunction with the ESM, provide liaison function between local law enforcement and rescue agencies and FPL for issues such as:

1. Bomb threats or acts of terrorism.

2. Member of the public or media arriving at the site.

3. Site egress and ingress.

4. Fire or rescuelmedical response.

c. Coordinate safeguards suspension with the ESM and EC.

d. Maintain site accountability of all personnel throughout the emergency.

e. Follow Security Procedures.

C. FACILITY CLOSEOUT AND RESTORATION NOTE All paperwork completed in the position notebook should remain in the position notebook.

1. Closed out with the local law enforcement agencies, as needed.

2. Closed out Security Logbook.

3. All paperwork collected.

4. Provided all completed paperwork (not bound in the position notebook) to the TSC Supervisor.

5. Returned position notebook to the storage cabinet.

END OF ATTACHMENT 13

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