ML021070725
| ML021070725 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/05/2002 |
| From: | Florida Power Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EM-202, Rev 70 | |
| Download: ML021070725 (60) | |
Text
PASSPORT DOCUMENT To NRC NRC Facility CR3 Department : TRANSMITTAL Address CR3-01242 / MAIL CODE: N/A DC DESK Page: 1 From Address CR3DOCSVCS Attention: DOCUMENT SERVICES FLORIDA POWER CORPORATION CRYSTAL RIVER COMPLEX 15760 WEST POWERLINE STREET 111111 ii1111 City CRYSTAL RIVER State:FL Postal Code: 34428-6708 Country UNITED STATES Email Contact Date/Time 04/05/02 09:55 Transmittal Group Id:0000001951 Trans No. 000060484
Title:
Total Items: 00001 IItem 0001 Facility CR3 POM Type EMG Sub EM0202 Document Number Sheet ACTIVE Doc Status 070 Revision Doc Date Copy # H Media 01 Copies If a document was not received or is no longer required check the response below and return to sender.
Documents noted above not received (identify those not received).
I no longer require distribution of these documents (identify those no longer required).
Date: Signature:
kJ\
R Slorida Power Reference AProgre Engy Copany Use FLORIDA POWER CRYSTAL RIVER UNIT 3 PLANT OPERATING MANUAL EMERGENCY PLAN IMPLEMENTING PROCEDURE EM-202 DUTIES OF THE EMERGENCY COORDINATOR EM-202 Rev. 70 Page 1 of 59
TABLE OF CONTENTS PAGE SECTION 1.0 PURPOSE ................................................................................................................................ 4
2.0 REFERENCES
......................................................................................................................... 4 PERSONNEL INDOCTRINATION ..................................................................................... 5 3.0 3.1 DEFINITIONS ................................................................................................................ 5 3.1.1 Bom b ............................................................................................................. 5 3.1.2 Civil Disturbance .......................................................................................... 5 3.1.3 Comm itted Dose Equivalent (CDE) ....................................................... 5 3.1.4 Credible Site-Specific Security Threat Notification ............................. 5 3.1.5 Deep Dose Equivalent (DDE) ................................................................. 5 3.1.6 Emergency Action Level (EAL) .............................................................. 5 3.1.7 Emergency Classification ....................................................................... 5 3.1.8 Emergency Coordinator (EC) ................................................................ 5 3.1.9 Emergency Response Data System (ERDS) .......................................... 6 3.1.10 Explosion .................................................................................................. 6 3.1.11 Extortion ................................................................................................... 6 3.1.12 Fire ........................................................................................................ 6 3.1.13 Hostage .................................................................................................... 6 3.1.14 Incident Report ....................................................................................... 6 3.1.15 Intrusionllntruder .................................................................................... 6 3.1.16 Local Assem bly Area .............................................................................. 6 3.1.17 Main Assem bly Area ................................................................................ 6 3.1.18 Protected Area ......................................................................................... 6 3.1.19 Protective Action Recommendations .................................................. 6 3.1.20 Release (Florida Nuclear Plant Emergency Notification Form ) ............................................................................................................. 7 3.1.21 Release, Unplanned (Reactor Plant Event Notification W orksheet) .................................................................................................... 7 3.1.22 Sabotage .................................................................................................. 7 3.1.23 Safe Shutdown Equipment ..................................................................... 7 3.1.24 Security Emergency ................................................................................ 7 3.1.25 Severe Accident ....................................................................................... 7 3.1.26 Significant Transient .............................................................................. 7 3.1.27 Site Boundary ......................................................................................... 7 3.1.28 Strike Action ........................................................................................... 7 3.1.29 Thyroid CDE Dose ................................................................................... 7 3.1.30 Total Effective Dose Equivalent (TEDE) ................................................. 7 3.1.31 Unplanned ................................................................................................ 7 3.1.32 Valid ..................................................................................................... 8 3.1.33 Visible Dam age ....................................................................................... 8 3.2 RESPONSIBILITIES ................................................................................................ 8 3.3 LIMITS AND PRECAUTIONS .................................................................................. 9 4.0 INSTRUCTIONS ..................................................................................................................... 10 4.1 EMERGENCY COORDINATOR'S GUIDE FOR UNUSUAL EVENT ...................... 11 4.2 EMERGENCY COORDINATOR'S GUIDE FOR AN ALERT ................................. 14 4.3 EMERGENCY COORDINATOR'S GUIDE FOR SITE AREA EMERGENCY .............................................................................................................. 17 4.4 EMERGENCY COORDINATOR'S GUIDE FOR GENERAL EMERGENCY .............................................................................................................. 20 EM-202 Rev. 70 Page 2 of 59
TABLE OF CONTENTS (Continued)
ENCLOSURES PAGE 1 Emergency Classification Table ............................................................................................ 23 2 Florida Nuclear Plant Emergency Notification Form (and associated information) ............... 39 3 Considerations for a Security Emergency ............................................................................ 44 4 Reactor Plant Event Notification Worksheet ....................................................................... 48 5 Emergency Notification for Units 1/2 & 4/5 (Optional Records Non-Quality) ...................... 50 6 Initiation of the Emergency Response Data System (ERDS) ............................................... 51 7 Evacuation Planning G uide .................................................................................................. 52 8 Guidelines for Protective Action Recommendations ........................................................... 56 EM-202 Rev. 70 Page 3 of 59
1.0 PURPOSE Provides instructions and guidelines used by the Emergency Coordinator during initiation of the Radiological Emergency Response Plan. Specific guidelines include emergency classification, reporting and notification requirements, and protective action recommendations for non-essential Energy Complex personnel and the public.
2.0 REFERENCES
2.1 Developmental References 2.1.1 10 CFR 50.47, Emergency Plans 2.1.2 10 CFR 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities 2.1.3 10 CFR 50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors 2.1.4 CR-3 Severe Accident Guideline 2.1.5 Emergency Action Level Bases Manual 2.1.6 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA-400-R-92-001, Environmental Protection Agency (October, 1991) 2.1.7 NEI 91-04, Revision 1, Severe Accident Issue Closure Guidelines 2.1.8 NEI 97-03, Methodology for Development of Emergency Action Levels 2.1.9 NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 2.1.10 Off-Site Dose Calculation Manual 2.1.11 Radiological Emergency Response Plan 2.1.12 Safety Evaluation of FPC proposed EAL changes for CR-3 (TAC No. MA2231), NRC to FPC letter 3N0299-02 EM-202 Rev. 70 Page 4 of 59
3.0 PERSONNEL INDOCTRINATION 3.1 Definitions 3.1.1 Bomb - An explosive device suspected of having sufficient force to damage plant systems or structures.
(See EXPLOSION.)
3.1.2 Civil Disturbance -A group of ten (10) or more people violently protesting station operations or activities at the site. A civil disturbance is considered violent when force has been used in an attempt to injure site personnel or damage plant property.
3.1.3 Committed Dose Equivalent (CDE) - Dose to an organ due to the intake of radioactive materials.
3.1.4 Credible Site-Specific Security Threat Notification - A threat specifically to CR-3 confirmed and validated by Nuclear Security. Notification may be received from recognized law enforcement or governmental agencies (e.g. Federal Bureau of Investigation (FBI), Florida Department of Law Enforcement (FDLE), Division of Emergency Management (DEM), Nuclear Regulatory Commission NRC.)
3.1.5 Deep Dose Equivalent (DDE) - External whole body dose.
3.1.6 Emergency Action Level (EAL) - A pre-determined, observable threshold for plant conditions that places the plant in a given emergency classification.
3.1.7 Emergency Classification - A system of classification in which emergency occurrences are categorized according to specific protective action levels. The four emergency classifications are:
3.1.7.1 Unusual Event - This classification refers to any event(s), in process or having occurred, indicating a potential degradation of the level of safety of the plant. NO releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs. This classification brings the operating staff to a state of readiness if escalation to a more severe action level classification occurs.
3.1.7.2 Alert - This classification refers to event(s) that are in process, or have occurred, involving an actual or potentially substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. The Technical Support Center (TSC) is staffed and assembly and accountability are performed at local assembly areas.
3.1.7.3 Site Area Emergency - This classification refers to event(s) that are in process, or have occurred, involving actual or likely major failures of plant functions needed for the protection of the public. Any releases are NOT expected to result in exposure levels, which exceed EPA Protective Action Guideline exposure levels at the SITE BOUNDARY. The TSC and the Emergency Operations Facility (EOF) are staffed and radiation monitoring teams may be dispatched. Protected Area evacuation and accountability is performed at CR-3. Assembly and accountability is performed at Units 1/2 & 4/5.
3.1.7.4 General Emergency - This classification refers to event(s) that are in process, or have occurred, involving actual or imminent substantial core degradation or nuclear fuel melting with the potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guidelines exposure levels at the SITE BOUNDARY. This classification initiates predetermined protective actions for the public, provides continuous assessment of information from on-site and off-site measurements, initiates additional measures indicated by the event, and provides current information and consultation with off-site authorities and the public. The Emergency Coordinator will probably decide to evacuate the Energy Complex.
3.1.8 Emergency Coordinator (EC) - The position with the highest level of authority for the CR-3 Emergency Organization and on-site emergency activities. This position is held by the Plant General Manager or designated alternate. The Superintendent Shift Operations assumes the position until the Plant General Manager or designated alternate arrives to assume Emergency Coordinator responsibilities.
EM-202 Rev. 70 Page 5 of 59
3.1.9 Emergency Response Data System (ERDS) - NRC requirement {10 CFR 50.72(a)(4)} to have the ability to acquire data from nuclear power plants in the event of an emergency at the plant. ERDS is a direct real-time transfer of data from FP to NRC. Once initiated, ERDS operates automatically.
3.1.10 Explosion - A rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.
3.1.11 Extortion - An attempt to cause an action at CR-3 by threat of force. Bomb threats that are unsubstantiated are NOT included in this definition.
3.1.12 Fire - Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do NOT constitute fires. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.
3.1.13 Hostage - A person or object held as leverage against the station to ensure that demands will be met by CR-3.
3.1.14 Incident Report- A report of the actual scenario of the emergency, the identified cause(s) of the emergency, and the radiological history of the emergency, including released quantities, existing radiological activity, abnormal doses for emergency worker and population doses.
3.1.15 Intrusionllntruder - Suspected hostile individual present in a protected area without authorization. An intruder also includes a badged employee (insider) acting in an active or passive manner in support of an overt or covert attempt to commit sabotage. A passive manner means the insider may provide intelligence type information regarding Security or Operations Unit actions or responses to persons or organizations planning or attempting to commit sabotage. This intelligence type information may include but NOT be limited to Security Force deployment strategies or procedures or Operations Unit procedures in response to security contingency events. An active manner means the insider may provide support to persons or organizations planning or attempting to commit sabotage. This support may include but NOT be limited to disrupting Security Force responses to contingency events or disrupting Operations Unit actions or response involving reactor safety controls in response to contingency events.
3.1.16 Local Assembly Area - A pre-designated area personnel report for organization, roll call, and supervision following an "Alert' emergency classification.
3.1.17 Main Assembly Area (MAA) - The place personnel report for organization and supervision following an evacuation of the CR-3 Protected Area. The Main Assembly Area is the Site Administration Building Auditorium.
3.1.18 Protected Area - All areas within the CR-3 security perimeter fence that require badged authorization for entry.
3.1.19 Protective Action Recommendations - Emergency measures recommended for purposes of preventing or minimizing radiological exposures to Energy Complex personnel or members of the public.
Protective Action Recommendations are made using all available data, primarily plant conditions.
Off-site dose projections and/or field survey results can also be factored in to Protective Action Recommendations if confidence in their accuracy is high (monitored release, confirmed field survey results).
EM-202 Rev. 70 Page 6 of 59
3-.11.20 Release (Florida Nuclear Plant Emergency Notification Form) - Any of the following:
Any increase in count rate on an effluent monitor that is a direct result of an event that has initiated an emergency declaration; OR Radioactivity detected by environmental monitoring; OR NOTE Design Basis Leakage or other suspected leakage should NOT be categorized as a release until confirmed by environmental monitoring.
Radioactivity escaping unmonitored from the plant.
3.1.21 Release, Unplanned (Reactor Plant Event Notification Worksheet) - Release is NOT authorized by a Release Permit or exceeds the conditions (e.g., minimum dilution flow, maximum discharge flow, alarm setpoints, etc.) on the applicable permit.
3.1.22 Sabotage - Deliberate damage, mis-alignment, or mis-operation of safe shutdown equipment with the intent to render the equipment unavailable.
3.1.23 Safe Shutdown Equipment - Equipment necessary to achieve and maintain the reactor subcritical with controlled decay heat removal.
3.1.24 Security Emergency - A Security related situation that poses a clear or imminent threat or danger to the plant and calls for prompt response and/or is confirmed as an act of sabotage.
3.1.25 Severe Accident - An accident beyond that assumed in the CR-3 design and licensing basis that results in catastrophic fuel rod failure, core degradation, and fission product release into the Reactor vessel, Reactor Building, or the environment.
3.1.26 Significant Transient - An UNPLANNED event involving one or more of the following:
(1) Automatic turbine trip at >25% reactor thermal power (2) Electrical load rejection >25% full electrical load (3) Plant runback (4) Reactor trip (5) Safety injection system actuation (6) >10% thermal power oscillations (7) Loss of decay heat removal-in Mode 4 ("Significant Transient" is NOT used in any Mode 5 or 6 EAL) 3.1.27 Site Boundary - That area, including the PROTECTED AREA that extends 4400 feet or 0.83 miles in a circle around the Reactor Building. Also referred to as the Owner Controlled Area.
3.1.28 Strike Action - Is a work stoppage within the PROTECTED AREA by a body of workers to enforce compliance with demands made. The strike actions must threaten to interrupt normal plant operations.
3.1.29 Thyroid CDE Dose - Dose to the thyroid due to intake of radioactive iodine.
3.1.30 Total Effective Dose Equivalent (TEDE) - The sum of external dose (DDE) and the equivalent amount of whole body dose due to individual organ uptakes.
3.1.31 Unplanned - An event or action is UNPLANNED if it is NOT the expected result of normal operations, testing, or maintenance. Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.
EM-202 Rev. 70 Page 7 of 59
3.1.32 Valid - An indication or report or condition is considered VALID when it is conclusively verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicator's operability, the condition's existence, or the report's accuracy is removed. Implicit in this definition is the need for timely assessment (e.g., within 15 minutes).
3.1.33 Visible Damage - Damage to equipment or structure that is readily observable without measurements, testing, or analyses. Damage is sufficient to cause concern regarding the continued operability or reliability of affected safety structure, system, or component. Example damage includes: deformation due to heat or impact, denting, penetration, rupture, cracking, paint blistering. Surface blemishing (e.g., paint chipping, scratches) should NOT be included.
3.2 Responsibilities 3.2.1 The Emergency Coordinator controls all activities at CR-3 during activation of the Radiological Emergency Response Plan.
3.2.2 The Emergency Coordinator shall NOT delegate the decisions related to classification of the emergency condition.
3.2.3 The Emergency Coordinator shall NOT delegate the decisions related to notification and protective action recommendations to State and Local authorities who implement off-site emergency measures, until the EOF Director communicates to the Emergency Coordinator the EOF accepts the State notification and Protective Action Recommendations (PARs) responsibilities. At this time, the EOF completes the Florida Nuclear Plant Emergency Notification Form.
3.2.4 Upon arrival on-site, the Plant General Manager (PGM) or designated alternate contacts the Control Room Emergency Coordinator or goes to the Control Room and receives a briefing about the status of the emergency condition and the implementation of the Radiological Emergency Response Plan. When ready to assume responsibility as the Emergency Coordinator, inform the Control Room Emergency Coordinator and Technical Support Center staff.
3.2.5 The Emergency Coordinator provides the Emergency Operations Facility Director an Incident Report when a sustained Site Area Emergency or General Emergency involves a Recovery Plan. This documents the emergency and serves as a basis for recovery phase operations.
3.2.6 During declared emergency conditions, the Emergency Coordinator is the sole contact for emergency regulatory directives. The Emergency Coordinator evaluates these directives for possible response to the emergency condition.
3.2.7 The Emergency Coordinator responsibilities in other Emergency Plan Implementing Procedures are implemented when plant conditions warrant.
3.2.8 Based on the evaluation of the emergency condition, the Emergency Coordinator has the authority to implement the following actions:
- Direct personnel to shelter or evacuate the Energy Complex.
- Order Energy Complex Plants placed in a safe shutdown condition.
- Notify all applicable agencies of the plant status.
- Suspend security safeguards as appropriate. {10 CFR 50.54(x)(y)}
- Request outside assistance, if necessary.
- Make the necessary personnel assignments to provide continuing response for long-term activities.
EM-202 Rev. 70 Page 8 of 59
3.2.9 The Emergency Coordinator reports to the EOF Director, once the EOF is operational.
3.2.10 The EOF Director provides for the direction and control of all emergency phase activities once the EOF is declared operational. The EOF Director has authority and responsibility for management of emergency response resources, coordination of radiological and environmental assessment, recommendations for public protective actions, and coordination of emergency response activities with Federal, State, and local agencies.
3.2.11 Nuclear Licensing prepares a written summary of any Alert, Site Area Emergency or General Emergency for the NRC and the State of Florida within twenty-four hours (or the next working day) from termination of the event.
3.2.12 During Severe Accident conditions, the Emergency Coordinator reviews and provides final approval of all mitigation strategies developed by the Accident Assessment Team before implementation.
3.3 Limits and Precautions 3.3.1 Upon declaration of a General Emergency, the minimum protective action recommendation is:
EVACUATE ZONE 1 3.3.2 During the initial phase of an emergency condition, the lack of information may prevent the Emergency Coordinator from completing the Florida Nuclear Plant Emergency Notification Form. If information is NOT available, do NOT delay notification to State Warning Point Tallahassee. Indicate additional information will follow when it becomes available.
3.3.3 The Reactor Plant Event Notification Worksheet is used as a guideline to provide adequate detail to the Headquarters Operations Officer to understand the event and its significance. All the information regarding an event may NOT be available at the time of notification, but at a minimum must provide the event classification and description as soon as possible after the State notification, within the required time.
3.3.4 For all radiological, Security events, hazardous material spills, toxic gas releases or violent weather conditions, the Emergency Coordinator determines the safe actions for plant personnel, which may include delaying the staffing of the TSC and EOF until it is safe to do so.
3.3.5 The Emergency Coordinator directly notifies the Plant General Manager and EOF Director to ensure the rationale of the emergency classification is understood.
3.3.6 Individuals assigned to make notifications are trained on how to make notifications and are familiar with communication systems. [NOCS 21207]
3.3.7 The Technical Support Center (TSC) continues to complete items on the Florida Nuclear Plant Emergency Notification Form and transmits to the EOF until the EOF Director declares the EOF operational, and informs the Emergency Coordinator the EOF accepts responsibility for State notifications and Protective Action Recommendations. At this time, the EOF Director assumes full responsibility for completing the Florida Nuclear Plant Emergency Notification Form.
3.3.8 Telephone notifications to the Nuclear Regulatory Commission (NRC), State of Florida, Citrus and Levy Counties are complete when direct voice contacts are made with the responsible representatives of the agencies notified. The leaving of a message with an agency's telephone operator, secretary, answering service, or message recording device is NOT a completed notification.
3.3.9 The Emergency Action Levels are NOT intended for maintenance and/or testing situations where abnormal instrument readings, alarms, and observations are expected. Some maintenance evolutions may require compensatory actions.
EM-202 Rev. 70 Page 9 of 59
4.0 INSTRUCTIONS 4.0.1 RECORD significant information, events, and actions taken during the emergency condition and retain for later evaluation. Information substantiating the sequence of events is compiled from procedures, communication logs, tape recordings, flip charts, message copies, photographs (if available) and other pertinent documentation.
4.0.2 DETERMINE the emergency classification using Enclosure 1, Emergency Classification Table.
Page 2 FISSION PRODUCT BARRIER MATRIX Page 3 ABNORMAL RADIATION LEVELS/RADIOLOGICAL EFFLUENT Page 5 NATURAL/MANMADE HAZARDS AND EC JUDGEMENT Page 11 SYSTEM MALFUNCTION Page 16 LOSS OF POWER 4.0.3 PERFORM steps from Emergency Coordinator Guide for each emergency classification as indicated in the following Sections:
4.1 UNUSUAL EVENT 4.2 ALERT 4.3 SITE AREA EMERGENCY 4.4 GENERAL EMERGENCY 4.0.4 USE the time blocks in Sections 4.1, 4.2, 4.3 and 4.4 to provide a reference of actions taken during the emergency condition. All actions, with the exception of decisions relating to classification and notification and Protective Action Recommendations made to State and Local authorities, can be performed in parallel by delegation from the Emergency Coordinator.
4.0.5 IF an emergency classification is upgraded before the first notification is made, THEN ENSURE notification is made within 15 minutes of original classification.
4.0.6 IF it is discovered that a condition previously existed that should have resulted in an emergency declaration, AND the condition NO longer exists, THEN make notifications to the NRC Operations Center via ENS within one hour of discovering the undeclared event, AND NOTIFY the Emergency Preparedness staff to NOTIFY the State and Local Governments. An emergency declaration is NOT required.
4.0.7 Information requested for TSC turnover is contained in Enclosure 4 of EM-1 02, Operation of the Technical Support Center.
4.0.8 REFER to EM-103 for additional Control Room activities during a declared emergency including dispatch of Operators outside of the Control Complex.
EM-202 Rev. 70 Page 10 of 59
4'.1 Emergency Coordinator's Guide For Unusual Event
[NOCS 1129, 96042]
TIME UNUSUAL EVENT DECLARED DATE RECOMMENDED WITHIN 5 MINUTES 4.1.1 NOTIFY Control Room staff of declaration and upgrade criteria (if any).
4.1.2 IF the emergency is due to a Security Event, THEN REFER TO Enclosure 3 before proceeding with the following steps.
4.1.3 NOTIFY Plant Personnel using information from Step 4.1.12.
REQUIRED WITHIN 15 MINUTES 4.1.4 NOTIFY SWPT within 15 minutes of declaration using Enclosure 2 and FAX after notification is complete. (Also REFER to Step 4.1.9.)
RECOMMENDED WITHIN 15 MINUTES 4.1.5 IF a release is occurring as a result of this event, THEN COMPLETE EM-204A, as time permits.
RECOMMENDED WITHIN 30 MINUTES 4.1.6 NOTIFY PGM or EC on-call. REQUEST he notify the EOF Director.
4.1.7 NOTIFY CR-3 NRC Resident Inspector.
4.1.8 NOTIFY Units 1/2 & 4/5 Control Rooms per Enclosure 5.
4.1.9 NOTIFY NRC via ENS as soon as practicable after the State per Enclosure 4.
REQUIRED WITHIN 60 MINUTES.
EM-202 Rev. 70 Page 11 of 59
Unusual Event Updates/Termination TIME 4.1.10 PROVIDE periodic plant status updates to:
- SWPT (every 60 minutes or as agreed upon) per Enclosure 2
- NRC per Enclosure 4 (after State of Florida update, unless continuous communication established)
- Units 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcements 4.1.11 If terminating, NOTIFY: DATE
- Emergency Coordinator on-call and REQUEST notification to EOF Director
- SWPT and document on Enclosure 2
- NRC within one hour of termination with verbal summary per Enclosure 4
- Unit 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcement EM-202 Rev. 70 Page 12 of 59
4.1.12 PA Announcement for an Unusual Event ANNOUNCE or PERFORM the following: Time:
- 1) ACTUATE the appropriate local evacuation alarm if required.
- 2) "ATTENTION ALL PERSONNEL, CRYSTAL RIVER 3 IS IN AN UNUSUAL EVENT BASED ON 11
- 3) "THERE (IS OR IS NOT) A RADIOLOGICAL RELEASE TO THE ENVIRONMENT IN PROGRESS."
- 4) STATE any appropriate special instructions (areas to be avoided or evacuated, etc.).
(IF conditions warrant personnel accountability, THEN REQUEST personnel to report to Local Assembly Areas).
- 5) REPEAT the announcement.
- 6) ESTABLISH continuous monitoring on PL-1.
EM-202 Rev. 70 Page 13 of 59
4i.2 Emergency Coordinator's Guide for an Alert [NOCS 1129, 96042]
TIME ALERT DECLARED DATE I
--- RECOMMENDED WITHIN 5 MINUTES 4.2.1 NOTIFY Control Room staff of declaration and upgrade criteria (if any).
4.2.2 IF the emergency is due to a Security Event, THEN REFER TO Enclosure 3 before proceeding with the following steps.
4.2.3 IF safe conditions exist, THEN NOTIFY Security to activate the TSC.
4.2.4 NOTIFY Plant Personnel using information from Step 4.2.16.
REQUIRED WITHIN 15 MINUTES 4.2.5 NOTIFY SWPT within 15 minutes of declaration per Enclosure 2 and FAX after notification is complete. (Also REFER to Step 4.2.10.)
RECOMMENDED WITHIN 15 MINUTES 4.2.6 IF a release is occurring as a result of this event, THEN COMPLETE EM-204A or EM-204B, as time permits.
RECOMMENDED WITHIN 30 MINUTES 4.2.7 NOTIFY PGM or EC on-call. REQUEST he notify the EOF Director.
4.2.8 NOTIFY CR-3 NRC Resident Inspector.
4.2.9 NOTIFY Units 1/2 & 4/5 Control Rooms per Enclosure 5.
4.2.10 NOTIFY NRC via ENS as soon as practicable after the State per Enclosure 4.
REQUIRED WITHIN 60 MINUTES.
4.2.11 ACTIVATE ERDS per Enclosure 6.
REQUIRED WITHIN 60 MINUTES.
ONCE TSC OPERATIONAL 4.2.12 NOTIFY Corporate Security.
4.2.13 NOTIFY Risk Management to notify ANI and NEIL insurance that CR-3 is in an emergency declaration. (Off-Site Support Phone Directory)
EM-202 Rev. 70 Page 14 of 59
Alert Updates/Termination TIME 4.2.14 PROVIDE periodic plant status updates to:
- SWPT (every 60 minutes or as agreed upon) per Enclosure 2 including the Supplemental Data Sheet
- Units 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcements 4.2.15 If terminating, NOTIFY: DATE /
- Company Senior Officer, if requested
- PGM and EOF Director
- SWPT and document on Enclosure 2
- NRC within one hour of termination with verbal summary
- Unit 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcement
- Corporate Security Specialist
- Risk Management (Off-Site Support Phone Directory)
- REQUEST Licensing to prepare a written summary within twenty-four hours (or next working day) of termination to SWPT and NRC.
EM-202 Rev. 70 Page 15 of 59
4.2.16 PA Announcement for an Alert CONSIDER safety of plant personnel and then ANNOUNCE or PERFORM the following:
Time:
- 1) ACTUATE the appropriate local evacuation alarm if required.
- 2) "ATTENTION ALL PERSONNEL, CRYSTAL RIVER 3 IS IN AN ALERT BASED ON
- 3) "THERE (IS OR IS NOT) A RADIOLOGICAL RELEASE TO THE ENVIRONMENT IN PROGRESS."
- 4) "ACTIVATE THE TSC/OSC. REPORT TO YOUR SHOP OR LOCAL ASSEMBLY AREA FOR ACCOUNTABILITY."
- 5) STATE any appropriate special instructions (areas to be avoided or evacuated, remaining at critical jobs, etc.).
- 6) REPEAT the announcement.
- 7) ESTABLISH continuous monitoring on PL-1.
EM-202 Rev. 70 Page 16 of 59
4.3 Emergency Coordinator's Guide for Site Area Emergency
[NOCS 1129, 96042]
TIME SITE AREA EMERGENCY DECLARED DATE RECOMMENDED WITHIN 5 MINUTES 4.3.1 NOTIFY Control Room staff of declaration and upgrade criteria (if any).
4.3.2 IF the emergency is due to a Security Event, THEN REFER TO Enclosure 3 before proceeding with the following steps.
4.3.3 IF safe conditions exist, THEN NOTIFY Security to activate the EOF and TSC.
4.3.4 NOTIFY Plant Personnel using information from Step 4.3.19 and ACTUATE Site Evacuation Alarm.
REQUIRED WITHIN 15 MINUTES 4.3.5 NOTIFY SWPT within 15 minutes of declaration per Enclosure 2 and FAX after notification is complete. (Also REFER to Step 4.3.11.)
RECOMMENDED WITHIN 15 MINUTES [NOCS 9090,9130]
4.3.6 DETERMINE protective actions for Energy Complex using Enclosure 7. NOTIFY Nuclear Security to coordinate with Corporate Security to ENSURE protective action instructions are provided for all areas of the Energy Complex.
4.3.7 NOTIFY Units 1/2 & 4/5 Control Rooms per Enclosure 5.
4.3.8 IF a release is occurring as a result of this event, THEN COMPLETE EM-204A or EM-204B, as time permits.
RECOMMENDED WITHIN 30 MINUTES 4.3.9 NOTIFY PGM or EC on-call. REQUEST he notify the EOF Director.
4.3.10 NOTIFY CR-3 NRC Resident Inspector.
4.3.11 NOTIFY NRC via ENS as soon as practicable after the State per Enclosure 4.
REQUIRED WITHIN 60 MINUTES.
(Once operational, this responsibility stays at TSC.)
4.3.12 ENSURE ERDS is activated per Enclosure 6.
REQUIRED WITHIN 60 MINUTES.
EM-202 Rev. 70 Page 17 of 59
ONCE TSC OPERATIONAL TIME 4.3.13 VERIFY Protected Area accountability is completed by Security within 30 minutes of an evacuation of the Protected Area.
4.3.14 NOTIFY Risk Management to notify ANI and NEIL insurance that CR-3 is in an emergency declaration. (Off-Site Support Phone Directory)
SITE AREA UPDATESITERMINATION 4.3.15 PROVIDE periodic plant status updates to:
- SWPT (every 60 minutes or as agreed upon) per Enclosure 2 including the Supplemental Data Sheet
- Units 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcements 4.3.16 IF recommending termination, entering the recovery phase, or de-escalating the event, THEN COORDINATE the decision with the State, counties, the EOF Director and if requested, the Company Senior Officer, before completing the Florida Nuclear Plant Emergency Notification Form.
CONSIDER the following when making this determination:
- Is a release continuing.
- Are plant conditions stable and expected to remain stable.
- Is the full emergency response organization needed to support safe and stable operation, or mitigation activities.
- Do radiological and other plant conditions permit resumption of normal personnel exposure limits to continue mitigation repair activities.
- Do radiological and other plant conditions permit resumption of normal access to plant and surrounding areas.
DATE 4.3.17 NOTIFY:
- NRC within one hour of termination with verbal summary
- Units 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcement
- Corporate Security Specialist
- Risk Management (Off-Site Support Phone Directory) 4.3.18 REQUEST Licensing to prepare a written summary within twenty-four hours (or next working day) of termination to SWPT and NRC.
EM-202 Rev. 70 Page 18 of 59
4.3.19 PA Announcement for a Site Area Emergency
[NOCS 7455]
CONSIDER safety of plant personnel and then ANNOUNCE or PERFORM the following:
Time:
- 1) ACTUATE the Site Evacuation alarm.
- 2) "ATTENTION ALL PERSONNEL, CRYSTAL RIVER 3 IS IN A SITE AREA EMERGENCY BASED ON it
- 3) "THERE (IS OR IS NOT) A RADIOLOGICAL RELEASE TO THE ENVIRONMENT IN PROGRESS."
- 4) IF the TSC/OSC is NOT activated, THEN ANNOUNCE: "ACTIVATE THE TSC/OSC."
- 5) "PERSONNEL ARE TO IMMEDIATELY EVACUATE THE PROTECTED AREA AND REPORT TO THE SITE ADMINISTRATION BUILDING AUDITORIUM."
- 7) STATE any appropriate special instructions (areas to be avoided or evacuated, etc.).
- 8) REPEAT the announcement.
- 9) ESTABLISH continuous monitoring on PL-1.
EM-202 Rev. 70 Page 19 of 59
4.4 Emergency Coordinator's Guide for General Emergency
[NOCS 1129, 96042]
GENERAL EMERGENCY DECLARED. DATE TIME RECOMMENDED WITHIN 5 MINUTES TIME 4.4.1 IF the EOF is operational, THEN NOTIFY the EOF Director of the classification change.
4.4.2 NOTIFY Control Room staff of declaration.
4.4.3 IF the emergency is due to a Security Event, THEN REFER TO Enclosure 3 before proceeding with the following steps.
4.4.4 IF safe conditions exist, THEN NOTIFY Security to activate the TSC and EOF (if NOT activated).
4.4.5 NOTIFY Plant Personnel using information from Step 4.4.20 and ACTUATE Site Evacuation Alarm if Protected Area NOT already evacuated.
REQUIRED WITHIN 15 MINUTES 4.4.6 DETERMINE Protective Action Recommendations per Enclosure 8.
(Minimum Protective Action Recommendations is to evacuate Zone 1.)
4.4.7 IF the EOF is NOT operational, THEN NOTIFY SWPT within 15 minutes of declaration per Enclosure 2 and FAX after notification is complete. (Also REFER to Step 4.4.12.)
RECOMMENDED WITHIN 15 MINUTES 4.4.8 DETERMINE Energy Complex protective actions per Enclosure 7 and NOTIFY Nuclear Security to coordinate with Corporate Security to ENSURE evacuation instructions are provided for all areas of the Energy Complex.
4.4.9 NOTIFY Units 1/2 & 4/5 Control Rooms per Enclosure 5.
4.4.10 IF a release is occurring as a result of this event, THEN COMPLETE EM-204A or EM-204B, as time permits.
RECOMMENDED WITHIN 30 MINUTES (NOT necessary if TSC and EOF Operational) 4.4.11 NOTIFY CR-3 NRC Resident Inspector.
4.4.12 NOTIFY NRC via ENS as soon as practicable after the State per Enclosure 4.
REQUIRED WITHIN 60 MINUTES.
(Once operational this responsibility stays at TSC.)
4.4.13 ENSURE ERDS is activated per Enclosure 6.
REQUIRED WITHIN 60 MINUTES.
EM-202 Rev. 70 Page 20 of 59
ONCE TSC IS OPERATIONAL TIME 4.4.14 VERIFY Protected Area accountability is completed by Security within 30 minutes of an evacuation of the Protected Area.
NOTIFY Risk Management to notify ANI and NEIL insurance that
- -- 4.4.15 CR-3 is in an emergency declaration. (Off-Site Support Phone Directory)
GENERAL EMERGENCY UPDATES/TERMINATION 4.4.16 PROVIDE periodic plant status updates to:
- SWPT (every 60 minutes or as agreed upon) per Enclosure 2 including the Supplemental Data Sheet
- Units 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcements 4.4.17 IF recommending termination, entering the recovery phase, or de-escalating the event, THEN COORDINATE the decision with the State, counties, the EOF Director and if requested, the Company Senior Officer, before completing the Florida Nuclear Plant Emergency Notification Form.
Consider the following when making this determination:
- Is a release continuing.
- Are plant conditions stable and expected to remain stable.
- Is the full emergency response organization needed to support safe and stable operation, or mitigation activities.
- Do radiological and other plant conditions permit resumption of normal personnel exposure limits to continue mitigation repair activities.
- Do radiological and other plant conditions permit resumption of normal access to plant and surrounding areas.
DATE /
4.4.18 NOTIFY:
- NOTIFY NRC within one hour of termination with verbal summary
- Unit 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcement
- Corporate Security Specialist
- Risk Management (Off-Site Support Phone Directory) 4.4.19 REQUEST Licensing to prepare a written summary within twenty-four hours (or next working day) of termination to SWPT and NRC.
EM-202 Rev. 70 Page 21 of 59
4.4.20 PA Announcement for a General Emergency
[NOCS 7455]
CONSIDER safety of plant personnel and then ANNOUNCE or PERFORM the following:
Time:
- 1) IF the Protected Area has NOT been evacuated, THEN ACTUATE the Site Evacuation alarm.
- 2) "ATTENTION ALL PERSONNEL, CRYSTAL RIVER 3 IS IN A GENERAL EMERGENCY BASED ON
- 3) "THERE (IS OR IS NOT) A RADIOLOGICAL RELEASE TO THE ENVIRONMENT IN PROGRESS."
- 4) IF the TSC/OSC is NOT activated, THEN ANNOUNCE: "ACTIVATE THE TSC/OSC."
- 5) IF the Protected Area has NOT been evacuated, THEN ANNOUNCE: "ALL NON-ESSENTIAL PERSONNEL, IMMEDIATELY EVACUATE THE PROTECTED AREA AND FOLLOW INSTRUCTIONS FROM SECURITY."
- 7) STATE any appropriate special instructions (areas to be avoided or evacuated, etc.).
- 8) REPEAT the announcement.
- 9) ESTABLISH continuous monitoring on PL-1.
EM-202 Rev. 70 Page 22 of 59
ENCLOSURE 1 (Page 1 of 16)
EMERGENCY CLASSIFICATION TABLE EMERGENCY ACTION LEVEL INDEX
- ABNORMAL RDLEVELSI RADIOL*OGICAL EFFLU ENT CATEGORY UE ALERT SAE GE Gaseous Effluents 1.1 1.2 1.3 1.4 Liquid Effluents 1.5 1.6 Unexpected Radiation Levels 1.7 1.8 Fuel Handling Spent Fuel Pool or Transfer 1.9 1.10 Canal Water Level NATURAL/MANMADE HAZARDS AND EC JUDGEMENT CATEGORY .UEALERT SAE GE Earthquake Experienced 2.1 2.2 External Flooding 2.3 2.4 Hurricane 2.5 Tornado/High Winds 2.6 2.7 Aircraft/Vehicle Crash 2.8 2.9 Toxic or Flammable Gases 2.10 2.11 Explosions/Catastrophic Pressurized 2.12 2.13 Equipment Failure Fire 2.14 2.15 Control Room Evacuation 2.16 2.17 Security Event 2.18 2.19 2.20 2.21 Internal Flooding 2.22 2.23 Emergency Coordinator Judgment 2.24 2.25 2.26 2.27 SYSTEM MALFUNCTION CATEGORY UE ALERT SAE GE Loss of Communications 3.1 Failure of Reactor Protection 3.2 3.3 3.4 Inability to Reach ITS Time Limits 3.5 Loss of Alarms/Indications 3.6 3.7 3.8 Fuel Clad Degradation 3.9 Turbine Failure 3.10 3.11 RCS Leakage 3.12 Inability to Maintain Hot Shutdown 3.13 Inadvertent Criticality 3.14 Inability to Maintain Plant in Cold Shutdown 3.15 Loss of Water Level in Reactor Vessel that 3.16 has Uncovered or Will Uncover Fuel
~LOSSOFPOWER
<CATEGORY<'A>~' UE ~ ALERT ~ SAE G Loss of AC Power 4.1 4.2 4.3 4.4 Loss of AC Power (Shutdown) 4.5 Loss of Vital DC Power 4.6 Loss of Vital DC Power (Shutdown) 4.7 EM-202 Rev. 70 Page 23 of 59
( ( '
'.OSURE I
, ge2of16) 1.
Emergency Classification Table FISSION PRODUCT BARRIER MATRIX APPi I(ARI iF uM~nnf*, 4-A ('*IMPl I=TF: FAr'P
.*.A.JI'
,. I II HUIN 114 rxr_,.3IUjIN a*j
. rx M.10 L-LJrIx .FJI %J I .0%. I UDL- L[Ut/VX\ rI..UL I I1I1%.7 DECIRE UNr'ASFLLOW/CING_ INIID ALrCOOUrEArS SEVERE ACCIDENT REGION OF ICC LOSS OF ADEQUATE SUBCOOLING MARGIN DECREASE FOLLOWING INITIAL INCREASE CURVES
- 2. RCS ACTIVITY >300 pCi/gm 1-131 2. RM-G29 OR 30 > 10 R/hr FOR 15 MINUTES OR 2. CONTAINMENT PRESSURE OR SUMP LEVEL LONGER RESPONSE NOT CONSISTENT WITH LOCA CONDITIONS
- 3. RM-G29 OR 30 >100 R/hr FOR 15 MINUTES 3. EC DEEMS RCS BARRIER IS LOST 3. AN OTSG HAS > 10 GPM TUBE RUPTURE OR LONGER WITH PROLONGED STEAMING TO THE ATMOSPHERE FROM THE AFFECTED OTSG OR AN UNISOLABLE STEAM LEAK OUTSIDE RB FROM THE AFFECTED OTSG
- 4. EC DEEMS FUEL CLAD BARRIER IS LOST 4. CONTAINMENT ISOLATION IS INCOMPLETE AND RELEASE PATH TO THE ENVIRONMENT EXISTS
- 5. EC DEEMS CONTAINMENT BARRIER IS LOST POETA OSO FUE CLAD % POTEN4TIAL LOSS OF REACTOR COOL.ANT POTENTIAL LOSSOF CONTAINMENT Iftany item is checked, barrier is potentially lost. SYSTEMIfayie isc ckdbririsptnallo .
Ente 3 o ULCAncasfctiontble below.x ~ ifanyitemi hcebriri oetal ot Enter 1. 5for CONTAINMENT iclsfcaontable
.Enter3 for R.S.in classification tble below. blw w
- 1. RCS CONDITIONS WARRANT ENTRY INTO 1. RCS LEAK OR OTSG TUBE LEAK REQUIRING ONE 1. RB PRESSURE >54 psig EOP-07 OR MORE INJECTION VALVES
- 2. CORE EXIT THERMOCOUPLES >700°F 2. RCS LEAK OR OTSG TUBE LEAK RESULTS IN ES 2. RB HYDROGEN CONCENTRATION >4%
ACTUATION ON LOW RCS PRESSURE 3, EC DEEMS FUEL CLAD BARRIER IN 3. RCS PRESSURE/TEMPERATURE RELATIONSHIP 3. RB PRESSURE >30 psig WITH NO BUILDING JEOPARDY VIOLATES NDT LIMITS SPRAY AVAILABLE
- 5. EC DEEMS RCS BARRIER IN JEOPARDY 5. CORE CONDITIONS IN SEVERE ACCIDENT REGION OF ICC CURVES FOR >15 MINUTES
- 6. EC DEEMS CONTAINMENT BARRIER IN JEOPARDY CLASSIFICATION TABLE ENTER LOSS OR POTENTIAL LOSS OR ZERO FOR EACH BARRIER THEN TOTAL AND DETERMINE CLASS BELOW FUEL CLAD + RCS + CONTAINMENT =
'IF TOTALIS: RECOMMENDED EVENT CLASSIFICATION IS:
> 0 BUT < 2 UNUSUAL EVENT
> 2 BUT < 4 ALERT
> 4 BUT < 8.5 SITE AREA EMERGENCY
> 8.5 GENERAL EMERGENCY EM-202 Rev. 70 Page 24 of 59
( ( ( 'LOSURE i age 3 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
ABNORMAL RAD LEVELS/RADIOLOGICAL EFFLUENT Gaseous Effluents 1.1 MODES: ALL 1.2 MODES: ALL 1.3 MODES: ALL 1.4 MODES: ALL MODES: ALL (1 or 2) (1 or 2) (1 or 2 or 3) (1 or 2 or 3)
- 1. A VALID reading on RM-A1 or RM-A2 1. A VALID reading on RM-A1 or RM-A2 1. VALID RM-A1 or RM-A2 Mid-Range 1. VALID RM-A1 or RM-A2 Mid-Range gas channel exceeds the high alarm Mid-Range monitor exceeds 6mR/hr. monitor reading exceeds the values on monitor reading exceeds the values on setpoint for 60 minutes or longer for 15 minutes or longer the following Table for the current the Table below for the current Stability Class for 15 minutes or Stability Class for 15 minutes or longer: longer:
Stab. Class Reading (mRPhr) Stab. Class Reading (mRPhr)
A. BorC 100 A, B or C 1000 D or E 20 D or E 200 ForG 12 F or G 120 OR OR OR OR
- 2. Sample analysis confirms gaseous 2. Sample analysis confirms gaseous 2. Dose Assessment results indicate 2. Dose Assessment results indicate SITE effluent being released exceeds effluent being released exceeds SITE BOUNDARY dose >100 mR BOUNDARY dose >1000 mR TEDE or 2 times the ODCM noble gas release 200 times the ODCM noble gas TEDE or >500 mR thyroid CDE for the >5000 mR thyroid CDE for the actual or setpoint for 60 minutes or longer release setpoint for 15 minutes or actual or projected duration of the projected duration of the release AND longer release core damage is suspected or has occurred OR OR
- 3. Field survey results indicate closed windows dose rates >lO0mR/hr 3. Field survey results indicate closed expected to continue for more than windows dose rates >10OOmR/hr one hour; or analyses of field survey expected to continue for more than one samples indicate thyroid CDE of hour; or analyses of field survey sample 500mR for one hour of inhalation, at or indicate thyroid CDE of 5000 mR for one beyond SITE BOUNDARY hour of inhalation, at or beyond SITE BOUNDARY Liquid Effluents 1.s MODES: ALL 1.6 MODES: ALL NotAppiicable Not Applicable MODES: ALL (1 or 2) A VALID reading on RM-L2, RM-L7, or sample analysis confirms the release
- 1. A VALID reading on RM-L2, RM-L7, exceeds 200 times the ODCM release or sample analysis confirms the setpoint for 15 minutes or longer release exceeds 2 times the ODCM release setpoint for 60 minutes or longer OR
- 2. Release continued for 60 minutes or longer with no dilution flow EM-202 Rev. 70 Page 25 of 59
( f *'LOSURE'1 age 4 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
,D LEVELSIRADIOLOGICAL EFFLUENT Unexpected Radiation 1.7 MODES: ALL 1.8 MODES: ALL Levels One or more VALID radiation monitor (1 or 2) readings unexpectedly exceed the values MODES: ALL below for 15 minutes or longer: 1. VALID radiation reading greater than 15 mR/hr for 15 minutes or longer in RM-G3 = 400 mR/hr the Control Room (RM-G1) or the RM-G4 = 600 mR/hr Central Alarm Station (CAS)
RM-G5 = 3,000 mR/hr RM-G9 = 100 mR/hr OR RM-G10 = 800 mRJhr RM-G14 = 1,000 mR/hr 2. One or more VALID radiation monitor RM-G17 = 800 mR/hr readings unexpectedly exceed the values below for 15 minutes or longer:
RM-G3 = 5,000 mR/hr RM-G4 = 5,000 mR/hr RM-G9 = 5,000 mR/hr RM-G10 = 5,000 mR/hr RM-G17 = 5,000 mR/hr i i Fuel Handling 1.9 MODES: ALL 1.10 MODES: ALL Spent Fuel Pool or (1 and 2) (1 or 2)
Transfer Canal Water 1. (a and b)
- 1. (a or b)
Level
- a. Uncontrolled level decrease resulting a. Plant personnel report damage of in indications of -2.5 feet in spent fuel irradiated fuel MODES: ALL pool AND OR
- b. VALID high alarm as indicated on
- b. Confirmed plant personnel report of RM-G15 or RM-G16 uncontrolled significant water level drop in spent fuel pool or transfer OR canal when Spent Fuel transfer tubes are open 2. Plant personnel report spent fuel pool or transfer canal water level drop has AND or will exceed makeup capacity such that irradiated fuel will be uncovered
- 2. Fuel remains covered with water EM-202 Rev. 70 Page 26 of 59
'.OSURE 1.
.ge 5 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION NATURAL/MANMADE HAZARDS AND EC JUDGEMENT CAEGR UNSULB LETSIEARAMRGN Y GENERL MERGENQ4Y1 K Earthquake Experienced 2.1 MODES: ALL 2.2 MODES: ALL Refer to Fission Product Baier Matrx.or Refer to Fission Product BarrierMatrix Emergency CoordinatorJudgment Emergency Coordinator Judgment MODES: ALL (1 and 2) (1 and 2)
- 1. Ground motion sensed by plant 1. Ground motion sensed by plant personnel personnel or confirmed Annunciator 0-3-14 "Seismic System Trouble" AND alarm
- 2. Confirmed earthquake causing AND Annunciator C-3-14 "Seismic System Trouble" alarm 2. (a or b)
- a. Analysis confirms the earthquake at OR
- b. Indications show degraded SAFE SHUTDOWN EQUIPMENT performance due to the earthquake External Flooding 2.3 MODES: ALL 2.4 MODES: ALL Refer to Fission Product Barrier Matrix or Refer to Fission Product Barrier Matrix or Emergency Coordinator Judgment Emergency Coordinator Judgment Mfll~.A gIntake canal level or visual observation (1 and 2) indicates flood water level > 98 feet
- 1. Intake canal level or visual observation indicates flood water level a 98 feet AND
- 2. Indications show degraded SAFE SHUTDOWN EQUIPMENT performance due to the flooding Hurricane 2.5 MODES: ALL The plant is within a Hurricane Warning MODES: ALL area EM-202 Rev. 70 Page 27 of 59
( ( f ..OSURE I t.ge 6 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
SAKfn 2.6 MU.)Lhb: ALL 2.7 MUUIIh: ALL TornadolHigh Winds Report by plant personnel of a Tornado (1 and 2)
MODES: ALL striking within the PROTECTED AREA
- 1. Tornado or High Winds orwindbome object strike one of the following structures:
Auxiliary Building, BWST, Control Complex, Diesel Generator Building, EFT-2 Building, Intermediate Building, Reactor Building EFP-3 Building AND
- 2. (a or b)
- a. Confirmed report of significant VISIBLE DAMAGE to buildings listed above OR
- b. Indications show degraded SAFE SHUTDOWN EQUIPMENT performance due to the tornado or high winds or windborne objects
2.8 MODES
ALL 2.9 MODES: ALL AircraftlVehicle Crash Report by plant personnel of Aircraft or (1 or 2)
Vehicle Crash involving the following MODES: ALL permanent structures: 1. Confirmed report of significant VISIBLE DAMAGE to buildings listed below:
Auxiliary Building, BWST Control Complex Auxiliary Building BWST Diesel Generator Building Control Complex EFT-2 Building Diesel Generator Building Intermediate Building EFT-2 Building Reactor Building Intermediate Building EFP-3 Building Reactor Building EFP-3 Building OR
- 2. Indications show degraded SAFE SHUTDOWN EQUIPMENT performance due to the Aircraft or Vehicle Crash EM-202 Rev. 70 Page 28 of 59
(i EME C Tge CO
( LOSURElI 7 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
TI IDAI iT Toxic or Flammable 2.10 MODES: ALL 2.11 MODES: ALL Gases (1 or 2) (1 or 2 or 3)
- 1. Report or detection of Toxic or 1. Flammable Gas levels > 25% Lower MODES: ALL Flammable Gas within the SITE Explosive Limit in areas required to BOUNDARY that could enter the maintain safe operations or establish Protected Area at levels >IDLH or and maintain cold shutdown
>25% Lower Explosive Limits affecting normal operation of the plant OR OR 2. Toxic Gas levels > IDLH levels in
- 2. areas that require continuous Confirmed notification by FPC, County, occupancy to maintain safe operation or State personnel to evacuate or or establish or maintain cold shutdown shelter site personnel based on an offsite event OR
- 3. Toxic Gas levels Ž IDLH levels within the PROTECTED AREA such that plant personnel are unable to perform actions necessary to maintain safe operations or establish and maintain cold shutdown using protective equipment EM-202 Rev. 70 Page 29 of 59
( "LOSURE1 age 8 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
NATURALIMANMADE HAZARDS AND EC JUDGEMENT Explosions/ 2.12 MODES: ALL 2.13 MODES: ALL Catastrophic Pressurized Report by plant personnel of VISIBLE (1 and 2)
DAMAGE to permanent structures or Equipment Failure equipment within the PROTECTED AREA 1. EXPLOSION or catastrophic failure of due to an EXPLOSION or catastrophic pressurized equipment in any of the MODES: ALL failure of pressurized equipment following structures:
Auxiliary Building Refer to Security Event BWST Control Complex Diesel Generator Building EFT-2 Building, Intermediate Building Reactor Building EFP-3 Building AND
- 2. (a or b)
- a. Report by plant personnel of EXPLOSION or catastrophic failure of pressurized equipment causing VISIBLE DAMAGE to SAFE SHUTDOWN EQUIPMENT OR
- b. Indications show degraded SAFE SHUTDOWN EQUIPMENT performance due to the EXPLOSION or pressurized equipment failure Fire 2.14 MODES: ALL 2.15 MODES: ALL (1 and 2) (I or 2)
MODES: ALL
- 1. FIRE in or threatening one of the 1. Report by plant personnel of VISIBLE following structures: DAMAGE to SAFE SHUTDOWN Auxiliary Building EQUIPMENT due to the FIRE BWST Control Complex, OR Diesel Generator Building
- 2. Indications show degraded SAFE EFT-2 Building SHUTDOWN EQUIPMENT Intermediate Building performance due to the FIRE Reactor Building EFP-3 Building AND
- 2. FIRE not extinguished within 15 minutes from either Control Room notification or receipt of a VALID fire alarm in the Control Room EM-202 Rev. 70 Page 30 of 59
( ( f "LOSURE'l
"* 9of 16) 9ge EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
UA7ADrQ AKdrl .it Control Room Evacuation 2.16 MODES: ALL 2.17 MODES: ALL MODES: ALL Control Room evacuation is required per (1 and 2)
AP-990, 'Shutdown Outside of the Control Room* 1. Control Room evacuation is required per AP-990, "Shutdown Outside of the Control Room" AND
- 2. Control of the necessary equipment not established per AP-990 within 15 minutes Security Event 2.18 MODES: ALL 2.19 MODES: ALL 2.20 MODES: ALL 2.21 MODES: ALL (1 or 2 or 3) (1 or 2) INTRUDER(S) penetrates or a BOMB is INTRUDER(S) has taken control of the MODES: ALL discovered in any of the areas listed Control Room, or Remote Shutdown Room Report by Security Shift Supervisor of one 1. Discovery of BOMB within the below: or plant equipment such that plant or more of the following events: PROTECTED AREA personnel are unable to operate Auxiliary Building equipment required to establish and
- 1. Occurrence of SABOTAGE OR BWST maintain safe shutdown conditions Control Complex OR
- 2. INTRUDER(S) penetrates the EFT-2 Building PROTECTED AREA Diesel Generator Building
- 2. HOSTAGE/EXTORTION situation or Intermediate Building hostile STRIKE ACTION threatening to Reactor Building interrupt plant operations EFP-3 Building OR
- 3. A violent CIVIL DISTURBANCE ongoing outside of the PROTECTED AREA but within the SITE BOUNDARY OR
- 4. A CREDIBLE SITE-SPECIFIC SECURITY THREAT NOTIFICATION EM-202 Rev. 70 Page 31 of 59
.'OSURE1.
( ,e10 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
NATURAL/MANMADE HAZARDS AND EC JUDGEMENT Internal Flooding 2.22 MODES: ALL 2.23 MODES: ALL (1 and 2) (1 and 2)
Modes: ALL
- 1. Indication of uncontrolled flooding in 1. Water level exceeds 1.5 feet in the the Auxiliary Building or Intermediate Auxiliary Building or Intermediate Building Building AND AND
- 2. Water level/flooding has the potential to 2. (a or b) affect or immerse SAFE SHUTDOWN EQUIPMENT a. Indications show degraded SAFE SHUTDOWN EQUIPMENT due to the flooding 11 OR
- b. Electrical hazards prevent plant personnel normal access to areas of plant containing SAFE SHUTDOWN EQUIPMENT I .4-Emergency Coordinator 2.24 MODES: ALL 2.25 MODES: ALL 2.26 MODES: ALL 2.27 MODES: ALL Judgment Other conditions exist which indicate a Other conditions exist which indicate that Other conditions exist which indicate (1 or 2) potential degradation of the level of safety events are in process or have occurred actual or likely major failures of plant of the plant which involve potential or actual functions needed for the protection of the Other conditions exist which indicate:
MODES: ALL substantial degradation of the level of public safety of the plant 1. Actual or imminent substantial core degradation with potential loss of containment integrity OR
- 2. The potential for uncontrolled radionuclide releases that can be expected to exceed EPA Protective Action Guidelines Plume Exposure Levels beyond the SITE BOUNDARY (see EAL 1.4)
EM-202 Rev. 70 Page 32 of 59
'_OSURE I
, , t- je 11 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
SYSTEM MALFUNCTION Failure of Reactor Not Applicable 3.2 MODES: 1,2,3 3.3 MODES: 1,2 3.4 MODES: 1,2 Protection (1 and 2) (1 and 2) (1 and 2 and 3)
MODES: 1,2,3 for ALERT 1. RPS Trip setpoint exceeded and no 1. RPS Trip setpoint exceeded and no 1. RPS Trip setpoint exceeded and no Reactor trip occurred Reactor trip occurred Reactor trip occurred MODES: 1,2 for SITE AREA and AND AND GENERAL Emergencies AND
- 2. Manual Reactor trip from Control Room 2. Manual Reactor trip from Control Room was successful and reactor is was not successful in shutting down 2. Manual Reactor trip from Control Room shutdown the reactor was not successful in shutting down the reactor AND
- 3. (a or b)
- a. Core exit thermocouple temperatures
> 7000°F, as indicated on SPDS.
- b. Adequate Secondary Cooling not available EM-202 Rev. 70 Page 33 of 59
( ( _OSURE 1 (Page 12 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
VQT M/A1 ItlMCTltM Inability to reach required 3.5 MODES: 1,2,3,4 mode within Improved (1 and 2)
Technical Specification
- 1. Entry into an Improved Technical time limits Specification LCO statement requiring a mode reduction AND MODES: 1,2,3,4
- 2. The plant is not in the required operating mode within the time prescribed by the LCO required action Loss of 3.6 MODES: 1,2,3,4 3.7 MODES: 1,2,3,4 3.8 MODES: 1,2,3,4 Alarms/indications (1 or 2) (1 and 2) (1 and 2 and 3 and 4)
- 1. UNPLANNED loss of Annunciator 1. (a or b) 1. (a orb)
MODES: 1,2,3,4 panels A-L and Annunciator printer for 15 minutes or longer a. UNPLANNED loss of Annunciator a. Loss of Annunciator panels A-L and panels A-L and Annunciator printer Annunciator printer for 15 minutes or OR for 15 minutes or longer longer
- b. UNPLANNED loss of NNI-X and b. Loss of NNI-X and NNI-Y for NNI-Y for 15 minutes or longer 15 minutes or longer AND AND
- 2. (a or b) 2. SIGNIFICANT TRANSIENT in progress
- b. Loss of Plant Computer and SPDS AND
- 4. Inability to directly monitor any one of the following:
Subcriticality Core Cooling Containment RCS Inventory EM-202 Rev. 70 Page 34 of 59
,( ",
'LOSURE1 je13of16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
QVQTF=M MAI 9I1 I1ikiTI'Kl
3.9 MODES
1,2,3,4,5 Fuel Clad Degradation (a or b)
MODES: 1,2,3,4,5 Radiochemistry analysis indicates:
- a. Dose Equivalent Iodine (1-131)
>1.0 pCi/gm for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer OR
- b. Specific activity >100/E-bar for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer Turbine Failure 3.10 MODES: 1,2,3 3.11 MODES: 1,2,3 MODES: 1,2,3 Report by plant personnel of main turbine (1or 2) failure causing penetration of the turbine casing or damage to main generator seals 1. Report by plant personnel of projectiles generated by a main turbine failure causing significant VISIBLE DAMAGE any of the following structures:
Auxiliary Building BWST Control Complex Diesel Generator Building EFT-2 Building Intermediate Building Reactor Building EFP-3 Building OR
- 2. Indications show degraded SAFE SHUTDOWN EQUIPMENT performance due to turbine generated projectiles EM-202 Rev. 70 Page 35 of 59
" 'LOSURE1 S ..... " .je14 ofl16)
TABLE EMERGENCY CLASSIFICATION ACCIDENT CONDITION:
EM-202 Rev. 70 Page 36 of 59
(k. *, e 15 of 16)1.
'.OSURE EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
QV5qTFM MAI FlINCTION EM-202 Rev. 70 Page 37 of 59
( '*OSURE 1'
- b je 16 of 16)
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
LOSS OF POWER Loss of AC Power 4.1 MODES: ALL 4.2 MODES: 1,2,3,4 4.3 MODES: 1,2,3,4 4.4 MODES: 1,2,3,4 (1 and 2) AC power capability to the 4160V ES Neither 4160V ES bus is capable of being (1 and 2) busses reduced to a single power source energized within 15 minutes MODES: ALL for UNUSUAL 1. Offsite Power Transformer (OPT) and for 15 minutes or longer such that only 1. Neither 4160V ES bus is capable of EVENT Backup ES Transformer (BEST) and one of the following is available: being energized MODES: 1,2,3,4 for ALERT, Auxiliary Transformer not available for 15 minutes or longer "A"EDG AND SITE AREA and "B"EDG GENERAL AND 2. (a orb)
Emergencies Offsite Power Transformer (OPT)
- 2. EDGs supplying power to required Backup ES Transformer (BEST) a. Restoration of 4160V ES Bus A or 4160V ES Busses 4160V ES Bus B is not likely within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> '
- b. Core exit thermocouples > 700°F as indicated on SPDS Loss of AC Power Not Applicable 4.5 MODES: 5,6, No Mode Not Applicable Not Applicable (Shutdown) Neither 4160V ES bus is capable of being energized within 15 minutes MODES: 5,6, No Mode (defueled)
Loss of Vital DC Power Applicable Nfot tNot Applicable 4.6 MODES: 1,2,3,4 RfertoFissionProductBarrer Matrix MODES: 1,2,3,4 Standby Power Status Lights for BUS Al, A2, and BUS B1, B2 on the Main Control Board (SSF Panel) are out for 15 minutes or longer Loss of Vital DC Power 4.. M 5,6,.........Not Applicable Not Applicable Not Applicable (Shutdown) 4.7 MODES: 5,6, No Mode Standby Power Status Lights for BUS Al, MODES: 5,6, No Mode (defueled) A2, and BUS B1, B2 on the Main Control Board (SSF Panel) are out for 15 minutes or longer _____.______________________
EM-202 Rev. 70 Page 38 of 59
ENCL OSU RE 2 (Page 1 of 5)
Notification Form Florida Nuclear Plant Emergency
- 1. THIS IS CRYSTAL RIVER UNIT 3. A. C THIS IS A DRILL. B. C1 THIS IS AN ACTUAL EVENT. I HAVE A MESSAGE.
ENSURE: C STATE C CITRUS C LEVY C1 RAD. CONTROL-ORLANDO (M-F ONLY) ARE ON LINE.
-2. A. Time/Date contact made B. Reported by: (Name/Title)
C. Message Number D. Reported from: 13 Control Room F1 TSC 13 EOF
- 3. SETE A. Z CRYSTAL RIVER UNIT 3 B. [I ST LCIE UNIT I 0. TURKEY POINT UNIT3 C. [I ST LUCIE UNIT2 E, E TURKEY POINT UNIT 4
- 4. ACCIDFNT C.I ASSIFICATION A. 03 NOTIFICATION OF UNUSUAL EVENT C. D3 SITE AREA EMERGENCY B. 13 ALERT D. 13 GENERAL EMERGENCY
- 5. C[IRRFNT FMFRrFN-Y 1lFCI ARATION: TIME DATE
- 6. REASON FOR FMFRGFNCY DFCI ARATION:
- 7. Af'IlITIONAI INFORMATION OR IUPDlATF:
- 8. IN.IIIRIFS REQUIJIRING- OFFSITF SUPPORT: A. 1] No 13 Yes F3 Unk B. Contaminated: 1] No RI Yes 13 Unk
- 9. WFATI-HFR DlATA: A. Wind direction from degrees.
B. Downwind Sectors affected (minimum of 3): .. .. .
- 10. RFI EASF STATIIS: A. E3 No Release (Go to Item 12) C. 13 A Release occurred, but stopped B. 13 A Release is occurring
A. 13 Information not available at this time.
B. 13 Release within normal operating limits (Tech SpecslODCM)
C. 13 Non-Significant (Fraction of PAG Range, release is > normal limits and <PAG levels)
D. 1] PAG Range (Protective Actions required)
- 12. 11TI ITY RFCOMMENIDEDI PROTECTIVE ACTIONS A. 13 NONE B. 13 SHELTER ZONES/AREAS:
EVACUATE ZONES/AREAS:
OR C.C0 ILES NO-ACTION EVACUAT-EASECTORN SHE.ETER:SmCTeRS 0- 2 _ _ _ _-_ _ _ _ _ _
5~-10 I13. HAS EVENT BFFN TFRMINAT~Fn?: A.13 NO B. 13 YES: Time _____Date
- 14. SIIPPI EIFMINTAI FORM IS ATTAr.HFr": A. 13 NO B. 13 YES
- 15. MISSArI RFrIIVF:I RY: Name Time Date THIS IS CRYSTAL RIVER UNIT 3. EC THIS IS A DRILL. Cl THIS IS AN ACTUAL EVENT. END OF MESSAGE.
EC/EOF DIRECTOR INITIALS:
EM-202 Rev. 70 Page 39 of 59
ENCLOSURE 2 Supplemental Data Sheet (Page 2 of 5)
The following supplemental data is completed by the TSC or EOF for an Alert or higher emergency declaration.
Supplement to Message Number PLANT CONDITIONS INFORMATION CRITICAL SAFETY FUNCTIONS:
A. REACTOR SHUTDOWN? YES El NO B. CORE ADEQUATELY COOLED? YES El NO C. ADEQUATE EMERGENCY POWER AVAILABLE (DIESELS OR OFFSITE SOURCE) YES El NO FISSION PRODUCT BARRIER STATUS: (Check one condition for each barrier)
BARRIER I/ INTACT / CHALLENGED 1( LOST 1( REGAINED FUEL No indication of clad damage Clad is intact but losing Clad has failed, Cooling restored, no CLADDING subcooling, water level, indicated by high further degradation etc. temps., high expected containment rad, etc.
PRI. REACTOR Leakage is within normal Leakage is within safety Leakage exceeds Leakage reduced to COOLANT charging or makeup pump injection capacity safety injection within injection SYSTEM capacity capacity capacity
__(system repaired)
CONTAINMENT No evidence of containment No leakage but Evidence of Repair efforts have leakage or tube rupture containment pressure is containment isolated leak or release is only through at or above safety system leakage containment condenser actuation points (known release pressure has (30 PSIG) path or radiation reduced to stop
_surveys) leakage COMPLETED BY: TIME: DATE:
RADIOLOGICAL DOSE ASSESSMENT DATA
- 1. RELEASE STATUS: A. E] No Release (no further data required) C. [] A Release occurred, but stopped B. [] A Release is occurring
- 2. RELEASE RATE:
A. [] NOBLE GASES: Curies per second M] Measured [] Default B. [ IODINES: Curies per second [] Measured R Default
- 3. TYPE OF RELEASE:
A. RI AIRBORNE Time/Date Started:
B.[ LIQUID TimelDate Started:
Time /Date Stopped: Time/Date Stopped:
- 4. PROJECTED OFFSITE DOSE RATE:
DISTANCE THYROID DOSE RATE (CDE) TOTAL DOSE RATE (TEDE)
I Mile (Site Boundary) A. mrem/hr B. mrem/hr 2 Miles C. mremlhr D. mrem/hr 5 Miles E. mrem/hr F. mremlhr 10 Miles G. mrem/hr H. mrem/hr
- 5. WEATHER DATA (used for the above data):
A. Wind Direction from degrees.
B. Wind Speed MPH (2.24 X metersisec.)
A Stability Class _ (Sigma Theta or Wind Range; See page 3 of 5)
COMPLETED BY: TIME: DATE:
EM-202 Rev. 70 Page 40 of 59
ENCLOSURE 2 (Page 3 of 5)
State of Florida Notification Protocol
[NOCS 96024]
Within 15 minutes of declaration of emergency classification, NOTIFY State Warning Point Tallahassee. (This also notifies Citrus and
'.evy counties and the Department of Health, Bureau of Radiation Control (DHBRC)-Orlando. If information is NOT available, do NOT elay notification to State Warning Point Tallahassee.
Using one of the following communications networks listed by priority:
- STATE Hot Ringdown (SHRD) - Station 120 or 121
- Commercial Telephone System 850-413-9911 or 1-800-320-0519 or 1-850-413-9900
- Florida Emergency Satellite Communication System - (ESATCOM)
- Local Government Radio (LGR) via Citrus County
- Portable Satellite Phone (Located in TSC cabinet)
If the Commercial Telephone is used for notification, a separate notification to Citrus County (746-2555) and Levy County (1-352-486 5212 or 1-352-486-5111 after hours) is required.
When making the initial notification of an emergency condition to SWPT, report the current emergency classification declared at the time the notification is made. If before initial notification or since the previous notification conditions were met (even briefly) for a higher classification, explain in Additional Information or Update section.
INITIAL NOTIFICATION Once communications are established with the SWPT Duty Officer and the station roll call is complete, READ the message in its entirety and REPEAT information and answer questions as requested. After the notification is completed, FAX the State Form by using Group 1 from the Fax machine.
SECTORS AFFECTED i.DEGREES , SECTORS DEGREES I SECTORS DEGREES SECTORS 349-11 (349-371) HJ K 102-123 (462-483) NPQ 214-236 BCD 12-33 (372-393) JKL 124-146 (484-506) P QR 237-258 CDE 34-56 (394-416) KL M 147-168 (507-528) Q RA 259-281 DEF 57-78 (417-438) LM N 169-191 (529-540) RAB 282-303 EF G 79-101 (439-461) MNP 192-213 A BC 304-326 FG H
-___327-348 GH J STABILITY CLASS SIGMA THETA (deg) WIND RANGE (deg) -DELTA T (deg) STABI"ILITY CLASS
> 22.5 > 135 _<
-1.46 A (most dispersed plume)
<22.5 to 17.5 134 to 105 -1.45 to -1.31 B
<17.5 to 12.5 104 to 75 -1.30 to -1.16 C
<12.5 to 7.5 74 to 45 -1.15 to -0.39 D
< 7.5 to 3.8 44 to 23 -0.38to1.15 E
<3.8 to 2.1 22 to 12 1.16 to 3.07 F
<2.1 <12 >_3.08 G UPDATE NOTIFICATION 0 Update SWPT every sixty minutes after initial notification and upgrades of emergency classification.
- The use of the FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM is required for:
- Initial notification that an emergency condition exists (Item 4)
- Any change in emergency classification (Item 4)
- Any change in Protective Action Recommendations (Item 12)
- Termination of an emergency classification (Item 13)
- Other updated information NOT meeting the above criteria does NOT require the use of the FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM.
. The sixty minute update notification is still required with a statement there is NO change from last update, unless the SWPT agrees to less frequent updates.
EM-202 Rev. 70 Page 41 of 59
ENCLOSURE 2 (Page 4 of 5)
Guidance for Completing the Florida Nuclear Plant Emergency Notification Form
- 1. Check appropriate box based on a drill or actual event. Ensure offsite agencies are on-line. If NOT, separate notifications to Citrus and Levy County are required.
- 2. A. Enter the time contact is made with the State Warning Point or Risk County. This time must be within 15 minutes of the "Current Emergency Declaration" time (Item 5) or within 60 minutes of the previous notification if used for an update.
B. Enter name and title of person making the notification.
C. Enter message number (beginning with #1 and following through sequentially in the TSC and EOF).
D. Enter location from which the notification is made.
- 3. Check Crystal River Unit 3 if NOT already checked and report to off-site agencies during notification.
- 4. Check the classification corresponding to current plant conditions. If, before the initial notification or since the previous notification, conditions were met (even briefly) for a higher classification, ensure that classification and condition is noted in Item 7, "Additional Information or Update."
- 5. Enter the emergency declaration time and date for the current accident classification.
- 6. Enter wording to indicate the Emergency Action Level description or the status of the Fission Product Barriers (loss or potential loss) used to declare the event (e.g., Loss of Reactor Coolant System Barrier, Potential Loss of Fuel Clad Barrier, etc.). This information should remain the same throughout update messages unless there is a classification change. Do NOT use acronyms or abbreviations.
- 7. Enter additional significant events here, including if conditions briefly existed for a higher emergency classification but NO longer exist, or conditions that would have independently warranted declaration of an equal or lower classification (e.g., a fire within the Protected Area during a SITE AREA or GENERAL EMERGENCY). Do NOT use acronyms or abbreviations.
- 8. Item "A"; Check "YES" only if there are injuries or illnesses that require off-site support (EMS, hospital). Check "Unk" ifthe extent of the injuries is unknown at this time or if it is NOT yet known if offsite treatment is necessary. Check "Unk" in item "B" if the nature of the injuries has prevented thorough monitoring onsite or ifthere is any doubt whether contamination is present.
- 9. Enter the wind direction in degrees in Item "A"and the three downwind sectors in Item "B." The downwind sectors confirm wind direction because of potential confusion with degrees "from" versus degrees "to."
- 10. Check Item "A" ifthere are NO indications of a release, then go to Item 12. Check Item "B" if a release is occurring, even though it may be less than normal operating limits. Check Item "C" if a release has occurred but stopped. Specific dose information will be supplied on the supplemental data sheet after the TSC is declared operational at an ALERT or higher.
RELEASE: (Refer to "Release (Florida Nuclear Plant Emergency Notification Form)" definition.)
- 11. Check Item "A" if Release Significance Category (See page 5 of 5) information is NOT available at the time of notification and follow-up as soon as possible with information. Check Item "B" if the current release is or the previous release was within normal operating limits (ITS/ODCM). Releases monitored by RM-A1 or RM-A2 are within normal operating limits if the low range gas channel is below its high alarm setpoint. Check Item "C" if the current release is or the previous release was greater than normal operating limits, but less than EPA PAG values. This involves any radiological release that may occur when there is NO fuel damage. Check Item "D" if the fuel clad barrier has been lost and there is any indication of a release (effluent monitors, surveys, etc.). A General Emergency and PARs would be automatically required. This terminology should be easily understood by decision-makers at all levels within the utility and at the State and local levels.
- 12. Check Item "A" if NO Protective Actions are necessary. Check Item "B" if PARs are necessary and enter Zone designation.
(Item "C" is used by--FTher Florida nuclear sites.)
- 13. Enter the time the event was terminated or when the transition from the "Emergency Phase" to the "Recovery Phase" has taken place.
- 14. Check "No" unless a Supplemental Form is completed for this particular message. If a Supplemental Form is attached, the Form is to be read as part of the emergency notification from the TSC or EOF and faxed.
.1 i5. Enter the name of the SWPT Duty Officer or the individual that receives the notification. Enter time and date call is completed or when Form is provided to Deputy State Coordinating Officer at the EOF.
Supplemental Page - Complete at the TSC or EOF at an Alert Classification or higher and provide to State & Counties with Page 1.
EM-202 Rev. 70 Page 42 of 59
ENCLOSURE 2 (Page 5 of 5)
Release Significance Categories CORE RELEASE RELEASE CONDITION STATUS SIGIFICANCE
__________ __________ CATEGORY No Core Damage No release NR (or clad challenged) Release in progress <NOL, NS No release NR Clad Failure Lost Release in progress PAG No release NR Core Melt EHE (PAG* Florida Release in progress Nuclear Plant Emergency Notification Form)
NR: NO RELEASE This category indicates NO release is occurring. This category is appropriate regardless of core status, if there are NO indications of a release (e.g., unexplained containment pressure decrease, unexplained abnormal radiation levels in Auxiliary Building or Intermediate Building, on the berm, or in the field). Do NOT assume Design Basis Leakage is
)ccurring if it has NOT been detected. If a release occurred but has now stopped, maintain the appropriate category S-below until EPZ doses have dissipated.
<NOL: RELEASE WITHIN NORMAL OPERATING LIMITS (ITS/ODCM)
This category indicates releases that are monitored by RM-A1 or RM-A2, occurring when the fuel is undamaged. These releases are within normal operating limits if the low-range gas channel is below its high alarm setpoint. Do NOT make this selection for releases NOT monitored by RM-A1 or RM-A2 unless they have been evaluated per the ODCM.
NS: NON-SIGNIFICANT (FRACTION OF PROTECTIVE ACTION GUIDELINE VALUES)
This category indicates releases that are occurring when the fuel is undamaged. It includes releases exceeding RM-A1 or RM-A2 high alarm setpoint (e.g., LOCA, Waste Gas System failures). It also includes releases NOT monitored by RM-A1 or RM-A2 (e.g., Steam Generator Tube Rupture with safeties lifting). These releases will NOT produce site boundary doses that approach the EPA Protective Action Guideline values of 1 REM TEDE and/or 5 REM thyroid. NO Protective Action Recommendations are necessary.
PAG: AT OR NEAR PROTECTIVE ACTION GUIDELINE VALUES This category indicates releases that are occurring after the fuel clad barrier has been lost. It includes damage to irradiated fuel stored in the fuel pools. Site Boundary doses greater than the EPA Protective Action Guideline of 1 REM TEDE and/or 5 REM thyroid are possible. The category is appropriate with fuel cladding failure even if only minor offsite doses are detected.
A General Emergency would be required and evacuation of at least 5 miles, 360 degrees (Zone 1) should be recommended.
Shelter or evacuation beyond 5 miles should be determined based on plant status and dose projections.
EHE: EARLY HEALTH EFFECTS (NOT on Florida Nuclear Plant Emerqency Notification Form, see NOTE below)
This category indicates releases that are occurring after severe core damage has taken place and where containment has failed early in the event. Doses of 25 REM TEDE and/or 2500 RADS thyroid could cause early health effects and these doses are easily possible within three miles from the plant. Evacuation of the Energy Complex should be performed and evacuation
)f the 10-mile EPZ (Zones 1,2,3) should be recommended (never sheltering) even if evacuees are exposed to the plume.
- NOTE:This category is NOT listed on the Florida Nuclear Plant Emergency Notification Form because the State implements protective actions at the PAG range above. However, it will be posted on status boards in the TSC and EOF.
EM-202 Rev. 70 Page 43 of 59
ENCLOSURE 3 (Page 1 of 4)
Considerations for a Security Emergency During a Security Emergency, keep this question in mind. Would the nature of the event cause plant personnel to be at greater risk if normal emergency response actions are taken (e.g., local assembly, staffing the TSC or EOF, evacuation)?
IF Security is NOT aware of the potential Security Emergency, THEN NOTIFY the Security Shift Supervisor immediately.
Maintain contact between the Control Room and the Security Shift Supervisor.
Do NOT delay offsite notifications beyond the required time while implementing this enclosure.
A Security Threat or event presents unique challenges to protect the health a safety of the public and employees. Normal emergency response procedure steps may be hindered due to events that are occurring. The following considerations are intended to aid in decision-making during each type of Security Emergency (REFER TO appropriate Security condition).
I. In-Progress Intruder(s) Threat (corresponds to an Alert or higher emergency classificationi Security announces the Security Emergency directing personnel to take suitable cover immediately until an "All Clear" announcement is made. Additionally, Security may initiate a PA announcement directed toward the intruders.
- Retain personnel in the Control Room and await instructions from Security.
- Do NOT sound the evacuation alarm.
- Do NOT staff the TSC/OSC. Maintain EC duties in the Control Room until Security determines it is safe to staff the TSC/OSC.
- Do NOT instruct personnel to go to their Local or Main Assembly Areas.
"* For Alerts, consider making telephone notifications to staff the minimum EOF positions if this can be done using personnel already offsite.
"* EOF activation: Do NOT use emergency pagers as it may reveal the location of plant personnel to the intruder(s). Make telephone notifications to staff at least the minimum EOF positions if this can be done using personnel already offsite.
"* If the EOF is ready to become operational and the TSC is NOT staffed, perform a turnover with the EOF Director.
EM-202 Rev. 70 Page 44 of 59
ENCLOSURE 3 (Page 2 of 4)
Considerations for a Security Emergency II. Confirmed Insider Threat involving a badged employee (corresponds to an Unusual Event emergency classification or higher)
Following a CREDIBLE NOTIFICATION of a confirmed insider threat, the Superintendent Shift Operations/Emergency Coordinator (SSO/EC) takes the following actions:
- 1. The SSO/EC should direct all personnel to place equipment in a safe condition, exit all vital areas and return to their shop or normal work locations. This direction may be given by using plant public address or by contacting discipline supervisors.
Supervisors should be directed to report by telephone to the Control Room when all personnel are accounted for.
- 2. The Security Shift Supervisor should be directed to verify that all vital areas are evacuated using the security computer system.
NOTE: The two-person rule is two individuals remaining in line-of-sight of each other while in plant vital areas. The individuals must remain in continuous visual contact unless personnel or plant safety will be adversely impacted.
- 3. Direct Nuclear Security to perform sweeps employing the two-person rule and verify that NO personnel are in any vital area. Security computer system monitoring of vital area access and two-person vital area patrols should be performed continuously.
- 4. Then SSO/EC should direct that all personnel only perform work approved by the Site Vice President, PGM, or SSO/EC in vital areas employing the two-person rule (Note 2).
EM-202 Rev. 70 Page 45 of 59
ENCLOSURE 3 (Page 3 of 4)
Considerations for a Security Emergency I1l. Credible Imminent Threat against the CR-3 Nuclear Plant (corresponds with an Unusual Event classification)
Plant Emergency Response Considerations NOTE: Other EALs (Fire, AirplaneNehicle Crash) may become appropriate based upon the results of the threat.
- 1. Declare Unusual Event (EAL 2.18). If necessary, implement the EC judgment EAL to escalate site/local response.
NOTE: A pager message is established that will allow Security to alert TSC staff to report to the EOF instead of the TSC. The SSO/ Security Shift Supervisor shall determine the location for TSC staffing.
- 2. If the event has the potential to escalate to a higher emergency classification, consider performing local assembly and staffing the TSC and/or EOF now. Consider alternate location for TSC staffing (EOF) depending upon the nature of the threat. Use emergency pagers with caution. Ensure emergency responders are NOT endangered while reporting to the TSC. Consider having Security notify emergency responders by telephone.
- 3. Determine protective actions for station personnel.
A. Coordinate with the Security Shift Supervisor to determine the best alternative based upon the extent of the threat to the site (localized area versus larger scale area), the time frame to the threat (i.e., is there enough time to allow the staff to evacuate down the berm before the threat or would sending people onto the berm potentially expose them to a threat), and the nature of the threat (should staff be moving around the site). Considerations should include sheltering and/or evacuation.
Consider alternate evacuation paths depending upon areas threatened.
B. Consider appropriate location for building operators. SCBAs / cylinders are staged in the Control Room area in the event building operators are brought into the Control Complex. Other personnel in the Control Complex should be minimized, as there will be a limited supply of SCBA cylinders. It may be appropriate to send them outside the Protected Area depending upon the nature/timing of the threat.
- 4. Muster the Fire Brigade. Consider the location to muster depending on the nature of the threat. It may be prudent to muster them outside the Protected Area until after the event occurs.
EM-202 Rev. 70 Page 46 of 59
ENCLOSURE 3 (Page 4 of 4)
Considerations for a Security Emergency Plant Operations Considerations:
- 1. Place the Control Complex on emergency recirculation. This will minimize smoke migration into the Control Complex from a potential fire situation. Consider securing of other building supply fans to minimize smoke migration into plant.
- 2. Consider tripping the reactor and taking action per EOP-02 (If time permits, PGM concurrence is required for tripping the reactor):
- a. If the Main Control Room is NOT under operator control, take actions to trip the plant outside of the Main Control Room.
- b. If the berm areas are threatened, EOP-02 actions for the Turbine/Auxiliary Buildings should be evaluated to NOT be performed to prevent exposing the building operators to a threat. Consider use of Security personnel as escorts for Operators in the field if needed.
- 3. Perform Actions of EOP-14, Enclosure 2. This will complete key actions in the Auxiliary Building early in the event the Auxiliary Building becomes inaccessible later.
- 4. Begin a plant cooldown at the maximum rate allowed by the governing procedure. Use OP-209 or EOPs as appropriate depending on the plant situation. Depending upon the timing of the threat, it may be necessary to commence plant cooldown before completing all steps of EOP-10.
- 5. If the Main Control Room is NOT under control of the operators, take action to transfer control to the remote shutdown panel. Control the plant per AP-990. If both the Main Control Room and the remote shutdown panel room are NOT accessible or under control of the operators, consider taking action to locally initiate emergency safeguards equipment.
- 6. Maximize availability of emergency safeguards systems, fire service, and makeup water sources. Again, consider the nature/location of the threat before dispatching staff into the field.
- a. Secure/restore from surveillances in progress.
- b. Top off tanks. Align alternate sources.
- c. If possible, ensure makeup is aligned to the fire service storage tanks in the event the threat causes a large fire and need for extended fire service use.
- 7. If the plant is shutdown, establish Reactor Building containment if possible.
- 9. Consider starting the Fire Service Pumps.
It is expected that equipment will start and load as required unless damaged by an event. As such, additional actions will NOT be specified to be considered to prevent exposing the operators to potentially threatened areas as well as to minimize Main Control Room actions.
EM-202 Rev. 70 Page 47 of 59
ENCLOSURE 4 (Paqe 1 of 2)
NRC FORM 361 REACTOR PLANT EVENT NOTIFICATION WORKSHEET NRC COMMUNICATOR EN #
- ... 1.101' ,4;.., Ic M0 I IT CeD1Ifa ,, ' 1<sn1.eIe.1nn ,,, 1enn.AAeJSCOA iAinn ,, ijni.Ai
- 1) Use EN hnescernmerw1 re-UII U
,ttC use~fJV IJ omer aJIL - - - -- -- I NOTIFICATION TIME FACILITY UNIT CALLER'S NAME CALL BACK:
CRYSTAL RIVER 3 ENS # 700-821-0027 Or # 1-352-795-6958 TIME& ZONE EVENT DATE , POWER I MODE BEFORE POWER / MODE AFTER TMOURCLASSIFICATIONS EVENT 1 NON-EMERGENCY 50.72 (b)(1) El v)(A) Safe S/D Capability El GENERAL EMERGENCY El TS Deviation El (v)(B) RHR Capability El SITE AREA EMERGENCY 4-HOUR NON-EMERGENCY 50.72 (b)(2) *E (v)(C) Control of Radiological Release El ALERT C3 (i) TS Required S/D E] (v)(D) Accident Mitigation
[] UNUSUAL EVENT C] (iv)(A) ECCS Discharge to RCS C] (xii) Offsite Medical El 50.72 NON-EMERGENCY (see next column) El (iv)(B) RPS Actuation E] (xiii) Loss Comm/AsmtlResp
[: PHYSICAL SECURITY (73.71) E (xi) Offsite Notification 60-DAY OPTIONAL 50.73 (a)(1)
El MATERIAUEXPOSURE (20.2202) -HOUR NON-EMERGENCY 50.72(b)(3) El Invalid Specified System Actuation E] FITNESS FOR DUTY E] (ii)(A) Degraded Condition Other Unspecified Requirement (Identify .
ElOTHER UNSPECIFIED REQMT (see last column) C] (ii)(B) Unanalyzed Condition 0l El INFORMATION ONLY El Specified System Actuation 1l DESCRIPTION Include: Systems affected, actuations &their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on Back)
- NOTI*ICA*TIONS9 YES N WBE ANYTHING UNUSUAL OR NOT UNDERSTOOD? El YES (Explain above) E] NO NRC RESIDENT STATE WARNING DID ALL SYSTEMS FUNCTION AS REQUIRED? E YES El NO (Explain above)
POINT CITRUS/LEVY COUNTIES OTHER GOVT AGENCIES MODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE UNTIL CORRECTED: RESTART DATE: [I YES O NO 11 _____I________
1 1_____
EM-202 Rev. 70 Page 48 of 59
ENCLOSURE 4 ADDITIONAL INFORMATION (Page 2 of 2)
NOTIFICATION TIME RADIOLOGICALRELEASES Check or Fill inApplicable Items (specific detailslexplanations should be covered in event description .
Q LIQUID RELEASE El GASEOUS RELEASE C] UNPLANNED RELEASE C] PLANNED RELEASE [] ONGOING Q] TERMINATED rI MONITORED C] UNMONITORED 0- OFFSITE RELEASE [] TS EXCEEDED El RM ALARMS [I AREAS EVACUATED O PERSONNEL EXPOSED OR CONTAMINATED [] OFFSITE PROTECTIVE ACTIONS RECOMMENDED
- State release path in descdption "ReleaseRates/Limits Release Rate. % 0.CM Limit Total Activity % 00CM Limit (From Dose Assessment Team) (CiIsec) (CI)
Noble Gas Iodine Particulate Liquid (excluding tritium & dissolved noble gases)
Liquid (tritium)
Total Activity iRAD MONITOR Plant Stack Condenser/ArEetr Main Steam Line .Othier (List) i~~READINGS (RMA-2) (RMA-12) (RMG-25,26,27,28)
RAD MONITOR READINGS:
ALARM SETPOINTS:
% ODCM LIMIT (IF APPLICABLE)
RCS OR SG TUBE LEAKS CHECK OR FILL INAPPLICABLE ITEMS: (SPECIFIC DETAILSIEXPLANA TIONS SHOULD BE CO VERED IN EVENT DESCRIP TION)
"LOCATION OF THE LEAK (E.G., SG#, VALVE, PIPE, ETC.)
LEAK RATE: UNITS: GPM/GPD T.S. Limits: E] Sudden or El Long Term Development LEAK START DATE: TIME: COOLANT ACTIVITY: PRIMARY ____._CI/ML SECONDARY __ pCI/ML LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL:
EVENT DESCRIPTION (Continuedfrom front)
"i" EC INITIALS DATE:
EM-202 Rev. 70 Page 49 of 59
ENCLOSURE 5 Emergency Notification Units 1/ 2 & 4/5 Use Enclosure 7 to determine Protective Action Recommendations for Energy Complex personnel.
(NONE for Unusual Event or Alert)
Unit 1/2 (extension 2120 or 563-4454) Contact Time Unit 4/5 (extension 5283 or 563-4460) Contact Time GIVE THE FOLLOWING INFORMATION TO THE FOSSIL UNITS:
- 1. Your name and position:
- 2. Emergency or drill:
- 3. Current Emergency Classification:
- 4. Briefly explain plant conditions using basic facts:
- 5. STATE if conditions are:
- a. "IMPROVING"
- b. "STABLE"
- c. "DEGRADING"
- 6. STATE (a) or (b) or (c):
(a) "NO RADIOACTIVE MATERIAL HAS BEEN RELEASED."
(b) "RADIOACTIVE MATERIAL IS BEING RELEASED AT LOW LEVELS (when NO fuel damage)."
(c) "RADIOACTIVE MATERIAL IS BEING RELEASED."
- 7. STATE (a) or (b) or (c) or (d):
- b. (SITE AREA EMERGENCY; see Enclosure 7) "BEGIN STANDARD ASSEMBLY AND ACCOUNTABILITY. REFER TO THE CRYSTAL RIVER COAL PLANT SITE ACCOUNTABILITY/EVACUATION MANUAL. ONCE ACCOUNTABILITY IS COMPLETE, NOTIFY CR-3 SECURITY AT EXTENSION 3258 OR 795-5078, AND STANDBY FOR FURTHER INSTRUCTIONS."
- c. (General Emergency, NO release and release NOT likely within 3 hrs; see Enclosure 7)
"BEGIN STANDARD ASSEMBLY AND ACCOUNTABILITY. REFER TO THE CRYSTAL RIVER COAL PLANT SITE ACCOUNTABILITY/EVACUATION MANUAL. ONCE ACCOUNTABILITY IS COMPLETE, NOTIFY CR-3 SECURITY AT EXTENSION 3258 OR 795-5078, AND EVACUATE NON-ESSENTIAL PERSONNEL. STANDBY FOR FURTHER INSTRUCTION."
- d. (General Emergency, release has occurred or is likely to occur within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />; see Enclosure 7) "SECURE THE PLANT AND EVACUATE. DO NOT PERFORM ASSEMBLY."
- 8. If time permits and you feel qualified, ask for questions.
- 9. STATE: "WE WILL KEEP YOU INFORMED."
EM-202 Rev. 70 Page 50 of 59
ENCLOSURE6 Initiation of the Emergency Response Data.System (ERDS)
[NOCS 40730]
Within the first hour of the declaration of an Alert, Site Area Emergency or General Emergency classification ACTIVATE ERDS. Once activated, ERDS operates automatically.
ERDS is located in the Control Room in the Cabinet labeled:
"Computer Main Frame, Cab. #5" ACTIVATION OF ERDS - Open the cabinet and perform the following:
- 1) DEPRESS button "B" on the COMMANDER for ERDS initiation. Make sure the red light comes on.
- 2) ALT-TAB to ERDS Display.
- 3) DEPRESS ALT-C on the keyboard.
The ERDS window will display a series of messages such as "Waiting for Connect" and
. "Waiting for Accept." Once the connection with the NRC is established, the messages will alternate between "Transmitting" and "Idle." If NO activation response is indicated on the monitor, contact the NIT Project Business Analyst for assistance, and NOTIFY the NRC over the ENS link, providing parameters as requested. If the link is inadvertently terminated once communications are established, ERDS automatically continues trying to reestablish communications.
DEACTIVATION OF ERDS NOTIFY the NRC before disconnecting the ERDS data link. Once concurrence is given by the NRC, ERDS transmission is terminated. If one of the above mentioned message is NOT on the monitor, it means that ERDS is NOT activated. Proceed with the following only if ERDS is still activated. The NRC also has the capability of terminating the ERDS transmission if needed.
- 1) DEPRESS button "B" on the COMMANDER for ERDS deactivation.
- 2) ALT-TAB to ERDS Display
- 3) DEPRESS ALT-C on the keyboard.
A series of messages will appear in the ERDS window. When the shut down is "finished, the message "Shutdown Completed" is displayed.
EM-202 Rev. 70 Page 51 of 59
ENCLOSURE 7 (Page 1 of 4)
Evacuation Planning Guide Energy Complex Protective Actions
- 1. DETERMINE protective actions for the Energy Complex using B or C or D below. (Use information in the tables and map on the following pages of this enclosure as necessary.)
A. UNUSUAL EVENT OR ALERT: NO PROTECTIVE ACTIONS B. SITE AREA EMERGENCY:
PERFORM assembly and accountability and INSTRUCT Fossil Control Rooms to report results to CR-3 Security at extension 3258 or 795-5078.
CONSIDER sheltering for releases lasting less than two hours.
For releases lasting greater than two hours or for planned releases, EVACUATE non-essential personnel.
C. GENERAL EMERGENCY:
(Release has NOT occurred and release NOT likely within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.)
- PERFORM assembly and accountability and INSTRUCT Fossil Control Rooms to report results to CR-3 Security at extension 3258 or 795-5078.
- EVACUATE non-essential personnel (including Main Assembly Area personnel).
- NOTIFY Fossil Control Rooms to standby for instructions.
- CONSIDER supplying dosimetry to remaining personnel.
D. GENERAL EMERGENCY:
(Release has occurred or is likely to occur within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.)
NOTIFY Fossil Control Rooms to secure their plants.
EVACUATE the Energy Complex even if a release has already started (including Main Assembly Area personnel).
EVACUATE without performing assembly.
- 2. NOTIFY Units 1/2 & 4/5 using Enclosure 5, per the EC Guide.
- 3. ENSURE Nuclear Security coordinates with Corporate Security to ensure these protective action instructions are provided to all areas of the Energy Complex, per the EC Guide.
Evacuation Considerations:
- Approximately 35 minutes for notification, equipment shutdown, assembly and accountability.
- Approximately 125 minutes to evacuate site using Access Road.*
- Approximately 160 minutes to evacuate site during adverse weather.*
- Consider a suitable evacuation route from the site.
- Early evacuation may be required under certain meteorological or radiological conditions.
- Based on 1344 vehicles on-site (approximately 700 - 1000 vehicles on the Energy Complex during normal operations).
EM-202 Rev. 70 Page 52 of 59
ENCLOSURE 7 (Page 2 of 4)
Evacuation Planning Guide Wind Direction Data N 349-11 (349-371) HJK NNE 12-33 (372-393) J KL NE 34-56 (394-416) KLM ENE 57-78 (417-438) LMN E 79-101 (439-461) MN P ESE 102-123 (462-483) N P Q SE 124-146 (484-506) P Q R SSE 147-168 (507-528) Q RA S 169-191 (529-540) RAB SSW 192-213 ABC SW 214-236 B CD WSW 237-258 CDE W 259-281 DE F WNW 282-303 EF G NW .304-326 F G H NNW 327-348 G HJ EM-202 Rev. 70 Page 53 of 59
ENCLOSURE 7 (Page 3 of 4)
Evacuation Planning Guide (Continued)
Contacts for Personnel Assembly A Units 4 & 5 Units 4 & 5 Control Room B/C Nuclear Administration Building Public Address System B/C North Coal Yard Units 4 & 5 Control Room D/ E CR-3 Warehouse Area Corporate Security Site Administration Building Specialist D/E Mariculture Center Corporate Security Specialist E /F/ G/ H Coal Train Yard Units 4 & 5 Control Room J/K/L South Coal Yard Units 1 & 2 Control Room N Units 1 & 2 Units 1 & 2 Control Room N Ralston Purina Building Corporate Security Specialist EM-202 Rev. 70 Page 54 of 59
C ENLOSURE 7 (Page 4 of 4),
EM-202 Rev. 70 Page 55 of 59
ENCLOSURE 8 (Page 1 of 2)
Guidelines for Protective Action Recommendations for Non-Essential Energy Complex Personnel and General Population
[NOCS 1128, 1592]
RECOMMENDED ACTION PLANT CONDITIONSIOFF-SITE DOSE ESTIMATES 0-5 MILES 5-10 MILES
- 1. CONDITION:
GENERAL EMERGENCY DECLARED.
NO APPARENT CORE DAMAGE.
CORE DAMAGE INDICATIONS:
- a. RCS pressure vs temperature in Region 1 or 2 Evacuate Zone 1 None (Refer to EOP-07); or (See Note 2.) (See Note 1.)
- b. RM-G29/30 reading < 100 Rlhr; or
- c. PASS results.
- 2. CONDITION:
GENERAL EMERGENCY DECLARED.
CLAD DAMAGE/GAS GAP RELEASE (NO CORE MELT).
CORE DAMAGE INDICATIONS:
- a. RCS pressure vs temperature in Region 3 Evacuate Zone 1 Shelter Zones 2 & 3 (Refer to EOP-07); or (See Note 2.) (See Note 1.)
- b. Core uncovered for 15-30 minutes; or
- d. PASS results.
OR:
- Dose at the 0.83 mile Site Boundary is projected to be:
a) TEDE: > 1.0 Rem b) Thyroid CDE: > 5.0 Rem
- 3. CONDITION:
GENERAL EMERGENCY DECLARED.
CORE MELT OCCURRING OR LIKELY.
CORE DAMAGE INDICATIONS:
- b. Core uncovered for > 30 minutes; or
WITH:
Evacuate Zone 1 Shelter Zones 2 & 3 NO projected containment failure and NO release underway. (See Note 2.) (See Note 1.)
Evacuate Zone 1 Evacuate Zones 2 & 3 E eNote2 (See Note 2.)
Projected containment failure and/or release underway. (See Note 2.) (See Note 2.)
(See Note 3.)
PARs within the first hour of an event should be based on PLANT CONDITIONS ONLY until the Dose Assessment Team is operational.
NOTE 1: Relocate/evacuate population affected by ground contamination after plume passage or at any time projected dose from actual release is > 1.0 REM TEDE or
NOTE 2: Evacuation time estimates are 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for a Zone 1 evacuation and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for Zones 2 & 3 evacuation. (These times do NOT include notification or preparation time for evacuees.)
NOTE 3: IF projected dose from an actual release is >1.0 REM TEDE or 5.0 REM Thyroid beyond 10 miles, THEN RECOMMEND evacuation to State and Local government by distance in miles, OR by subdivision and geographic boundaries.
ZONE DESCRIPTIONS Zone 1: 0-5 miles 360 degrees and out to 10 miles in Gulf.
Zone 2: 5-10 miles in Citrus County.
. Zone 3: 5-10 miles in Levy County.
EM-202 Rev. 70 Page 56 of 59
ENCLOSURE 8 (Page 2 of 2)
Guidelines for FP Emergency Worker Exposure DOSE LIMIT CONDITION (REM TEDE) GUIDANCE
- 1. Emergency conditions 5 Emergency worker exposure should not requiring actions to not exceed 5 REM TEDE.
prevent serious injury or protect valuable property.
- 2. Emergency conditions 10 Exposure greater than 5 REM TEDE requiring actions to should receive approval of the prevent serious injury or Emergency Coordinator. Appropriate protect valuable property. controls for emergency workers include time limitations and respirators.
- 3. Emergency conditions 25 Exposure greater than 5 REM TEDE requiring lifesaving should receive approval of the actions or actions to Emergency Coordinator. Appropriate protect large populations. controls for emergency workers include time limitations, respirators, and thyroid blocking.
- 4. Emergency conditions > 25 Exposure greater than 5 REM TEDE requiring lifesaving receive approval of the Emergency actions or actions to Coordinator. Exposure at this level protect large populations. should be to volunteers who are healthy, above the age of 45, have an understanding of the health risks involved, and, preferably, be those whose normal duties have trained them for such missions. Appropriate controls for emergency workers include time limitations, respirators, and thyroid blocking.
NOTE: Reference for this table is Table 2.2 in the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400-R/92-001).
EM-202 Rev. 70 Page 57 of 59
Revision Summary Non-Intent Changes Throughout Change Florida Power Corporation and FPC to Florida Power and FP. NUPOST 104919 Enclosure 1 Re-aligned all logic terms of table to left margin for consistency.
Note of 3.0 Delete the SA exemption disclaimer as EPIPs are no longer exempted.
Change of Intent New definition 3.1.4 CREDIBLE SITE-SPECIFIC SECURITY THREAT NOTIFICATION as "A threat specifically to CR-3 confirmed and validated by Nuclear Security. Notification may be received from recognized law enforcement or governmental agencies (e.g., Federal Bureau of Investigation (FBI), Florida Department of Law Enforcement (FDLE), Division of Emergency Management (DEM, Nuclear Regulatory Commission (NRC).) and renumber subsequent definitions accordingly. AR 56490-59 Renumbered definition To add "An intruder also includes a badged employee (insider) acting in an 3.1.15 active or passive manner in support of an overt or covert attempt to commit sabotage. A passive manner means the insider may provide intelligence type information regarding Security or Operations Unit actions or responses to persons or organizations planning or attempting to commit sabotage. This intelligence type information may include but NOT be limited to Security Force deployment strategies or procedures or Operations Unit procedures in response to security contingency events. An active manner means the insider may provide support to persons or organizations planning or attempting to commit sabotage. This support may include but NOT be limited to disrupting Security Force responses to contingency events or disrupting Operations Unit actions or response involving reactor safety controls in response to contingency events."
Step 3.3.4 Add Security event to list of items where EC may delay staffing of the emergency response facilities to provide for safe actions for plant personnel.
The change is based on the above revisions.
Steps 4.1.9, 4.2.10, 4.3.11, Replace the word "immediately" to "as soon as practicable." Student feedback and 4.4.12 and NRC Resident Inspector concerns regarding recent Simulator E-Plan evolution. The NUREG addresses the application of the term immediate for purposes of NRC notification but the literal interpretation was creating human factoring concerns.
Step 4.1.6 Moved step from recommended within 15 minutes to recommended within 30 minutes for consistency with other EC guides.
EAL 2.18 Add 4 th condition as" OR 4. A CREDIBLE SITE-SPECIFIC SECURITY THREAT NOTIFICATION." This was previously approved by the NRC. AR 56490-59, NUPOST 104060 EM-202 Rev. 70 Page 58 of 59
Enclosure 2 Place an "X" in the box for item 3 and updated guidance. This is an accuracy item for EP PIs that can be checked to eliminate overlooking the item when completing the form. Added guidance to item 7 to not use abbreviations /
acronyms. Revised Item 11 guidance to delete "NO PARs are required at this level." Page 5, core conditions, add "(or clad challenged) to No Core Damage and "Lost" to Clad Failure to make consistent with EM-225 enclosure. NUPOST 104064 Enclosure 3 Replace Enclosure 3 to reflect revised considerations for a Security Emergency.
The enclosure now includes decision-making aids for each type of Security emergency including plant operational considerations. AR 56490-57 & 60, NUPOST 104348 Enclosure 5 Rearrange items 5 & 6 so plant status follows the brief explanation of plant conditions and change wording of item 6 to reflect significance of release to Fossil Control Room personnel.
EM-202 Rev. 70 Page 59 of 59