L-2003-107, Emergency Plan Implementing Procedure

Emergency Plan Implementing Procedure

ML031140377
Person / Time
Site:	Saint Lucie
Issue date:	04/23/2003
From:	Jefferson W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2003-107
Download: ML031140377 (33)

Text

0 FPL Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 April 23, 2003 L-2003-107 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 the revised procedure that implements the St. Lucie Plant Radiological Emergency Plan.

Number Title Revision Implementation Date EPIP-01 Classification Of Emergencies 6

April 18, 2003 EPIP-01 Revision 6 incorporated a plant change request (PCR) to delete wording regarding technical specification limits and correctly place symbol references in the procedure.

Please contact us if there are any questions regarding this procedure.

VI Williahm Jefferson, Jr.

Vice President St. Lucie Plant WJ/tIt Enclosure 4P)-4 s an FPL Group company

Procedure No.

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

IMPLEMENTING PROCEDURE 6

F P L Effective Date SAFETY RELATED 04118/03

Title:

CLASSIFICATION OF EMERGENCIES Responsible Department: EMERGENCY PLANNING REVISION

SUMMARY

Revision 6 - Incorporated PCR #03-0403 to delete wording regarding technical specification limits and correctly place symbols. (J. R. Walker, 02/21/03)

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 NESPO07 guidance. (J. RpWalker, 04/21/00) 00 PCEURE P,9erO~uCi Revision FRG Review Date Approved By Approval Date S

OPS 0

12/15197 J. Scarola 12/15/97 DATE Plant General Manager DOCT PROCEDURE Revision FRG Review Date Approved By Approval Date DOCN EPIP-01 6

02/20/03 R. E. Rose 02/21/03 SYS Plant General Manager COM COMPLETED N/A ITM 6

Designated Approver N/A Designated Approver (Minor Correction)

REVISION NO:

PROCEDURE TITLE PAGE 6

CLASSIFICATION OF EMERGENCIES 2 of 32 PROCEDURE NO.

EPIP-01 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE...............

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

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PROCEDURE TITLE-PAGE 6

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:

Unusual Event Alert Site Area Emergency 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.

P 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.

11 NUREG-1022, Section 3.1.1

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PROCEDURE TITLE PAGE 6

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.

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6 CLASSIFICATION OF EMERGENCIES 5 of 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.

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6 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

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CLASSIFICATION OF EMERGENCIES 7 of 32 PROCEDURE NO.

EPIP-01 I

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 I 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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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

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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

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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.

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6 CLASSIFICATION OF EMERGENCIES 11 of 32 PROCEDURE NO:

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

5.

12 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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6 CLASSIFICATION OF EMERGENCIES 12 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT 5.3

§1 1ii 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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CLASSIFICATION OF EMERGENCIES 13 of 32 PROCEDURE NO 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.

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY' I A ABNORMAL PRIMARY Reactor Coolant System (RCS) Leakage

§1 RCS Leakage GREATER THAN 50 orpm LOCA GREATER THAN capacity of A release has occurred or is in orooress 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 than

1. RCS leakage greater than available I

Containment High Range Radiation 50 gpm but less than available charging charging pump capacity occurring with monitor greater than 1 46 X 105 R/hr (if A

Control Room observation pump capacity.

RCS pressure above HPSI shutoff CHRRM Inoperable, Post-LOCA OR OR head monitors greaterthan 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. EmergencyCoordinatorjudgement OR boundary (1 mile) exposure levels have OR 3

Loss of RCS subcooled margin due to been exceeded as indicated by either 2 Indication of leaking RCS safety or RCS leakage (saturated conditions)

A, B, C or D below:

relief valve which causes RCS OR pressure to drop below setpoints' 4

Containment High Range Radiation A

1000 mrem/hr (total dose rate)

Unit I - 1600 psla Monitors indicate 7.3 X 103 R/hr (If Unit 2 - 1736 psla CHRRM Inoperable, Post-LOCA B. 1000 mrem (total dose - TEDE) monitors Indicate between 100 and 1000 mR/hr)

C 5000 mrem/hr (thyroid dose rate)

D 5000 mrem (thyroid dose - CDE)

(continued on next page) 1 A ABNORMAL PRIMARY LEAK RATE FTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

C.

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CLASSIFICATION OF EMERGENCIES 14 of 32 PROCEDURE NO EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 2 of 20)

EVENT/CLASS 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 1.A. ABNORMAL PRIMARY LEAK RATE FTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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6 CLASSIFICATION OF EMERGENCIES 15 of 32 PROCEDURE NO:

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

EVENTICLASS 1.B.

ABNORMAL PRIMARY TO SECONDARY LEAK RATE (Page 1 of 2)

UNUSUAL EVENT RCS PRI/SEC Leakaae

1. Measured RCS to secondary leakage exceeds Tech Spec limits AND

2.

Secondary plant activity is detected.

ALERT Rapid gross failure of one steam generator tube (WITHIN charging pump capacity) with loss of offsite power

1. Measured RCS to secondary leakage greater than Tech. Spec.

Limits and within charging pump capacity.

AND

2. Secondary plant activity is detected.

AND

3. Loss of both Non-Vital 4 16 KV buses SITE AREA EMERGENCY Rapid gross failure of steam generator tubes (GREATER THAN charging pump capacity) with a loss of offsite power I

Measured RCS to secondary leakage is greater than charging pump capacity AND 2 Secondary plant activity is detected.

AND 3 Loss of both Non-Vital 4.16 KV buses.

GENERAL EMERGENCY Loss of 2 of the 3 fission product bamers with imminent loss of the third (any two of the following exist and the third is imminent)

1. Fuel element failure (confirmed DEQ 1-131 activity greater than 275 pCilmL).

AND 2

LOCA or Tube rupture on unisolable steam generator.

AND

3.

Containment integnty breached (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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6 CLASSIFICATION OF EMERGENCIES PROCEDURE NO.:

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

EVENT/CLASS 1 B.

ABNORMAL PRIMARY TO SECONDARY LEAK RATE (Page 2 of 2)

UNUSUAL EVENT ALERT Rapid failure of steam generator tubes (GREATER THAN charging pumr capacity)

I Measured RCS to secondary leakage greater than charging pump capacity.

AND 2

Secondary plant activity is detected.

SITE AREA EMERGENCY

§2 Rapid failure of steam generator tube(s) (GREATER THAN charging pump capacity) with steam release In progress

1. Measured RCS to secondary leakage greater than charging pump capacity AND

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.)

GENERAL EMERGENCY 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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CLASSIFICATION OF EMERGENCIES 17 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT I

ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 5 of 20)

EVENT/CLASS 1.C. LOSS OF SECONDARY COOLANT (Page 1 of 2)

UNUSUAL EVENT Rapid depressunzation of secondary plant

1. Rapid drop in either steam generator pressure to less than 600 psia ALERT Malor steam leak with GREATER THAN 10 Qpm pnmarv/secondarv leakage I

Rapid drop in either stearmi generator pressure to less than 600 psia AND 2

Known pn/sec leak of greater than 10 gpm AND

3. Secondary plant activity is detected SITE AREA EMERGENCY Major steam leak with GREATER THAN 50 ppm primary/secondary leakage and fuel damage indicated 1 Rapid drop in either steam generator pressure to less than 600 psia.

AND

2. Known pri/sec leak of greater than 50 gpm AND 3 Secondary plant activity is detected.

AND 4 Fuel element damage is indicated (Refer to Fuel Element Failure Event/Class 4.A).

GENERAL EMERGENCY A release has occurred or is in progress resulting in

1. Containment High Range Radiation monitor greater than 1 46 X 105 R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr)

OR

2. Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C or D below:

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)

(continued on next page)

Total loss of feedwater

1. No main or auxiliary feedwater flow available for greater than 15 minutes when required for heat removal.

AND

2. Steam Generator levels are less than 40% wide range TLOF with once-through cooling initiated

1. No main or auxiliary feedwater flow available.

AND

2. PORV(s) have been opened to facilitate core heat removal 1 C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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CLASSIFICATION OF EMERGENCIES 18 of 32 PROCEDURE NO:

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

EVENTICLASS 1.C. LOSS OF SECONDARY COOLANT (Page 2 of 2)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Loss of 2 of the 3 fission product barriers with imminent loss of the 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 Integnty Breached.

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

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6 CLASSIFICATION OF EMERGENCIES 19 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT I

ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 7 of 20)

EVENT/CLASS 2 A.

UNCONTROLLED EFFLUENT RELEASE UNUSUAL EVENT Radiological effluent limits exceeded

1.

Plant effluent monitor(s) exceed alarm setpoint(s)

AND 2

Confirmed analysis results for gaseous or liquid release which exceeds ODCM limits.

ALERT A release has occurred or is in progress that is 10 times the effluent emit

1.

Plant effluent monitor(s) significantly exceed alarm setpoints.

AND

2.

Confirmed analysis results for gaseous or liquid release which exceeds 10 times ODCM limits SITE AREA EMERGENCY

§2 A release has occurred or is in progress resulting in

1. Containment High Range Radiation Monitor greater than 7 3 X 103 R/hr (Post-LOCA monitors indicate between 100 and 1000 mR/hr, if CHRRM inoperable)

OR

2.

Measured Dose Rates or Offsite Dose Calculation (EPIP-09) worksheet values at one mile In excess of:

A 50 mrem/hr (total dose rate) or 250 mrem/hr (thyroid dose rate) for 1/2 hour.

OR B

500 mrem/hr (total dose rate) or 2500 mrem/hr (thyroid dose rate) for two minutes at one mile GENERAL EMERGENCY A release has occurred or is In progress resulting In

1. Containment High Range Radiation monitor greater than 1 46X 105 R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr)

OR 2 Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C or D below.

A 1000 mrem/hr (total dose rate)

B 1000 mrem (total dose - TEDE)

C 5000 mrem/hr (thyroid dose rate)

NOTE If analysis is not available within one hour and It is expected that release is greater than ODCM limit, classify as UNUSUAL EVENT.

NOTE If analysis is not available within one hour and it is expected that release is equal to or greater than 10 times ODCM limit, classify as ALERT.

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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6 CLASSIFICATION OF EMERGENCIES 20 of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 8 of 20)

EVENTICLASS UNUSUAL EVENT 2.B. HIGH RADIATION LEVELS IN PLANT ALERT High radiation levels or high airborne contamination which indicates a severe degradation in the control of radioactive matenals

1. Any valid area monitor alarm from an unplanned 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 unplanned source in excess of 1000 times normal levels.

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

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6 CLASSIFICATION OF EMERGENCIES 21 of 32 PROCEDURE NO:

EPIP-01 ST. LUCIE PLANT l

ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 9 of 20)

EVENT/CLASS 3

FIRE UNUSUAL EVENT

§2 Uncontrolled fire within the Power Block lasting more than 10 minutes, ALERT Uncontrolled fire

1. Potentially affecting safety systems AND

2. Requiring off-site support in the opinion of the NPS/EC SITE AREA EMERGENCY

§2 Fire compromising the function of safety systems (e a. both trains rendered inoperable)

GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event/Class 6 A NOTE

§2 Exploslon is defined as a rapid chemical reaction resulting in noise, heat and rapid expansion of as 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 he g. both EXPLOSION 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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6 CLASSIFICATION OF EMERGENCIES 22 of 32 PROCEDURE NO EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 10 of 20)

EVENT/CLASS 4 A FUEL ELEMENT FAILURE UNUSUAL EVENT Fuel element damage

1. Process monitors or area radiation surveys indicate increased letdown activity AND

2. Confirmed RCS sample indicating.

ALERT Fuel element failure

1. Process monitors or area radiation surveys indicate increased letdown activity and confirmed RCS Samples indicating DEQ 1-131 activity greater than or equal to 275 pCI/mL.

SITE AREA EMERGENCY Fuel element failure with inadequate core cooling

1. RCS DEQ 1-131 activity greater than or equal to 275 pCi/mL.

AND 2 Highest CET per core quadrant indicates greater than 1 00F superheat or 700'F.

GENERAL EMERGENCY A release has occurred or is in progress resulting in

1. Containment High Range Radiation monitor greater than 1.46 X 105 R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mRlhr)

OR 2 Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C or D below A. Coolant activity greater than the Tech Spec limit for iodine spike (Tech Spec Figure 3 4-1 )

OR B. Coolant activity greater than 100/E pCi/gram specific activity.

A 1000 mrem/hr (total dose rate)

NOTE If analysis is not available within one hour and it is expected that activity is greater than Tech Spec limit, classify as UNUSUAL EVENT NOTE If analysis is not available within one hour and it is expected that RCS activity for DEQ 1-131 is greater than 275 pCi/mL, classify as an ALERT B

1000 mrem (total dose -TEDE)

C. 5000 mrem/hr (thyroid dose rate)

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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EVENT/CLASS 4 B. FUEL HANDLING ACCIDENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Fuel handling accident which results

§2 Major damage to irradiated fuel in in the release of radioactivity to Containment or Fuel Handling Building Containment or Fuel Handling Building

1. NPS/EC determines that an irradiated fuel assembly may have been damaged.

AND

2. Associated area or process radiation monitors are in alarm.

1 Affected area radiation monitor greater than 1000 mrem/hr.

AND 2 Damage to more than one irradiated fuel assembly OR 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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EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 12 of 20)

EVENTICLASS 5 A EARTHQUAKE UNUSUAL EVENT

§2 A confirmed earthquake has occurred

1. A confirmed earthquake has been experienced within the Owner Controlled Area.

OR 2

¶4 An earthquake is detected by plant seismic monitor instruments or other means.

ALERT SITE AREA EMERGENCY

§2 A confirmed earthquake has occurred.

§2 A confirmed earthquake has occurred GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event /

Class 6 A.

1. A confirmed earthquake has occurred which registered GREATER THAN 0.05g within the Owner Controlled Area.

OR

2.

A confirmed earthquake has occurred that could or has caused trip of the turbine generator or reactor.

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

OR

2. A confirmed earthquake has occurred that has caused loss of any safety system function (e g, both trains Inoperable) 5 B. HURRICANE Hurricane Warning Hurricane warning with winds near design basis Humcane warning with winds GREATER THAN design basis NOTE Refer to Potential Core Melt Event I Class 6 A.

1. Confirmed hurricane warning is in effect

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

NOTE At FPL's request, NOAA will provide an accurate projection of wind speeds onsite 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the onset of hurricane force winds If that projection is not available within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entenng into the warning, classify the event using current track and wind speeds to project onsite conditions. For example, projected onsite wind speed would be less than maximum humcane wind speed if the track is away from PSL.

1. Plant not at cold shutdown.

AND

2. Confirmed humcane warning is in effect and winds are expected to exceed 194 mph within the Owner Controlled Area NOTE At FPL's request, NOAA will provide an accurate projection of wind speeds onsite 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the onset of humcane force winds If that projection Is not available within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering Into the warning, classify the event using current track and wind speeds to project onsite conditions For example, projected onsite wind speed would be less than maximum hurricane wind speed if the track 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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ST. LUCIE PLANT I

ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 13 of 20)

EVENTICLASS 5C. TORNADO UNUSUAL EVENT Notification of a tornado sighted In the Owner Controlled Area ALERT

§2 Any tornado stnking the Power Block SITE AREA EMERGENCY GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event /

Class 6.A.

5 D ABNORMAL WATER LEVEL Abnormal water level conditions are expected or occumng 1 Low intake canal level of -10.5 ft.

MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more OR 2 Visual sightings by station personnel that water levels are approaching storm drain system capacity.

Flood, low water. humcane surge or other abnormal water level conditions

1. The storm drain capacity is exceeded during hurricane surge or known flood conditions OR

2. Low Intake canal level of -10 5 ft MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more with emergency barrier valves open.

Flood, low water, hurricane surge or other abnormal water level conditions causing failure of vital equipment

1.

Flood/surge water level reaching elevation +19 5 ft (turbine building ! RAB ground floor)

OR 2

Low intake canal level has 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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CLASSIFICATION OF EMERGENCIES 26 of 32 PROCEDURE NO:

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ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 14 of 20)

NOTE I Activation of the Emergency Response Facilities does not require declaration of an emergency or entry Into a specific emergency classification. -4 EVENTICLASS 6 A INCREASED AWARENESS OR POTENTIAL CORE MELT (Page 1 of 2)

UNUSUAL EVENT Emeroencv Coordinator's ludoement that plant conditions exist which warrant increased awareness on the part of the operating staff and/or local authorities.

1 The plant is shutdown under abnormal conditions (e g, exceeding cooldown rates or primary system pipe cracks are found dunng operation)

OR

2. Any plant shutdown required by Technical Specifications In which the required shutdown Is not reached within action limits ALERT

§2 Emergencv Coordinators ludgement that

§2 plant conditions exist which have a potential to degrade the level of safety at the plant SITE AREA EMERGENCY Emergency Coordinator's ludgement that

§2 plant conditions exist which are sionifcantlv degrading In an uncontrollable manner.

GENERAL EMERGENCY Emergency Coordinator's ludoement that plant conditions exist that make release of large amounts of radioactivity in a short period appear possible or likely (Any core melt situation )

1 LOCA with failure of ECCS leading to severe core degradation or melt.

2 LOCA with initially successful ECCS and subsequent failure of containment heat removal systems for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

OR 3 Total loss of feedwater followed by failure of once-through-cooling (ECCS) to adequately cool the core.

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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> OR 5 ATWS occurs which results in core damage or causes failure of core cooling and make-up systems QE 6 Any major Intemal or extemal 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

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CLASSIFICATION OF EMERGENCIES 27 of 32 PROCEDURE NO.

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

EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY 6 A INCREASED AWARENESS OR POTENTIAL CORE MELT (Page 2 of 2)

GENERAL EMERGENCY NOTES

1. Most likely containment failure mode is melt-through with release of gases only.

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

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CLASSIFICATION OF EMERGENCIES 28 of 32 PROCEDURE NO EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 16 of 20)

EVENT/CLASS 7 A. LOSS OF POWER UNUSUAL EVENT ALERT SITE AREA EMERGENCY Loss of off-site power or loss of all

§2 Station Blackout (Total Loss of AC)

§2 Station Blackout (Total Loss of AC)

GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event / Class 6 A on-site AC power capability

1. Loss of off-site AC power OR

2. Loss of capability to power at least one vital 4 16 kv bus from any available emergency diesel generator.

1. Loss of off-site AC power AND

2. Failure of both emergency diesel generators to start or load for GREATER THAN 15 minutes

1. Loss of offsite AC power.

AND

2. Sustained failure of both emergency diesel generators to start or load.

AND

3. Failure to restore AC power to at least one vital 4.16 kv bus within 15 minutes.

Loss of all on-site DC power 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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EVENT/CLASS 8 A LOSS OF PLANT CONTROL FUNCTIONS UNUSUAL EVENT ALERT Loss of Plant Control Functions

1. Complete loss of any function needed for plant cold shutdown OR

2. Failure of the Reactor Protection System to bnng the reactor subcntical when needed.

OR

3. Control Room is evacuated (for other than drill purposes) with control established locally at the Hot Shutdown Control Panel.

SITE AREA EMERGENCY Cntical Loss of Plant Control Functions

1. Loss of any function or system which, In the opinion of the Emergency Coordinator, precludes placing the plant in Hot Shutdown.

OR

2. Failure of the RPS to trip the reactor when needed and operator actions fall to bring the reactor subcntical.

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

GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event /

Class 6 A 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 00F.

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

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EVENTICLASS 8 B LOSS OF ALARMS /

COMMUNICATION!

MONITORING UNUSUAL EVENT ALERT

§2 Significant loss of effluent monitoring §2 Loss of alarms SITE AREA EMERGENCY Loss of alarms/monitoring

1. Inability to monitor* a significant transient in progress.

GENERAL EMERGENCY capability, communications, indication and alarm panels. etc.

which impairs ability to perform accident or emergency assessment 1 Loss of effluent or radiological monitoring capability requiring plant shutdown OR 2 Loss of all pnmary 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 1 Unplanned loss of most (greater than 75%) or all safety system annunciators AND 2

Plant transient in progress.

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

EVENT/CLASS UNUSUAL EVENT 9A AIRCRAFT/MISSILE Unusual aircraft activity

1. Aircraft crash in the Owner Controlled Area or unusual aircraft activity over facility that in the opinion of the NPS/EC, could threaten the safety of the plant or personnel.

ALERT

§2 Aircraft/missile impact

1. Aircraft crash Into the Power Block OR 2 Visual or audible indication of missile impact on the Power Block SITE AREA EMERGENCY GENERAL EMERGENCY

§2 Damage to vital systems from aircraft/missiles

1. Aircraft crash into the Power Block damaging vital plant systems.

OR

2. Damage resulting in loss of safe shutdown equipment from any missile 9 B. TURBINE FAILURE Turbine rotating component failure causing rapid plant shutdown Visual indication that the turbine casing has been penetrated by blading 9 C. TOXIC OR FLAMMABLE GAS Unplanned/uncontrolled toxic or flammable gas release in the Owner Controlled Area that could affect plant/personnel safety.

Entry of toxic or flammable gas into

§2 Toxic or flammable gas has diffused areas potentially affecting plant operation into vital areas compromising the function of safety related equipment (e a. 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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EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 20 of 20)

EVENTICLASS

10. SECURITY THREAT UNUSUAL EVENT A SECURITY ALERT has been called by the SecuntV Force in response to one or more of the items listed below

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

Secunty Force stnke

10. Credible site-specific Security threat notification ALERT A SECURITY EMERGENCY has been called by the Secunty Force as defined in the Safeguards Contingency Plan SITE AREA EMERGENCY GENERAL EMERGENCY A SECURITY EMERGENCY involving Imminent occupancy of the control room or other area(s) vital to the operation of the reactor as defined In the Safeguards Contingency Plan A successful takeover of the olant including the Control Room or any other area(s) vital to the operation of the reactor (as per the Secuntv Plan) 10 SECURITY THREAT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR