Text

Revision 4 to EPIP-01, Classification Emergencies.
	ML021960053
Person / Time
Site:	Saint Lucie
Issue date:	07/11/2002
From:	Jernigan D; Florida Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2002-134 EPIP-01, Rev 4
	Download: ML021960053 (33)
	v • d • e

Florida Power & Light Company, 6501 South Ocean Drive, Jensen Beach, FL 34957 0'*IFPL July 11, 2002 L-2002-134 10 CFR 50 Appendix E U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Emergency Plan Implementing Procedure In accordance with 10 CFR 50 Appendix E, enclosed is a copy of a revised implementing procedure for the St. Lucie Plant Radiological Emergency Plan:

Number Title Revision Implementation Date EPIP-01 Classification of Emergencies 4 June 28, 2002 EPIP-01 was revised in accordance with Revision 40 to the St. Lucie Plant Radiological Emergency Plan. The following revisions were made: 1) Initiating Conditions (IC) for RCS leakage were revised, 2) Emergency Action Levels (EAL) under security threat Initiating Conditions were added, 3) definitions for EAL and IC were added, 4) guidance for multiple and dual unit events was added, and 5) several editorial and administrative changes were made.

Plea§ cont ct us if there are any questions regarding this procedure.

Very yours, onald E. Jernigan Vice President St. Lucie Plant DEJ/tit Enclosure an FPL Group company

Procedure No.

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

IMPLEMENTING PROCEDURE 4 FPL SAFETY RELATED Effective Date 06/28/02

Title:

CLASSIFICATION OF EMERGN E Responsible Department: EMERGENCY PLANNING REVISION

SUMMARY

I L1 Revision 4 - Revised lAW revision to E-Plan (R40). Revised ir ifl_9fi_1ttd ,-,mWý leakage. Added EALs under security threat initiating condition. Added definitionsT fo&EL 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 1 - Revised to RCS EAL for alert based on NESP007 guidance. (J. R. Walker, 04/21/00)

T 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-01 4 05/23/02 D. Rose 05/23/02 SYS Plant General Manager COM COMPLETED N/A ITM 4 Designated Approver N/A Designated Approver (Minor Correction)

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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 D E F INIT IO NS ............................................................................................ 5 5.0 INSTR UCT IO NS ...................................................................................... 9 ATTACHMENTS ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE .......................... 13

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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:

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, etc. aind shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶ Indicates a management directive, vendor recommendation, plant pract ice or other non-regulatory commitment that should NOT be revised withou t consultation with the plant staff.

1! 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

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

5. 11 NUREG-1022, Section 3.1.1

6. 12 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.

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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.

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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

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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:

1. 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.

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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

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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

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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 Lucie Plant Radiological Emergency Plan.

St.

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.

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

5. ¶2 If an 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

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EPIP-01 ST. LUCIE PLANT 5.3 ¶1 Classification of An Event Based On Subsequent Information

1. If subsequent information of a more detailed nature (e.g., sampling results) becomes available after the initial classification 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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EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 1 of 20)

CAUTION

§2 Section 1.A should not be used for a steam generator tube leak/rupture.

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1.A. ABNORMAL PRIMARY Reactor Coolant System (RCS) Leakage RCS Leakage GREATER THAN 50 qpm LOCA GREATER THAN capacity of Arelease has occurred or is in progress LEAK RATE charging pumps resulting in:

(Page 1 of 2) 1. RCS leakage GREATER THAN 1. Unisolable RCS leakage as indicated by 10 gpm as indicated by: Charging/letdown mismatch greater 1. RCS leakage greater than available 1. Containment High Range Radiation than 50 gpm but less than available charging pump capacity occurring with monitor greater than 1.46 X 106 R/hr (If A. Control Room observation charging pump capacity. RCS pressure above HPSI shutoff CHRRM inoperable, Post-LOCA OR OR head. monitors greater than 1000 mR/hr).

B. Inventory balance calculation 2. Unisolable measured RCS leakage OR OR OR indicating greater than 50 gpm but less 2. RCS leakage greater than available 2. Performance of EPIP-09 (Off-site Dose C. Field observation than available charging pump capacity. makeup occurring with RCS pressure Calculations) or measured dose rates OR below HPSI shutoff head. from off-site surveys indicate site D. Emergency Coordinator judgement OR boundary (1 mile) exposure levels have AND 3. Loss of RCS subcooled margin due to been exceeded as indicated by either Inability to reduce the leak rate to RCS leakage (saturated conditions). A, B, C or D below:

technical specification limits within OR the timeframe of the action 4. Containment High Range Radiation A. 1000 mrem/hr (total dose rate) statement. Monitors indicate 7.3 X 103 R/hr (If NOTE CHRRM inoperable, Post-LOCA B. 1000 mrem (total dose - TEDE) monitors indicate between 100 and For RCS Leakage in Section 1 1000 mR/hr).

above, the (Notification of) C. 5000 mrem/hr (thyroid dose rate)

Unusual Event should be declared upon commencing a D. 5000 mrem (thyroid dose - CDE) load reduction/mode 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 psia Unit 2 - 1736 psia 1.A. ABNORMAL PRIMARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR I

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EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 2 of 20)

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I.A. ABNORMAL PRIMARY Loss of 2 of the 3 fission oroduct LEAK RATE barriers 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.

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

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

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

(Page 1 of 2) limits.

AND 1. Measured RCS to secondary 1. Measured RCS to secondary 1. Fuel element failure (confirmed

2. Secondary plant activity is leakage greater than Tech. Spec. leakage is greater than charging DEQ 1-131 activity greater than detected. Limits and within charging pump pump capacity. 275 pCi/mL).

capacity. AND AND AND 2. Secondary plant activity is 2. LOCA or Tube rupture on

2. Secondary plant activity is detected. unisolable steam generator.

detected. AND AND 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)

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 I

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

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1.B. ABNORMAL Rapid failure of steam generator §2 Rapid failure of steam generator PRIMARY TO tubes (GREATER THAN charging tube(s) (GREATER THAN charging SECONDARY LEAK pump capacity) pump capacity) with steam release in RATE progress (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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EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 5 of 20)

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I.C. LOSS OF Rapid depressurization of secondary Major steam leak with Major steam leak with A release has occurred or is in SECONDARY plant GREATER THAN 10 qpm GREATER THAN 50 qpm progress resulting in:

COOLANT primary/secondary leakage primary/secondary leakage and fuel (Page 1 of 2) 1. Rapid drop in either steam damage indicated 1. Containment High Range generator pressure to less than 1. Rapid drop in either steam Radiation monitor greater than 600 psia. generator pressure to less than 1. Rapid drop in either steam 1.46 X 105 PRhr (If CHRRM 600 psia. generator pressure to less than inoperable, Post-LOCA monitors AND 600 psia. greater than 1000 mR/hr).

2. Known pri/sec leak of greater AND OR than 10 gpm. 2. Known pri/sec leak of greater 2. Performance of EPIP-09 (Off-site AND than 50 gpm. Dose Calculations) or measured

3. Secondary plant activity is AND dose rates from off-site surveys detected. 3. Secondary plant activity is indicate site boundary (1 mile) 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) 1.C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 6 of 20)

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1.C. LOSS OF Loss of 2 of the 3 fission oroduct SECONDARY barriers with imminent loss of the COOLANT third (any two of the following exist (Page 2 of 2) 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.

1.C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR I

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

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 2.A. UNCONTROLLED Radiological effluent limits exceeded A release has occurred or is in §2 A release has occurred or is in A release has occurred or is in EFFLUENT RELEASE progress that is 10 times the effluent progress resulting in: progress resulting in:

1. Plant effluent monitor(s) exceed limit alarm setpoint(s). 1. Containment High Range 1. Containment High Range AND 1. Plant effluent monitor(s) Radiation Monitor greater than Radiation monitor greater than

2. Confirmed analysis results for significantly exceed alarm 7.3 X 103 R/hr (Post-LOCA 1.46 X 105 R/hr (If CHRRM gaseous or liquid release which setpoints. monitors indicate between inoperable, Post-LOCA monitors exceeds ODCM limits. AND 100 and 1000 mR/hr, if CHRRM greater than 1000 mR/hr).

2. Confirmed analysis results for inoperable). OR gaseous or liquid release which OR 2. Performance of EPIP-09 (Off-site exceeds 10 times ODCM limits. 2. Measured Dose Rates or Offsite Dose Calculations) or measured Dose Calculation (EPIP-09) dose rates from off-site surveys NOTE NOTE worksheet values at one mile in indicate site boundary (1 mile)

If analysis is not available within If analysis is not available within excess of: exposure levels have been one hour and it is expected that one hour and it is expected that exceeded as indicated by either A, release is greater than ODCM release is equal to or greater A. 50 mrem/hr (total dose rate) B, C or D below:

limit, classify as UNUSUAL than 10 times ODCM limit, or 250 mrem/hr (thyroid dose EVENT. classify as ALERT. rate) for 112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months . A. 1000 mrem/hr (total dose rate)

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)

ODCM - refers to Chemistry Procedure C-200, Offsite Dose Calculation Manual (ODCM) 2.A. UNCONTROLLED EFFLUENT RELEASE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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

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

1. Any valid area monitor alarm from indeterminable source with 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 concentration from an indeterminable 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

PAGE:

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

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

3. FIRE §2 Uncontrolled fire within the Power safety systems (e.g., 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 resulting in noise, heat and rapid expansion of gas.

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.g., 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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EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 10 of 20)

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

1. Process monitors or area 1. Process monitors or area radiation surveys indicate radiation surveys indicate 1. RCS DEQ 1-131 activity greater 1. Containment High Range increased letdown activity increased letdown activity and than or equal to 275 pCi/mL. Radiation monitor greater than AND confirmed RCS Samples AND 1.46 X 105 Rhr (If CHRRM

2. Confirmed RCS sample indicating DEQ 1-131 activity 2. Highest CET per core quadrant inoperable, Post-LOCA monitors indicating: greater than or equal to indicates greater than 100 F greater than 1000 mR/hr).

275 pCi/mL. superheat or 700°F. OR A. Coolant activity greater than 2. Performance of EPIP-09 (Off-site the Tech Spec limit for iodine Dose Calculations) or measured spike (Tech Spec dose rates from off-site surveys Figure 3.4-1.). indicate site boundary (1 mile)

OR exposure levels have been B. Coolant activity greater than exceeded as indicated by either A, 100/1 pCi/gram specific B, C or D below:

activity.

A. 1000 mrem/hr (total dose rate)

NOTE NOTE B. 1000 mrem (total dose - TEDE)

If analysis 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

REVISION NO.: PROCEDURE TITLE: PAGE:

4 CLASSIFICATION OF EMERGENCIES 23 of 32 PROCEDURE NO.:

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

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

1. Affected area radiation monitor

1. NPS/EC determines that an greater than 1000 mtrem/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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4 CLASSIFICATION OF EMERGENCIES 24 of 32 PROCEDURE NO.:

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

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

1. A confirmed earthquake has been 1. A confirmed earthquake has 1. A confirmed earthquake has Class 6.A.

experienced within the Owner occurred which registered occurred which registered Controlled Area. GREATER THAN 0.05g within the GREATER THAN 0.1g within the OR Owner Controlled Area. Owner Controlled Area and the plant

2. T4 An earthquake is detected by OR not in Cold Shutdown.

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

5.B. HURRICANE Hurricane Warning Hurricane warningq with winds near Hurricane warning with winds NOTE desigqn basis GREATER THAN desiqn basis Refer to Potential Core Melt Event /

Class 6.A.

1. Confirmed hurricane warning is in 1. Confirmed hurricane warning is in 1. Plant not at cold shutdown.

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

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. If that 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.

5.A. EARTHQUAKE 5.B. HURRICANE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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4 CLASSIFICATION OF EMERGENCIES 25 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 13 of 20)

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

Class 6.A.

5.D. ABNORMAL WATER Abnormal water level conditions are Flood, low water, hurricane surge or Flood, low water, hurricane surge or LEVEL expected or occurring other abnormal water level other abnormal water level conditions conditions causinq failure of vital

1. Low intake canal level of -10.5 ft. equipment 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 OR exceeded during hurricane surge 1. Flood/surge water level reaching

2. Visual sightings by station or known flood conditions. elevation +19.5 ft. (turbine personnel that water levels are OR building/RAB ground floor).

approaching storm drain system 2. Low intake canal level of -10.5 ft. OR capacity. 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 emergency barrier valves open. caused the loss of all ICW flow.

5.C. TORNADO 5.D. ABNORMAL WATER LEVEL AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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4 CLASSIFICATION OF EMERGENCIES 26 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 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 Emergencv Coordinator's iudgement that Emergency Coordinator's iudgement that §2 EmergencyvCoordinator's iudqement that §2 Emergency Coordinator's ludgement that 6.A. INCREASED §2 plant conditions exist which warrant plant conditions exist which have a plant conditions exist which are plant conditions exist that make release of AWARENESS OR lame amounts of radioactivity in a short POTENTIAL CORE MELT increased awareness on the part of the potential to deqrade the level of safety at significantly degrading in an uncontrollable operating staff and/or local authorities. the plant. manner. period appear possible or likely. (Any core (Page 1 of 2) melt situation.)

1. The plant is shutdown under abnormal conditions (e.g., exceeding cooldown

1. LOCA with failure of ECCS leading to rates or primary system pipe cracks are severe core degradation or melt.

found during operation).

OR OR 2. LOCA with initially successful ECCS

2. Any plant shutdown required by and subsequent failure of containment Technical Specifications in which the heat removal systems for greater than required shutdown is not reached 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

within action limits.

OR

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

N--

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4 CLASSIFICATION OF EMERGENCIES 27 of 32 PROCEDURE NO.:

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

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

(Page 2 of 2) Quicker releases are expected 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.

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

PROCEDURE TITLE: PAGE:

REVISION NO.:

4 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 Station Blackout (Total Loss of AC) Station Blackout (Total Loss of AC) NOTE 7.A. LOSS OF POWER Loss of off-site power or loss of all §2 §2 Refer to Potential Core Melt on-site AC power capability. for GREATER THAN 15 minutes Event / Class 6.A.

1. Loss of off-site AC power.

AND 1. Loss of offsite AC power.

1. Loss of off-site AC power.

2. Failure of both emergency diesel AND OR 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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4 CLASSIFICATION OF EMERGENCIES 29 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 17 of 20)

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 8.A. LOSS OF PLANT Loss of Plant Control Functions Critical Loss of Plant Control Functions NOTE CONTROL FUNCTIONS Refer to Potential Core Melt Event /

1. Complete loss of any function 1. Loss of any function or system Class 6.A.

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 subcritical 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 drill 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.

8.A. LOSS OF PLANT CONTROL FUNCTIONS AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR I

REVISION NO.: PROCEDURE TITLE: PAGE:

4 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 8.B. LOSS OF ALARMS / §2 Significant loss of effluent monitoring §2 Loss of alarms Loss of alarms/monitoring COMMUNICATION / capability, communications, MONITORING indication and alarm panels, etc., 1. Unplanned loss of most (greater 1. Inability to monitor* a significant which impairs ability to perform than 75%) or all safety system transient in progress.

accident or emergency assessment. annunciators.

AND

1. Loss of effluent or radiological 2. Plant transient in progress.

monitoring capability requiring plant shutdown.

OR

2. Loss of all primary and backup communication capability with 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 integrity.

8.B. LOSS OF ALARMS /

COMMUNICATION /

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

REVISION NO.: PROCEDURE TITLE: PAGE:

4 CLASSIFICATION OF EMERGENCIES 31 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 19 of 20)

EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 9.A. AIRCRAFT / 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.

threaten the safety of the plant or 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 Unplanned/uncontrolled toxic or Entry of toxic or flammable -gas into §2 Toxic or flammable gas has diffused FLAMMABLE GAS flammable gas release in the Owner areas potentially affecting plant into vital areas compromising the Controlled Area that could affect operation. function of safety related equipment plant/personnel safety. (e.g., 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

PAGE:

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4 CLASSIFICATION OF EMERGENCIES 32 of 32 PROCEDURE NO.:

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

ALERT SITE AREA EMERGENCY GENERAL EMERGENCY EVENT/CLASS UNUSUAL EVENT A successful takeover of the plant A SECURITY EMERGENCY A SECURITY EMERGENCY has including the Control Room or any A SECURITY ALERT has been involving imminent occupancy of the

10. SECURITY THREAT been called by the Security Force as other area(s) vital to the operation of called by the Security Force in control room or other area(s) vital to defined in the Safeguards the reactor (as per the Security Plan).

response to one or more of the items the operation of the reactor as Contingency Plan.

listed below. defined in the Safeguards Contingency Plan.

1. Bomb threat

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. Security Force strike

10. Credible site-specific Security threat notification

10. SECURITY THREAT OF THE EMERGENCY COORDINATOR A.FTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES

L-2002-134, Revision 4 to EPIP-01, Classification Emergencies.

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L-2002-134, Revision 4 to EPIP-01, Classification Emergencies.

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