L-2002-134, 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) | |
Text
Florida Power & Light Company, 6501 South Ocean Drive, Jensen Beach, FL 34957 0'*
July 11, 2002 IFPL 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 Effective Date SAFETY RELATED 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)
FRG Review Date 12/15/97 FRG Review Date 05/23/02 Approved By J. Scarola Plant General Manager Approved By D. Rose Plant General Manager N/A Designated Approver N/A Designated Approver (Minor Correction)
T Approval Date 12/15/97 Approval Date 05/23/02 S
OPS DATE DOCT PROCEDURE DOCN EPIP-01 SYS COM COMPLETED ITM 4
Revision 0
Revision 4
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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 IN IT IO N S............................................................................................
5 5.0 IN STR U CT 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. ai shall NOT be revised without Facility Review Group review and Plant General Manager approval.
¶ Indicates a management directive, vendor recommendation, plant pract or other non-regulatory commitment that should NOT be revised withou 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 nd ice t
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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 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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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 1.A.
ABNORMAL PRIMARY LEAK RATE (Page 1 of 2)
UNUSUAL EVENT Reactor Coolant System (RCS) Leakage
- 1. RCS leakage GREATER THAN 10 gpm as indicated by:
A. Control Room observation OR B. Inventory balance calculation OR C.
Field observation OR D. Emergency Coordinator judgement AND Inability to reduce the leak rate to technical specification limits within the timeframe of the action statement.
NOTE For RCS Leakage in Section 1 above, the (Notification of)
Unusual Event should be declared upon commencing a load reduction/mode change.
ALERT RCS Leakage GREATER THAN 50 qpm
- 1. Unisolable RCS leakage as indicated by Charging/letdown mismatch greater than 50 gpm but less than available charging pump capacity.
- 2. Unisolable measured RCS leakage indicating greater than 50 gpm but less than available charging pump capacity.
SITE AREA EMERGENCY LOCA GREATER THAN capacity of charging pumps
- 1. RCS leakage greater than available charging pump capacity occurring with RCS pressure above HPSI shutoff head.
- 3.
Loss of RCS subcooled margin due to RCS leakage (saturated conditions).
- 4. Containment High Range Radiation Monitors indicate 7.3 X 103 R/hr (If CHRRM inoperable, Post-LOCA monitors indicate between 100 and 1000 mR/hr).
- 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 GENERAL EMERGENCY A release has occurred or is in progress resulting in:
- 1. Containment High Range Radiation monitor greater than 1.46 X 106 R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
- 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) 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 ABNORMAL PRIMARY LEAK RATE (Page 2 of 2)
GENERAL EMERGENCY Loss of 2 of the 3 fission oroduct 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 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.A.
I
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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 Leakage
- 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.
(continued on next page)
SITE AREA EMERGENCY Rapid gross failure of steam generator tubes (GREATER THAN charging pump capacity) with a loss of offsite power
- 1. 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 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 integrity breached.
(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 1.B.
ABNORMAL PRIMARY TO SECONDARY LEAK RATE (Page 2 of 2)
UNUSUAL EVENT ALERT Rapid failure of steam generator tubes (GREATER THAN charging pump capacity)
- 1. 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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EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 5 of 20)
EVENTICLASS I.C. LOSS OF SECONDARY COOLANT (Page 1 of 2)
UNUSUAL EVENT Rapid depressurization of secondary plant
- 1.
Rapid drop in either steam generator pressure to less than 600 psia.
ALERT Major steam leak with GREATER THAN 10 qpm primary/secondary leakage
- 1. Rapid drop in either steam generator pressure to less than 600 psia.
AND
- 2. Known pri/sec leak of greater than 10 gpm.
AND
- 3.
Secondary plant activity is detected.
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.
SITE AREA EMERGENCY Major steam leak with GREATER THAN 50 qpm 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).
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.
GENERAL EMERGENCY A release has occurred or is in progress resulting in:
- 1. Containment High Range Radiation monitor greater than 1.46 X 105 PRhr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
- 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) 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 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 oroduct 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 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 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.
NOTE If analysis is not available within one hour and it is expected that release is greater than ODCM limit, classify as UNUSUAL EVENT.
ALERT SITE AREA EMERGENCY A release has occurred or is in
§2 A release has occurred or is in progress that is 10 times the effluent progress resulting in:
limit
- 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.
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.
- 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).
- 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 112 hour0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br />.
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 1.46 X 105 R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
- 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)
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 2.B. HIGH RADIATION LEVELS IN PLANT UNUSUAL EVENT ALERT High radiation levels or high airborne 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).
- 2.
Unexpected plant iodine or particulate airborne concentration of 1000 DAC as seen in routine surveying or sampling.
- 3.
Unexpected direct radiation dose rate reading or unexpected airborne radioactivity concentration from an indeterminable 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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EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 9 of 20)
EVENTICLASS
- 3.
FIRE EXPLOSION 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.g., both trains rendered inoperable).
GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event/Class 6.A.
NOTE
§2 Explosion is defined as a rapid chemical reaction resulting in noise, heat and rapid expansion of gas.
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)
UNUSUAL EVENT Fuel element damage
- 1. Process monitors or area radiation surveys indicate increased letdown activity AND
- 2.
Confirmed RCS sample indicating:
A. Coolant activity greater than the Tech Spec limit for iodine spike (Tech Spec Figure 3.4-1.).
OR B. Coolant activity greater than 100/1 pCi/gram specific activity.
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
AND
- 2.
Highest CET per core quadrant indicates greater than 100F superheat or 700°F.
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.
GENERAL EMERGENCY A release has occurred or is in progress resulting in:
- 1. Containment High Range Radiation monitor greater than 1.46 X 10 5 Rhr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).
- 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) 4.A FUEL ELEMENT FAILURE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR EVENT/CLASS 4.A.
FUEL ELEMENT FAILURE 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.
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EVENTICLASS 4.B. FUEL HANDLING ACCIDENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY Fuel handlinq accident which results
§2 Major damage to irradiated fuel in in the release of radioactivity to 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.
Containment or Fuel Handling Building
- 1. Affected area radiation monitor greater than 1000 mtrem/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 GENERALEMERGENCY
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UNUSUAL EVENT
§2 A confirmed earthquake has occurred
- 1. A confirmed earthquake has been experienced within the Owner Controlled Area.
- 2. T4 An earthquake is detected by plant seismic monitor instruments or other means.
Hurricane Warning
- 1. Confirmed hurricane warning is in effect.
ALERT SITE AREA EMERGENCY
§2 A confirmed earthquake has occurred.
§2 A confirmed earthquake has occurred.
- 1.
A confirmed earthquake has occurred which registered GREATER THAN 0.05g within the Owner Controlled Area.
- 2.
A confirmed earthquake has occurred that could or has caused trip of the turbine generator or reactor.
Hurricane warningq with winds near desigqn basis
- 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 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.
- 1. A confirmed earthquake has occurred which registered GREATER THAN 0.1g within the Owner Controlled Area and the plant not in Cold Shutdown.
- 2. A confirmed earthquake has occurred that has caused loss of any safety system function (e.g., both trains inoperable).
Hurricane warning with winds GREATER THAN desiqn basis
- 1. Plant not at cold shutdown.
AND
- 2. Confirmed hurricane warning is in effect and winds are expected to exceed 194 mph within the Owner Controlled Area.
5.A.
EARTHQUAKE 5.B. HURRICANE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event/
Class 6.A.
NOTE Refer to Potential Core Melt Event /
Class 6.A.
EVENTICLASS 5.A. EARTHQUAKE 5.B.
HURRICANE 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 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.
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EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 13 of 20)
UNUSUAL EVENT Notification of a tornado sighted in the Owner Controlled Area Abnormal water level conditions are expected or occurring
- 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.
- 2. Visual sightings by station personnel that water levels are approaching storm drain system capacity.
ALERT
§2 Any tornado striking the Power Block.
Flood, low water, hurricane surge or other abnormal water level conditions
- 1. The storm drain capacity is exceeded during hurricane surge or known flood conditions.
- 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.
SITE AREA EMERGENCY GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event /
Class 6.A.
Flood, low water, hurricane surge or other abnormal water level conditions causinq failure of vital equipment
- 1. Flood/surge water level reaching elevation +19.5 ft. (turbine building/RAB ground floor).
- 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 EVENTICLASS 5.C. TORNADO 5.D. ABNORMAL WATER LEVEL
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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.
EVENTICLASS 6.A.
INCREASED AWARENESS OR POTENTIAL CORE MELT (Page 1 of 2)
UNUSUAL EVENT ALERT Emergencv Coordinator's iudgement that
§2 Emergency Coordinator's iudgement 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 during operation).
- 2. Any plant shutdown required by Technical Specifications in which the required shutdown is not reached within action limits.
plant conditions exist which have a potential to deqrade the level of safety at the plant.
SITE AREA EMERGENCY
§2 EmergencyvCoordinator's iudqement that
§2 plant conditions exist which are significantly degrading in an uncontrollable manner.
GENERAL EMERGENCY Emergency Coordinator's ludgement that plant conditions exist that make release of lame amounts of radioactivity in a short period appear possible or likely. (Any core melt situation.)
- 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 />.
- 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 />.
- 5. ATWS occurs which results in core damage or causes failure of core cooling and make-up systems.
- 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 I
N--
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EVENTCLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY 6.A. INCREASED AWARENESS OR POTENTIAL CORE MELT (Page 2 of 2) 6.A. INCREASED AWARENESS OR POTENTIAL CORE MELT 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.
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 16 of 20)
UNUSUAL EVENT ALERT Loss of off-site power or loss of all
§2 Station Blackout (Total Loss of AC)
§2 on-site AC power capability.
- 1. Loss of off-site AC power.
- 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.
Loss of all on-site DC power
- 1. Drop in A and B DC bus voltages to less than 70 VDC.
SITE AREA EMERGENCY Station Blackout (Total Loss of AC) 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 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.
GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event / Class 6.A.
7.A. LOSS OF POWER AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR EVENTICLASS 7.A. LOSS OF POWER
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EVENTICLASS 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.
- 2. Failure of the Reactor Protection System to bring the reactor subcritical when needed.
- 3. Control Room is evacuated (for other than drill purposes) with control established locally at the Hot Shutdown Control Panel.
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.
SITE AREA EMERGENCY Critical 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.
- 2. Failure of the RPS to trip the reactor when needed and operator actions fail to bring the reactor subcritical.
- 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.
8.A. LOSS OF PLANT CONTROL FUNCTIONS AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR I
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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 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.
- 2. Loss of all primary and backup communication capability with offsite locations.
- 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.
SITE AREA EMERGENCY Loss of alarms/monitoring
- 1. Inability to monitor* a significant transient in progress.
GENERAL EMERGENCY
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
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EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 19 of 20)
EVENT/CLASS 9.A. AIRCRAFT / MISSILE 9.B. TURBINE FAILURE 9.C. TOXIC OR FLAMMABLE GAS UNUSUAL EVENT 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.
Turbine rotating component failure causing rapid plant shutdown.
Unplanned/uncontrolled toxic or flammable gas release in the Owner Controlled Area that could affect plant/personnel safety.
ALERT
§2 Aircraft/missile impact
- 1. Aircraft crash into the Power Block.
- 2. Visual or audible indication of missile impact on the Power Block.
SITE AREA EMERGENCY
§2 Damage to vital systems from aircraft/missiles
- 1. Aircraft crash into the Power Block damaging vital plant systems.
- 2. Damage resulting in loss of safe shutdown equipment from any missile.
Visual indication that the turbine casing has been penetrated by blading.
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.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 GENERAL EMERGENCY
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EVENT/CLASS
- 10. SECURITY THREAT UNUSUAL EVENT A SECURITY ALERT has been called by the Security Force in response to one or more of the items listed below.
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
10.
ALERT A SECURITY EMERGENCY has been called by the Security Force as defined in the Safeguards Contingency Plan.
Bomb threat Attack threat Security threat Protected Area intrusion attempt Sabotage attempt Internal disturbance Civil disturbance Vital Area intrusion Security Force strike Credible site-specific Security threat notification SITE AREA 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.
GENERAL EMERGENCY A successful takeover of the plant including the Control Room or any other area(s) vital to the operation of the reactor (as per the Security Plan).
- 10. SECURITY THREAT A.FTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR