ML022560246
| ML022560246 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/06/2002 |
| From: | Florida Power Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EM-202 | |
| Download: ML022560246 (64) | |
Text
To Facility Address From Address City Country Email Contact Date/Time Trans No.
Total Items:
NRC NRC CR3 Department :
CR3-01242 / MAIL CODE: N/A DC DESK CR3DOCSVCS Attention: DOCUMENT SERVICES -
SA2A FLORIDA POWER CORPORATION CRYSTAL RIVER COMPLEX 15760 WEST POWERLINE STREET CRYSTAL RIVER State:FL Postal Code: 34428-6708 UNITED STATES 09/06/02 09:06 Transmittal Group Id:0000004840 000078502
Title:
00001 Wpc~o2 Item Facility Type Sub Document Number Sheet Doc Status Revision Doc Date Copy #
Media Copies 0001 CR3 POM EMG EM0202 ACTIVE 071 H
01 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).
Signature:
PASSPORT DOCUMENT TRANSMITTAL Page:
1 1111IlM IIMlil t
lll 1Hlll Date:
z::;-
K..
R RForida Power a
Pwer Reference A ProgressEnergy Com...M U se "FLORIDA POWER CRYSTAL RIVER UNIT 3 '
PLANT OPERATING MANUAL EMERGENCY PLAN IMPLEMENTING PROCEDURE EM-202 DUTIES OF THE EMERGENCY COORDINATOR Page 1 of 63 Rev. 71 L
EM-202
SECTION 1.0 PAGE PURPOSE.....................V....................
4..............................
4 111-ý Page 2 of 63 EM-202 Rev. 71 TABLE OF CONTENTS
2.0 REFERENCES
..... 1................................................................................ 4 3.0 -
PERSONNEL INDOCTRINATION............................................. 5 3.1 DEFINITIONS...............................................................................................................
5 3.1.1 Bomb........................................................................................................
5 3.1.2-Civil Disturbance...................................................................................
5 3.1.3 Committed 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.............................................
I......................................................... 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 Intrusion/intruder.........................................................................................
6 3.1.16 Local Assembly Area.............................................................................
6 3.1.17 Main Assembly Area..................................................................................
6 3.1.18 Protected Area.........................................................................................
6 3.1.19
'Protective Action Recommendations.........................
6
-3.1.20 Release (Florida Nuclear Plant Emergency Notification SForm ).............................................................................................................
6 3.1.21 Release, Unplanned (Reactor Plant Event Notification Worksheet)...............................................
I.............................................. 7
-3.1.22 Sabotage..................................................................................................
7 1 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...............................................................................................................
7
-3.1.33
. Visible Damage......................................................................................
7 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
TABLE OF CONTENTS (Continued)
ENCLOSURES
-PAGE 1-Em ergency Classification Table.................................
....................................... 23:
2 Florida Nuclear Plant Emergency Notification Form (and associated information)............ 39 3 ' Considerations for a Security Emergency..............................
46 4
Reactor Plant Event Notification W orksheet.....................................
................................ 51 5
Emergency Notification for Units 1/2 & 4/5 (Optional Records Non-Quality)......................
55 "6
Initiation of the Emergency Response Data System (ERDS),
56" 7
Evacuation Planning Guide..............................................
- 57 "8
Guidelines for Protective Action Recommendations 61
'7 Rev. 71 EMo202
/
\\
Page 3 of 63
1.0
- PURPOSE, This procedure 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 E2Rev. 71 EM-202 Page 4 of 63
3.0 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 everit(s) that are in process, or have occurred, involving an actual or "potentially substantial degradatiorn 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.
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' S-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) - This position is 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.
Page 5 of 63 3.1 3.1.1 3.1.2 3.1.3 3.1.4 "3.1.5 3.1.6 PERSONNEL INDOCTRINATION Definitions Bomb - An explosive device suspected of having sufficient force to damage plant systems or structures.
(See EXPLOSION.)
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.
Committed Dose Equivalent (CDE) - Dose to an organ due to the intake of radioactive materials.
Credible Site-Specific Security Threat Notification - A threat specifically to CR-3 confirmed and validated by Site 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.)
Deep Dose Equivalent (DDE) - External whole body-dose.
Emergency Action Level (EAL) - A pre-determined, observable threshold for plant conditions that places the plant in a given emergency classification..
3.1.7.3 1**
,Rev. 71 EM-202
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 Intrusion/Intruder - Suspected hostile individual (outsider) present in the Protected Area without authorization. An intruder also includes a badged employee (insider) attempting to commit or providing assistance to others in committing sabotage. These activities may occur while the insider is either physically inside or outside the Protected Area. Upon identification, the insider's authorization i§ "immediately revoked by Site Security..
3.1.16 Local Assembly Area - A pre-designated area personnel -report for organization, roll call, and supervision following an "Alert', emergency classification.
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).
3.1.20 Release (Florida Nuclear Plant Emergency Notification Form) - Any of the following:
,: Any increase in count rate on an effluent monitor that is a-direbt result of an event that has initiated an emergency declaration; OR Radioactivity detected by environmental monitoring;
,OR Design Basis Leakage or other suspected leakage should NOT be categorized as a release Until Sconfirmed by environmental monitoring.
Radi escaping unmonitored from the plant.
EM-202 Rev. 71 Page 6 of 63
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 appiikable 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 decayheat 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 4 400 feet or 0.83 miles in a.
S.
-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.
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 obser'vfion 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, S..
.. t e s t i n g, o r a n a ly s e s. D a m a g e is s u ff ic i e n t t o c a u s e c o n c e rn r e g a r d i n g t h e c o n t i n u e d o p e r a b i l ity o r 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.
Page 7 of 63 EM-202 Rev. 71
3.2 Responsibilities 3.2.1 The Emergency Coordinator controls all activities at CR-3 d6riihgactivation of the Radiological Emergency Response Plan.
K, 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.
3.2.61 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 K.>
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.'{1 0 CFR 50.54(x)(y)}
S-Request outside assistance, if necessary.
"Make the necessary personnel assignments to provide continuing response for long-term activities:
S-Approve media releases until the EOF is operational and assumes responsibility.
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 The Licensing / Regulatory Programs Unit prepares a written summary of any Alert, Site Area Emergencyior 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 mitigationstrategies developed by the Accident Assessment Team before implementation.
EM-202
.Page 8 of 63 Rev. 71
3.2.13 Site Security activates the Emergency Response Organization and implements evacuation of the Crystal River Energy Complex based on requests from the Emergency Coordinator.
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 understarnd the event and its significance. The initial NRC notification may be performed using the information from Items 4 through 7 and Item 12 of the FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM, in order to expedit6 notification from the Control Room. If an open communications channel is established, routine use of the form is NOT required, provided that verified changes in plant / equipment status are communicated to the NRC verbally and a summary of the communications with the NRC is maintained in the log. 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, hazardous material spills, toxic gas releases'or violent weather cbnditions, 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 or ECOn-Call and EOF Director to ensure the rationale of the emergency classification is understood. It is acceptable, if the EC requests the PGM or EC On-Call to notify the EOF Director or the EC may establish a conference call.
"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. Any exceptions to the transfer of these resl5onsibilities (delay in transfer, etc) must be clearly communicated during the facility turnover briefing.
. 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 recordingdevice 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.
3.3.10
" A Security Threat or event presents unique challenges to protecting the health and safety of the public and plant staff. Normal emergency response procedure steps may be hindered due to events that are occurring. Enclosure 3 provides considerations for a Security-related emergency.,
I - Page 9 of 63 EM-202
- Rev. 71
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 the Emergency Coordinator Guide for each emergency classification as indicated in the following Sections:
4.1 UNUSUALEVENT 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-102, Operation of the
-Technical Support Center. CONSIDER establishing a conference call with the EC On-Call and EOF Director for this turnover.
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.
4.0.9' In most situations, events are terminated rather than downgraded. However, there may be conditions where downgrading is appropriate. For downgrading the emergency classification level, if the current plant conditions have improved to satisfy a lower classification Emergency Action Level, NOTIFY the Emergency Coordinator On-Call and EOF Director for concurrence to downgrade. For Alerts or higher, unless the conditions are resolved within 30 minutes, downgrading should NOT occur until after the TSC and EOF (as appropriate) are operational and the event sufficiently evaluated by the Emergency Response Organization.,
- 4.0.10 For Emergency Phase termination and transition to the Recovery Phase, from an Unusual Event or Alert, DETERMINE the need for a Recovery Plan and a support organization. For a Site Area Emergency or General Emergency, ASSIST the EOF Director with the completion of the Termination Checklist from REP-03. If the Site Area Emergency event is of short duration (approximately 30 minutes or less), and the EOF is NOT operational, terminate the event. If conditions will allow for termination of the Emergency Phase, enter the Recovery Phase. If conditions do NOT support termination of the emergency and entry
' into the Recovery Phase, continue the Emergency Phase.
Page 10 of 63
ý -Rev. 71 EM-202
4.1 Emergency Coordinator's Guide for Unusual Event
[NOCS 1129, 96042]
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 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 and 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 using
- information from Items 4 - 7 and Item 12 of the Florida Nuclear Plant "Emergency Notification Form or Enclosure 4.
REQUIRED WITHIN 60 MINUTES.
.RPage 11 of 63 TIME I _____
I EM-202 Rev. 71
4.1.10 MRev. 71 "Unusual Event Updates TIME 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 is established)
Units 1/2 & 4/5 Control Rooms per Enclosure 5
- CR-3 Plant Personnel via PA announcements Unusual Event Termination Upon the decision to terminate, NOTIFY:
DATE
- Emergency Coordinator On-Call and 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 4.1.11 SPage 12 of 63 EM-202
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
- 3) 4)
"THERE (IS OR IS NOT) A RADIOLOGICAL RELEASE TO THE ENVIRONMENT IN PROGRESS."
STATE any appropriate special instructions (areas to be avoided or evacuated, etc.).
(LF conditions warrant personnel accountability, THEN REQUEST personnel to report to Local Assembly Areas).
- 5) REPEAT the announcement.
- 6) ESTABLISH continuous monitoring on PL-1.
/
p Page 13 of 63
ý I
÷
÷ t EM-202
- Rev. 71
Emergency Coordinator's Guid fo rah Alert [NOCS 1129, 96042]
"ALERT DECLARED RECOMMENDED WITHIN 5 MINUTES 4.2.1 NOTIFY Control Room staff of declaration and upgrade criteria (if any).
DATE J
IF the emergency is due to a Security Event, THEN REFER TO Enclosure 3 before proceeding with the following steps.
IF safe conditions exist, THEN NOTIFY Site Security to activate the TSC.
NOTIFY Plant Personnel using information from Step 4.2.18.
REQUIRED WITHIN 15 MINUTES 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 IF a release is occurring as a result of this event,
-T-HEN COMPLETE EM-204A or EM-204B, as time permits.
RECOMMENDED WITHIN 30 MINUTES I
"NOTIFY PGM or EC On-Call and the EOF Director.
NOTIFY CR-3 NRC Resident Inspector.
NOTIFY Units 1/2 &4/5 Control Rooms per Enclosure 5.
2.10 NOTIFY NRC via ENS as soon as practicable after the State using information from Items 4 - 7 and Item 12 of the Florida Nuclear Plant Emergency Notification Form or Enclosure 4.
REQUIRED WITHIN 60 MINUTES.
2.11 ACTIVATE ERDS per Enclosure 6.
REQUIRED WITHIN 60 MINUTES.
"ONCE TSC OPERATIONAL "NOTIFY AIl insurance that CR-3 is in an emergency declaration.
(Off-Site Support Phone Directory)
NOTIFY Risk Assessment to notify NEIL insurance that CR-3 is in an emergency declaration. (Off-Site Support Phone Directory)
-e Page 14 of 63 4.2 TIME 4.2.2 4.2.3 4.2.4 4.2.5 4.2.6 4.2.7 "4.
S 4..
4.;
4.2.12 4.2.13 P
Rev. 71 EM-202 I
2.8 2.9
Alert Updates, TIME 4
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 "Alert Downgrading 4.2.15 If the EC and EOF Director were notified, CONSULT with them for concurrence before downgrading occurs.
D, Alert Termination 4.2.16 Upon the decision to terminate, NOTIFY:
D
- 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
- American Nuclear Insurers (ANI) (Off-Site Support Phone Directory)
"- Risk Management (Off-Site Support Phone Directory) 4.2.17 REQUEST the Licensing/Regulatory Programs Unit to prepare a written summary within twenty-four hours (or next working day) of termination to SWPT and NRC.
ATE ATE EM-202Rev.
71 4.2.1 EM-202 SPage 15 of 63'
4.2.18 PA Announcement for an Alert CONSIDER the safety of plant personnel and then ANNOUNCE or PERFORM the following:
Tierime:___
ACTUATE the appropriate local evacuation alarm if required..
"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.).
REPEAT the announcement.
ESTABLISH continuous monitoring on PL-1.
C EM-202 Rev. 71
- 1) 2)
- 6) 7)
,Page 16 of 63 EM-202
4.3 Emergency Coordinator's Guide for Site Area Emergency
[NOCS 1129, 96042]
- TIME T IM E 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 Site Security to activate the EOF and TSC.
4.3.4 NOTIFY Plant Personnel using information from Step 4.3.22 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 fo& Energy Complex using. NOTIFY Site Security to coordinate "protective action instructions 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 and 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 using information from Items 4 - 7 and Item 12 of the Florida Nuclear Plant Emergency Notification Form or Enclosure 4.
REQUIRED WITHIN 60 MINUTES.
4.3.12
-,,-ENSURE ERDS is activated per Enclosure 6.
'REQUIRED WITHIN 60 MINUTES.
Page 17 of 63 I-EM-202 Rev. 71 '
4.3.13 4.3.15 4.3.16 4.3.17 4.:
4.2 4.:
4.
ONCE TSC OPERATIONAL TIME VERIFY Protected Area accountability is completed by Site Security within 30 minutes of an evacuation of the Protected Area.
NOTIFY ANI insurance that CR-3 is in an emergency declaration.
(Off-Site Support Phone Directory)
NOTIFY Risk Assessment to notify NEIL insurance that CR-3 is in an emergency declaration. (Off-Site Support Phone Directory)
SITE AREA EMERGENCY UPDATES 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
"-SITE AREA EMERGENCY DOWNGRADING If the EC and EOF Director were notified, CONSULT with them for concurrence before downgrading occurs.
DATE
/
SITE AREA EMERGENCY TERMINATION 3.18 IF the EOF is operational, THEN ASSIST with the completion of the Termination Checklist from REP-03.1 -
3.19 IF the event is of short duration (approximately 30 minutes or less) and the EOF is NOT operational, THEN TERMINATE the event.
3.20 Upon the decision to terminate, NOTIFY:
'DATE J_
- SWPT and document on Enclosure 2
- 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
- American Nuclear Insurers (ANI) (Off-Site Support Phone Directory)
- Risk Management (Off-Site Support Phone Directory) 3.21 REQUEST the Licensing/Regulatory Programs Unit to prepare a written summary within twenty-four hours (or next working day) of termination to, _
"SWPT and NRC.
Page 18 of 63 Rev. 71 EM-202
-4.3.22 PA Announcement for a Site Area Emergency
-°
[NOCS 7455]
CONSIDER the safety of plant personnel and then ANNOUNCE or PERFORM the following:
Tim
"1)
ACTUATE the Site Evacuation alarm.
"2)
"ATTENTION ALL PERSONNEL, CRYSTAL RIVER 3 IS IN A SITE AREA EMERGENCY BASED ON
-3)
"THERE (IS OR IS NOT) A RADIOLOGICAL RELEASE TO THE ENVIRONMENT IN PROGRESS.
S4)
IF the TSC/OSC is NOT activated, THEN ANNOUNCE: OACTIVATE THE TSC/OSC."
- 5)
"PERSONNEL ARE TO IMMEDIATELY EVACUATE THE PROTECTED AREA AND REPORT TO THE SITE ADMINISTRATION BUILDING AUDITORIUM.
- 6)
"ALL EOF PERSONNEL, REPORT TO THE EOF."
- 7)
STATE any appropriate special instructions (areas to be avoided or evacuated, etc.).
- 8) 9)
REPEAT the announcement.,
ESTABLISH continuous monitoring on PL-I.
7 Page 19 of 63
, EM-202 SRev. 71
-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,"
T-HEN 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 Site Security to activate the TSC and EOF (if NOT already activated).
4.4.5 NOTIFY Plant Personnel using information from Step 4.4.22 and ACTUATE Site Evacuation Alarm if Protected Area NOT already evacuated.
REQUIRED WITHIN 15 MINUTES 4.4.6 DETERMINE Protective Action Reconmmendations 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 Site Security to coordinate evacuation instructions 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.
g-S 4.4.12 NOTIFY NRC via ENS as soon as practicable after the State using information from Items 4 - 7 and Item 12 of the Florida Nuclear Plant Emergency Notification Form or Enclosure 4.
REQUIRED WITHIN 60 MINUTES.
4.4.13 ENSURE ERDS is activated per Enclosure 6.
REQUIRED WITHIN 60 MINUTES.
EM-202 Rev. 71 Page 20 of 63
-ONCE TSC IS OPERATIONAL TIME 4.4.14 VERIFY Protected Area accountability is completed by Security within 30 minutes of an evacuation of theProtected Area.
<.._z 4.4.15 NOTIFY ANI insurance that CR-3 is in an emergency declaration.
"(Off-Site Support Phone Directory) 4.4.16 NOT IFY Risk Assessment to notify NEIL insurance that CR-3 is in an emergency declaration. (Off-Site Support Phone Directory)
"GENERAL EMERGENCY UPDATES 4.4.17 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 GENERAL EMERGENCY TERMINATION 4.4.18 IF the EOF is NOT operational, THEN WAIT until the EOF is operational before terminating.
4.4.19 IF the EOF is operational, THEN ASSIST with the completion of the Termination Checklist from REP03.
4.4.20 Upon the decision to terminate, NOTIFY:
-'DATE I
- 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
- American Nuclear Insurers (ANI) (Off-Site Support Phone Directory)
"- Risk Management (Off-Site Support Phone Directory) 4.4.21 REQUEST the Licensing/Regulatory Programs Unit to prepare a written summary within twenty-four hours (or next working day) of termination to SWPT and NRC.
EM-202 Rev. 71 Page 21 of 63
4.4.22 PA Announcement for a General Emergency
[NOCS 7455]
CONSIDER the safety of plant personnel and then ANNOUNCE or PERFORM the following:
Time:: _._'m_.
- 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."
- 6)
-IF the EOF is NOT activated, THEN ANNOUNCE: "ALL EOF PERSONNEL, REPORT TO THE EOF."
- 7)
STATE any appropriate special instructions (areas to be avoided or evacuated, etc.).
- 8) 9)
REPEAT the announcement.
ESTABLISH continuous monitoring on PL-1.
/
Page 22 of 63 EM-202 Rev. 71
--EMERGENCY CLASSIFICATION TABLE.
EMERGENCY ACTION LEVEL INDEX ENCLOSURE 1 (Page 1 of 16)
- ABNORMAL RADLEVELSI RADIOLOGICAL-EFFLUENT
-CATEGORY ~
~~UE1
- ALERT
'~~SAE
~Q-GE~
Gaseous Effluents 1.1 12 1.3 1.4 Uquid 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,
'$Z
~
~
UE-
-~
ALERT U SAE
~ T GE Earthquake Experienced 2.1 2.2 External Flooding 2.3
°,
2.4 A_
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
-I I 2.14 2.15 Control Room Evacuation 2.16 2.17 Secunty Event
",2.18 2.19 2.20 2.21 "Internal Flooding 2.22
'-2.23 SEmergency Coordinator Judgment 2.24
-2.25 2.26 2.27
. ~ ~'~i~
~~ThxSYSTEM MALFUNCTION'f
- <L%
%V
-CATEGORYI.
i<
UE-':.
' ALERT:
"Loss of Communications 3.1 Failure of Reactor Protection
-32 3.3 3.4 Inability to Reach ITS Time Umits 3.5 Loss of Alarms/Indications 3.6
_ - 3.7 3.8 Fuel Clad Degradation 3.9 Turbine Failure 3.10
-3.11 SRCS Leakage 3.12 Inability to Maintain Hot Shutdown
-3.13 Inadvertent Cnticality 3.14 Inability to Maintain Plant in Cold Shutdown 3.15 Loss of Water Level in Reactor Vessel that has Uncovered or Will Uncover Fuel S~LOSS OF POWER
-':i
,CATEGORY.-~
"~-
9~E ~
ALERT. -
~
~
G GE~
Loss of AC Power 4.1 42-4.3 4.4 Loss of AC Power (Shutdown) 4.5 Loss of Vital DC Power 4.6 Loss of Vital DC Power (Shutdown) 4.7,_
Page 23 of 63 t
EM-202 Rev. 71
.Emergency Classification Table FISSION PRODUCT BARRIER MATRIX APPLICABLE MODES: 1-4 COMPLETE FOR ALL BARRIERS 4tOSS'OF'FUEL CLAD~~
any Item Is checked, barrier' Is'Iost.
&r FUEL: CLAD In classificationtablebelow.A CORE CONDITIONS IN REGION 3 OR SEVERE ACCIDENT REGION OF ICC CURVES 2
RCS ACTIVITY >300 pCVgm 1-131 DOSE`
EQUIVALENT LOSS OF' REACTOR "COOL~ANT SYSTEM
\\
if any Item Is checked, barrier Is lost ;
2,,*
,Enter 4 for RCS It classification table below.
Z,,,
.LOSS OF!CONTAINMENT...>
-,E It any Item,'
Is checked bararIer Is' lost.
~Enter,ý2 for, CONTAINMENrIW'cla'isifkatlon table below.
- 1. RAPID UNEXPLAINED RB PRESSURE '
, DECREASE FOLLOWING INITIAL INCREASE L ___
1 4
I I-
- LONGER,
- 3. AN OTSG HAS > 10 GPM TUBE RUPTURE "WITH PROLONGED STEAMING TO THE
- 3. RM-G29 OR 30 >100 R/hr FOR 15 MINUTES
- 3. EC DEEMS RCS BARRIER IS LOST.
ATMOSPHERE FROM THE AFFECTED OTSG OR LONGER OR AN UNISOLABLE STEAM LEAK OUTSIDE RB FROM THE AFFECTED OTSG '
- 4. CONTAINMENT ISOLATION IS INCOMPLETE
- 4. EC DEEMS FUEL CLAD BARRIER IS LOST, AND RELEASE PATH TO THE ENVIRONMENT EXISTS
- 5. EC DEEMS CONTAINMENT BARRIER IS LOST POTENTIAL, LOSS.OF'FUEL CLAD -.. "
POTENTIAL' LOSS'OREACTOCOOAN OTENTIALLOSS'OF CONTAINMENT
'i Is ke-SYSTE I
r f any Item Is checkedbre Is potentIially lot Ilf any, lem schec kd, arr~lier.l* potentially lo~st.
/ ;i
!a y m l n c e,o rlrsp~
n a yi
- s.
':Enter 3' or FUEL CCLAD In' classIlfication 'table belowv ;
lf'anY Item Is checkedbarrler is'potentlallyiIost;<*s*
Enter1.i5 for CONTAINMENT In class hficatlon table below.:
~~,
~~~
' ~ Enter,3 for R~CS in classification table beIlo w.
Z
~'
~ ~ '
- 1. RCS CONDITIONS WARRANT ENTRY INTO
- 2. CORE EXIT THERMOCOUPLES >700'F
ACTUATION ON LOW RCS PRESSURE,
- 3. EC DEEMS FUEL CLAD BARRIER IN
- 3. RCS PRESSURE/TEMPERATURE RELATIONSHIP
- 4. HPI/PORV OR HPI/SAFETY VALVE COOLING IS IN
"'**'PROGRESS
- 4. RMG-29 OR -30 READINGS >25,000 1R ihr" 5" ECDESRSBRIRIEPR5.
CORE CONDITIONS IN SEVERE ACCIDENT
,,5. EC DEEMS RCS BARRIER IN JEOPARDY REGION OF ICC CURVES FOR >15 MINUTES
- 6. EC DEEMS CONTAINMENT BARRIER IN
'*,,JEOPARDY ENTER LOSS OR POTENTIAL LOSS OR ZERO FOR EACH BARRIER THEN TOTAL AND DETERMINE CLASS BELOW FUEL CLAD
+
+
CONTAINMENT
=
=
>OBUT<2 UNUSUAL EVENT
>2BUT<4 ALERT
> 4 BUT < 8.5 SITE AREA EMERGENCY,
> 8.5 GENERAL EMERGENCY' E-0Rev. 71 IFjTOTALIS:7_
4*,2 RECO MMENDED EVENTCLASSI FICATION IS:'*
Page 24 of 63 EM-202 APPLICABLE MODES: 1-4 COMPLETE FOR ALL BARRIERS I....................
F "LOSURE 1
_ge 2 of 16)
C EMERGENCY CLASSIFICATION TABLE "ACCIDENT CONDITION:
ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT GCATEGORY EERIER<UNU ENC7ALERT' S
ARE Gaseous Effluents MODES. ALL 1.1 MODES ALL (I or 2)
- 1. A VALID reading on RM-AI or RM-A2 gas channel exceeds the high alarm setpoint for 60 minutes or longer OR 2
Sample analysis confirms gaseous effluent being released exceeds 2 times the ODCM noble gas release setpoint for 60 minutes or longer 1.2 MODES. ALL (I or'2) 1 A VAUD reading on RM-A1 or RM-A2 Mid-Range monitor exceeds 6mR/hr for 15 minutes or longer OR 2 Sample analysis confirms gaseous effluent being released exceeds 200 times the ODCM noble gas release setpoint for 15 minutes or longer Liquid Effluents 1.5 MODES:ALL
1.6 MODES
ALL (I or 2)
A VAUD 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 setpolnt for 15 minutes or longer release exceeds 2 times the ODCM release setpoInt for 60 minutes or Slonger OR
- 2.
Release continued for 60 minutes or longer with no dilution flow 1.3 MODES.
ALL (I or2or3)
- 1. VALID RM-A1 or RM-A2 Mid-Range monitor reading exceeds the values on the following Table for the current Stability Class for 15 minutes or longer Stab, Class Reading (mR/hr)
A, BorC 100 D or E 20 ForG 12 OR
- 2. Dose Assessment results indicate SITE BOUNDARY dose >100 mR TEDE or >500 mR thyroid CDE for the actual or projected duration of the release OR s
3 Field survey results indicate closed windows dose rates >100mR/hr expected to continue for more than one hour. or analyses of field survey samples Indicate thyroid CDE of 500mR for one hour of Inhalation, at or 1.4 MODES ALL (1 or 2 or 3)
- 1. VALID RM-AI or RM-A2 Mid-Range monitor reading exceeds the values on the Table below for the current Stability Class for 15 minutes or longer:
Stab Class Reading (mR/hr)
A, B or C 1000 DorE 200 ForG 120 OR,
- 2. Dose Assessment results Indicate SITE BOUNDARY dose >1000 mR TEDE or
>5000 mR thyroid CDE for the actual or projected duration of the release AND core damage is suspected or has occurred ORe
- 3. Field survey results indicate closed windows dose rates >lOOOmR/hr expected to continue for more than one hour, or analyses of field survey sample,,
Indicate thyroid CDE of 5000 mR for one hour of Inhalation, at or beyond SITE PrIlli imnanRY Page 25 of 63 S'ILOSURE 1
," ge 3 of 16)
Rev 71 EM-202
(
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
"LOSURE1
.ge 4 of 16)
ABNORMAL RAD LEVELS/RADIOLOGICAL EFFLUENT Page 26 of 63 I
EM-202 Rev. 71 6
(7 EMERGENCY CLASSIFICATION TABLE Q "LOSURE1
.ige 5 of 16)
ACCIDENT CONDITION NATURAL / MANMADE HAZARDS AND EC JUDGEMENT Page 27 of 63 I
EM-202 Rev. 71
(
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
NATURAL / MANMADE HAZARDS AND EC JUDGEMENT (Continued)
U.NULSPAL.'EVENT p~Q~
- ALERT, SIEAE EEGNCY~ 6ENERA-EMERGENC 26 MODES ALL Report by plant personnel of a Tornado stnking within the PROTECTED AREA 2 8 MODES ALL Report by plant personnel of Aircraft or Vehicle Crash Involving the following permanent structures' Auxiliary Building.
BWST NControl Complex Diesel Generator Building EFT-2 Building I
Intermediate Building Reactor Building EFP-3 Building 2.7 MODES-ALL (1 and 2)
- 1. Tornado or High Winds or windbome object strike one of the following structures, Auxiliary Building,'
- BWST,
- Control Complex, Diesel Generator Building,
- EFT-2 Building, Intermediate Building, SReactor Building
- EFP-3 Building AND 2
a
" (aorb),
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 windbome objects 2.9 MODES ALL (1 or 2)
- 1. Confirmed report of significant VISIBLE DAMAGE to buildings fisted below:.
OR 21 Auxiliary Building BWST Control Complex Diesel Generator Building EFT-2 Building Intermediate Building Reactor Building EFP-3 Building ndicatlons show degraded SAFE SHUTDOWN EQUIPMENT ý erformance due to the Aircraft or Vehicle Crash 1 1 t)
EFmergcoissniy Cr0tn atdg or'.
Page 28 of 63 "MLOSURE1 Q age 6 of 16)
Tornado/High Winds MODES ALL Aircraft/Vehicle Crash MODES ALL' I
EM-202 Rev. 71
C ACCIDENT CONDITION:
NATURAL/ MANMADE HAZARDS AND EC JUDGEMENT (Continued)
WCATEGORY.-
C AEG TALERTI VSITE ARE IEMERGENCY
- , GENERALkE-M ERGENCY Toxic or Flammable Gases' MODES. ALL 2.10 MODES-ALL (1 or 2) 1 Report or detection of Toxic or Flammable Gas within the SITE BOUNDARY that could enter the "Prctected Area at levels > IDLH or 25% Lower Explosive Umits affecting normal operation of the plant OR
- 2. Confirmed notification by FP. County, or State personnel to evacuate or shelter site personnel based on an offsite event r
T I
2.11 MODES-ALL (I or 2 or 3)
- 1. Flammable Gas levels > 25% Lower Explosive Limit In areas required to maintain safe operations or establish and maintain cold shutdown OR
- 2. Toxic Gas levels > IDLH levels In areas that require continuous occupancy to maintain safe operation or establish or maintain cold shutdown OR
- 3. Toxic Gas levels > 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
.1 __________________________
J ____________________
11 Page 29 of 63 EMERGENCY CLASSIFICATION TABLE
"-( 'LOSURE1 age 7of 16)
EM-202 Rev. 71
(7 EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
NATURAL I MANMADE HAZARDS AND EC JUDGEMENT (contil C.ATEG.ORY UNU I-A'ffVET
- ,ALERT
ý S!TEAREAE EMERGENCY Explosions/
Catastrophic Pressurized Equipment Failure MODES, ALL Fire MODES ALL 2.12 MODES. ALL I
'Refer to Fission Product Barier Matx*&
S; System Malfuhntldonor Emerency*,*
Cnord~naftbr'Judgmdient7 'z Page 30 of 63
" "IOSURE 1 ge 8 of 16)
EM-202 Rev. 71
(
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
NATURAL / MANMADE HAZARDS AND ECJUDGEMENT (Continued) h,,~CATEG'oRY4;
!'UNUSUAL EVENT 4:
~ALERT,,j~~
SITE, AREAkEMERGENCY GENERAL EMERGENCY.
Control Room Evacuation MODES, ALL Security Event MODES-ALL 2.18 MODES-ALL (1 or2or3)
Report by Security Shift Supervisor of one or more of the following events.
- 1. OcCurrence of SABOTAGE OR
- 2. HOSTAGE/EXTORTION situation or hostile STRIKE ACTION threatening to Interrupt plant operations 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 2.16 MODES: ALL Control Room evacuation Is required per AP-990, "Shutdown Outside of the Control Room*
2.19 MODES. ALL (1 or 2)
- 1. Discovery of BO)MB within the PROTECTED AREA OR
- 2. INTRUDER(S) penetrates the PROTECTED AREA, r
r 2.17 MODES-ALL (I and 2)
- 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 2.20 MODES-ALL, INTRUDER(S) penetrates or a BOMB is discovered In any of the areas listed below.
Auxiliary Building
- BWST Control Complex EFT-2 Building, Diesel Generator Building Intermediate Building Reactor Building EFP-3 Building 2.21 MODES. ALL INTRUDER(S) has taken control of the Control Room, or Remote Shutdown Room or plant equipment such that plant personnel are unable to operate equipment required to establish and maintain safe shutdown conditions Page 31 of 63
'OSURE 1 9 of 16)
EM-202 Rev. 71
C C'
FMFFNIV
(I AIFlCATIflN
ARI F ACCIDENT CONDITION:
NATURAL I MANMADE HAZARDS AND EC JUDGEMENT (Continued)
CAEOR'Y I
UNUSUAL.'EVENT;:
~4fALERT'
':IEAE EIIRGN Gý ERGEI Internal Flooding "Modes ALL Emergency Coordinator, Judgment MODES ALL 2 22 MODES-ALL 11 nnd
- 1. Indication of uncontrolled flooding in the Auxiliary Building or Intermediate Building AND
- 2. Water leveVflooding has the potential to affect or Immerse SAFE SHUTDOWN EQUIPMENT 2.24 MODES-ALL Other conditions exist which indicate a potential degradation of the level of safety of the plant 2.23 MODES. ALL (1 and 2)
- 1. Water level exceeds 1 5 feet In the Auxiliary Building or Intermediate Building AND
. I (a orb)"
2.
- a. Indications show degraded SAFE SHUTDOWN EQUIPMENT due to the flooding OR
- b. Electrical hazards prevent plant personnel normal access to areas of plant containing SAFE SHUTDOWN EQUIPMENT 2.25 MODES, ALL Other conditions exist which Indicate that events are In process or have occurred which involve potential or actual substantial degradation of the level of safety of the plant
-Refer to
- Fissiont ri" 2.26 MODES ALL Other conditions exist which indicate actual or likely major failures of plant functions needed for the protection of the public
'* Refer to Fisslon Frbduct B e
P Matrr, or, 2.27 MODES. ALL (1 or 2)
Other conditions exist which indicate:
- 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)
MRPage 32 of 63
'. "-OSURE 1
,e 10 of 16)
(
'1*M.202 I Rev. 71
C EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
SYSTEM MALFUNCTION,
.,EVENT~>>~ ~ALERT
~
j JLSITEIARI Rev. 71
" "LOSURE 1 jell of 16)
Page 33 of 6 EM-202
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
SYSTEM MALFUNCTION (Continued) -."
UNJIAL:VET
~
ALERT'
' SITE ARENEMERGENCY3/4 I Page 34 of 63 "LOSURE 1 je 12 of 16)
EM-2'02 Rev. 71
C ACCIDENT CONDITION:
SYSTEM MALFUNCTION (Continued)
CATEGORY,;\\1*
~UNUSUALýElENT
~
ALET-S I E I
EEMERGU Fuel Clad Degradation MODES 1,2,3,4,5 Turbine MODES Failure 1,12,3 4-3.9 MODES 1,2,3,4,5 (a or b)
Radiochemistry analysis Indicates.
- a. Dose Equivalent Iodine (1-131)
> 1.0 piCifgm 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/S-bar for
-48 hours or longer, /
3.10 MODES-1,2,3 Report by plant personnel of ma failure causing penetration of thi casing or damage to main genei Rfef-r to l 3.11 - MODES-1,2,3 in turbine (1 or 2) a turbine rator 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 e
EMERGENCY CLASSIFICATION TABLE F
'.OSURE 1 Je 13 of 16) to Fission C
Rev. 71 Page 35 of 63
EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
'SYSTEM MALFUNCTION (Continued)'
/
'OSURE 1 al 14 of 16)
""M0Rev. 71 Page 36 of, 63 ORY U I NUSUAL EVENT ALERT
ýSITE';'
r' EM-202
'C N'
"EM-02Rev. 71 EMERGENCY CLASSIFICATION TABLE I
ACCIDENT CONDITION:
"-OSURE 1
.,e 15 of 16)
EM-202 Page 37 of 63
C
'CAITEIGOIRY 7
UU:UALEVENf ALERTW EMERGENCY GENERAL.-EEMERGERNTCY Loss of AC Power MODES ALL for UNUSUAL I
'EVENT' L
MODES-1,2,3,4 for ALERT, SITE AREA and "GENERAL Emergencies,
'Loss of AC Power (Shutdown*
MODES. 5,6, No Mode (defueled)
Loss of Vital DC Power' MODES. 1,2,3,4 Loss of Vital DC Power (Shutdown)
MODES: 5,6, No Mode (defueled) 4.1 MODES.
ALL (1 and 2)
- 1. Offsite Power Transformer (OPT) and Backup ES Transformer (BEST) an.d Auxiliary Transformer not available for
'15 minutes or longer AND
4.7 MODES
5,6, No Mode 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 II 4.2 MODES.
1,2,3,4 AC power capability to the 41660V ES busses reduced to a single power source for 15 minutes or longer such that only one of the following is available:
"A"EDG
"*B EDG Offsite Power Transformer (OPT)
Backup ES Transformer (BEST) 4.5 MODES. 5,6, No Mode Neither 4160V ES bus is capable of being energized within 15 minutes I
1 4.3 MODES'-
1,2,3,4 Neither 4160V ES bus is capable of being energized within 15 minutes
4.6 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 4.4 MODES' 1,2,3,4 (1 and 2)
- 1. Neither 4160V ES bus Is capable of being energized AND
- 2. (a orb)
- a. Restoration of 4160V ES Bus A or 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 /> OR
- b. Core exit thermocouples > 700°F as indicated on SPDS EM-202 Page 38 of 63 EMERGENCY CLASSIFICATION TABLE ACCIDENT CONDITION:
"LOSS OF POWER
" "LOSURE1 je 16 of 16) 14 I
t
/
Rev. 71
ENCLOSURE 2 (Page 1 of 7)
Florida Nuclear Plant Emergency Notification Form
- 1.
THIS IS CRYSTAL RIVER UNIT 3.:A. El THIS IS A DRILL. B. El THIS IS AN ACTUAL EVENT. I HAVE A MESSAGE.
ENSURE:
[I STATE 0
CITRUS El LEVY El RAD. CONTROL-ORLANDO (M-F ONLY) ARE ON LINE.
A. Time/Date contact made B. Reported by: (Name/Title)
C.' Message Number _
A. Z CRYSTAL RIVER UNIT 3 D. Reported from: 5 Control Room E] TSC E] EOF
ýj'O St LbCiEUNiTi ':U ;TUR KEY POINT UNIT 3 C. _ST LUCIE UNIT2 <E._I UTURKEY POINT UNIT.4
- 4. ACCIDENT CLASSIFICATION A. [] NOTIFICATION OF UNUSUAL EVENT C. [5 SITE AREA EMERGENCY CCIENTB.
5 ALERT D.E5 GENERAL EMERGENCY
- 5. CURRENT EMERGENCY DECLARATION:
TIME DATE
- 6. REASON FOR EMERGENCY DECLARATION:
- 7. ADDITIONAL INFORMATION OR UPDATE:
- 8. INJURIES REQUIRING OFFSITE SUPPORT: A. ] No' 5] Yes 5] Unk B. Contaminated: El No El Yes [I Unk
- 9. WEATHER DATA:
A. Wind direction from degrees.
B.
Downwind Sectors affected (minimum of 3):.
- 10. RELEASE STATUS:
A. E] No Release (Go to Item 12)
C. El A Release occurred, but stopped B. E] A Release is occurring -
- 11. OFFSITE RELEASE SIGNIFICANCE CATEGORY (at the Site Boundary)
A. El Information not available at this time.
B. El Release within normal operating limits (Tech Specs/ODCM)
C. El Non-Significant (Fraction of PAG Range, release is > normal limits and <PAG levels)
' D El PAG Range (Protective Actions required)
- 12. UTILITY RECOMMENDED PROTECTIVE ACTIONS A.
[ 5 N O N E B. E S H E L T E R Z O N E S / A R E A S :_
EVACUATE ZONES/AREAS:__
- 13.
HAS E TB TERMINED:
AN O
ACnO EVAYUATESECTiReS ELTER EC-DatO
- 13. HAS EVENT BEEN TERMINATED?:
A.E5 NO B. ElYES: Time _____Date'-
- 14. SUPPLEMENTAL FORM IS ATTACHED?:
A.
Al NO
- 15. MESSAGE RECEIVED BY:
Name THIS -IS CRYSTAL RIVER UNIT 3. E0 THIS IS A DRILL.
ECIEOF DIRECTOR INITIALS.
B.El YES "Time Date El THIS IS AN ACTUAL EVENT.
END OF MESSAGE.
Page 39 of 63
- 3. SITE Rev. 71 -
EM-202
ENCLOSURE 2 "Supplemental Data Sheet (Page 2 of 7)
The following supplemental data is completed by the TSC or EOF for an Alert or higher emergency declaration.
Supo"lerhent to Message Number ___________
PLANT CONDITIONS INFORMATION CRITICAL SAFETY FUNCTIONS:
A. REACTOR SHUTDOWN?
E] YES El NO B. CORE ADEQUATELY COOLED?
[I YES E] NO C. ADEQUATE EMERGENCY POWER AVAILABLE (DIESELS OR OFFSITE SOURCE)
E] YES E] NO FISSION PRODUCT BARRIER STATUS: (Refer to EM-225, Enclosure 8, Part III to complete this section and check one condition for each barrier)
RIER I
CJNTACT I.*CHALLEEGEDA:IE
"~FUEL~§'
'LADD[ NGZ REACTOR 2 0OL ANT YSTEM:ý'.
'CONTAINM ENT--
No indication of clad damage Leakage is within normal charging or makeup pump capacity.
No evidence of containment leakage or tube rupture release is only through condenser Clad is intact but losing subcooling, water level, etc.
Leakage is within safety injection capacity No leakage but containment pressure is at or above safety system actuation points (30 PSIG)
Clad has failed, indicated by high temps., high containment rad, etc.
Leakage exceeds safety injection
- capacity Evidence of containment leakage (known release path or radiation surveys)
Cooling restored, no further degradation expected Leakage reduced to within Injection
- capacity (system repaired)
Repair efforts have isolated leak or containment pressure has reduced to stop leakage COMPLETED BY:
TIME:
DATE:
- 1. RELEASE STATUS:
RADIOLOGICAL DOSE ASSESSMENT DATA A. El No Release (no further data required)
C. El A Release occurred, but stopped B. El A Release Is occurring
- 2. RELEASE RATE:
A. El NOBLE GASES:
Curies per second E] 'Measured El Default B. E] IODINES:
_ -Curies per second F1 Measured E] Default
- 3. TYPE OF RELEASE:
A. F1 AIRBORNE Time/Date Started::
B. F1 Time /Date Stopped:
- 4. PROJECTED OFFSITE DOSE RATE:
DISTANCE THYROID DOSE RATE (CDE)
TOTAL 1 Mile (Site Boundary)
A.
mremlhr B.
2 Miles
- C.
mrem/hr D
5 Miles E.
mremlhr F.
10 Miles G.
".mrem/hr
" H.
- 5. WEATHER DATA (used for the above data):
A. Wind Direction from _
degrees.'
B. Wind Speed _
_MPH (2.24 X meters/sec.)
Stability Class_ _
(Sigma Theta or Wind Range; See page 6 of 7)
COMPLETED BY:
"LIQUID Time/Date Started:
Time/Date Stopped:
DOSE RATE (TEDE) mrem/hr mrem/hr mrem/hr
_.mrem/hr TIME:______
DATE:
SPage 40 of 63 ai Rev. 71 EM-202
ENCLOSURE 2 J(Page 3of 7)
State of Florida Notification Protocol
[NOCS 96024]
,-GENERAL NOTIFICATION PROTOCOLS
.. Nhen communicating information to State and Counties, enunciate proper, read off the information by line number, transmit numbers digit by digit, avoid sound alike action statements, spell ifficult words, as appropriate, use three word phrases for descriptions / narratives, and do NOT use technical jargon.
if the emergency is terminated or reclassified before all contacts are made, or if the emergency is the result of an Emergency Action Level(s) indicating a higher classification that after a brief period is downgraded to a lower classification,'
perform the following:
.'1 "o STATE-the current emergency classification; and then o
STATE the highest classification status and when it was achieved; and then o
STATE the period of time that the higher classification existed and the mitigating conditions that caused the
,emergency classification to be downgraded.
In long-lasting events caused by natural phenomena, regular update notifications to the State and Counties can be suspended or the frequency reduced (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, shiftly, etc.) if both the following criteria are met:
.o State and Counties agree to the suspension orreductioninfrequency.
o There is NO significant change in plant status.
If during a notification, a change in classification occurs, perform the following as appropriate. REFER TO initial notification protocois for when a classification is briefly met.
If a higher classification is met:
o SUSPEND notification of the lower classification o
INFORM off-site agencies to stand-by for classification upgrade "o-TRANSMIT the higher classification verbally and FAX the lower classification form to the agencies If a lower classification is met:
I I.
o COMPLETE the current communication in progress o
INFORM off-site agencies to stand-by for classification downgrade COMPLETE the Supplemental Form when the TSC or EOF is operational. READ the Supplemental Form as part of the emergency notification and FAX after the notification is complete.
- After the Emergency Coordinator or designee approves the FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM, any information added to or any changes to existing information requires re-approval before transmittal off-site.
o correct an error on the form, draw a single line through the error, enter the correct information, and initial and date.
Completion time of the last notification transmittal is the'start time of the 60-minute clock for-update notifications.
INITIAL NOTIFICATION Within 15 minutes of declaration of emergency classification, any change in emergency classification, or any change to' Protective Action Recommendations NOTIFY-State Warning Point Tallahassee. This also notifies Citrus and Levy counties and the Department of Heafth Bureau of Radiation Control (DHBRC)-Orlando. Ensure offsite agencies are on line by checking each box as station roll call is completed. If offsite agencies do NOT respond to roll call, separate notifications using Commercial telephones to Citrus (746-2555) and Levy County (1-352-486-5212 or 1-352-486-5111 after hours) are required. SWPT will contact DHBRC. If information is NOT available, do NOT delay notification to State Warning Point Tallahassee. Item 2.A of the form is the official time lo-rthe 15 minute notification time limit and update notifications and is considered completed when SWPT answers the telephone, NOT when roll call or the message is completed.
Using one of the following communications networks listed by priority:
"- STATE Hot Ringdown (SHRD) - Station 120 or 121
- Commercial Telephone Systern:l -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)
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 briefly met for a higher classification, explain in Additional Information or Update section using guidance from item 7 on page 5 of this enclosure.
\\._),nce communications is established with the' SWPT Duty Officer and the station roll call is complete, READ the message in its entirety, REPEAT information and answer questions as requested.
After the notification is completed, FAX the FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM by using Group 1 from the Fax machine. Group 1 consists of SWPT, Citrus County EOC Levy County EOC, Department of Health, Bureau of Radiation Control (DHBRC)-Orlando, and Florida Power Emergency Response Facilities.
EM-202 Rev:71
-Page 41 of 63
_ 1
ENCLOSURE 2 State of Florida Notification Protocol (Continued)-
(Page 4 of 7)
UPDATE NOTIFICATION 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-meetin the above criteria does NOT require the use of the FLORIDA NUCLEAR PLANT EMERGENCY NOTIFT'ATION-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.
If the update notification will be delayed because of current plant conditions and activities, inform the SWPT Duty Officer.
Page 42 of 63 EM-202 Rev. 71 -
ENCLOSURE 2 (Page 5 of 7)
Guidance for Completing the Florida Nuclear Plant Emergency Notification Form NOTE: Shaded areas on the form are used by other Florida Nuclear Plants and are NOT completed for CR-3.
- 1.
Check appropriate box based on a drill or actual event.
"2.
A.
Enter the time (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) and date (MM/DD/YY) 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 update notification.
B.
Print the name and position title of person making the notification. Do NOT use acronyms.
C.
Enter message number (beginning with #1 and following through sequentially in the TSC and EOF).
D.
Check the location box 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. Refer to item 7 guidance for when conditions briefly exist for a higher classification.
- 5.
Enter the emergency declaration time (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) and date (MM/DD/YY) for the current accident classification.
- 6.
Enter 1) a short description of the current event in layman's terms to indicate the accident condition Emergency Action Level (paraphrased) or 2) the status of the Fission Product Barriers used to declare the event (e.g., Loss of Reactor Coolant System Barrier, Potential Loss of Fuel Clad Barrier, etc.) from the FPB Matrix. This information should remain the same throughout update messages unless there is a classification change. Do NOT use plant-specific acronyms or abbreviations.
- 7.
Enter 1) additional significant events, including if conditions briefly existed for a higher emergency classification but NO longer exist, or 2) 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). If, before the initial notification or since the previous notification, conditions were met (even briefly) for a higher classification, ensure that the classification and condition is noted in this item. Refer to Enclosure 2, Page 3 for additional instructions. Do NOT use plant-specific acronyms or abbreviations.
- 8.
Item "A"; Check "YES" only if there are injuries or illnesses that require off-site support (EMS, hospital). Check "Unk" if the 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 if there 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."
SECTORS AFFECTED i-
_327-348 GHJ
- 10.
Check Item "A" if there 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. RELEASE: (Refer, to "Release (Florida Nuclear Plant Emergency Notification Form)" definition.)
- 11.
Check applicable Release Significance Category based on table on page 7 of this enclosure.
12.*
Check Item "A" if NO Protective Actions are necessary. Check Item "B" if PARs are necessary and enter Zone designation.
- 13.
Enter the time (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) and date (MM/DDIYY) the emergency classification 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.
- 15.
Print the name of the SWPT Duty Officer or the individual that receives the notification. Enterthe time (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) and date (MM/DD/YY) the call is completed or when the 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.
Page 43 of 63
,DEGREES
- z SECTORS
-DEGREES J, *SECTORSý
-I DEGREES SECTORS 349-11 (349-371)
HJK 102-123 (462-483)
N P Q 214-236 B CD 12-33 (372-393)
J K L 124-146 (484-506)
P Q R 237-258 C D E 34-56 (394-416)
KLM 147-168 (507-528)
Q R A 259-281 D E F 57-78 (417-438)
L M N 169-191 (529-540)
R A B 282-303 E F G 79-101 (439-461)
M N P 192-213 A B C 304-326 F G H EM-202 Rev. 71
- -ENCLOSURE 2 (Page 6 of 7)
Guidance for Completing the Supplemental Data Sheet of the Florida Nuclear Plant Emergency Notification Form k,.jlant Conditions Information (The Accident Assessment Coordinator completes this section for all classification levels)
Check the appropriate box for Critical Safety Functions based on current plant conditions.
Check the appropriate box indicating the current status of the Fission Product Barriers using EM-225, Enclosure 8, Part II.
This information should be verified with item 6 of page 1 for consistency.
Print the name of the individual completing this section and enter the time (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) and date (MM/DD/YY) the information is completed.
Radiological Dose Assessment Data (The Radiation Controls Coordinator completes this section if a release is occurring or occurred, but stopped. Otherwise, this section is NOT completed except for "Completed By.")
- 1. Check Item "A" if there are NO indications of a release, this section is NOT completed. Check Item "B" if a release is occurring, even though it rffaji be less than normal operating limits. Check Item "C" if a release has occurred but stopped. This information should be verified with item 10 of page 1 for consistency.
- 2.
Enter the Noble Gas and Iodine Release Rates in Ci/sec from the RadDose IV printout and check the measured or default box as appropriate.
-3.
If Item 1, box A is checked, N/A this item. If Item 1, box B or C is checked, check the appropriate box for airborne or liquid release and enter the time and date the release started and stopped.
- 4. Enter the Projected Thyroid Dose Rate (CDE) and Total Dose Rate (TEDE) for each distance location from the RadDose IV printout.
- 5. Enter the wind direction in degrees in Item "A," the wind speed in MPH in Item "B," and the Stability Class based on the Sigma Theta or Wind Range table below from the RadDose IV printout. This data is used for Item 4 and may be different than Item 9 "A" on page 1.
STABILITY CLASS Print the name of the individual completing this section and enter the time (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) and date (MM/DD/YY) the information is completed. ComDlete this item even when Item 1 is checked "No Release.
EM-202 Rev. 71 Page 44 of 63
<SIGMA-THETA WIND RANGES DELTA T STABILITY CLASS 2
')(degrees)
(degrees)
-(degrees)
> 22.5
>_135 "5"
.- 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
<7.5to3.8.
44to 23
-0.38 to 1.15 E
<3.8to2.1 22to12-1.16to3.07 F
<21 ".<
12 3.08 G (most concentrated plume)
ENCLOSURE 2 (Page 7 of 7)
Release Significance Categories CORE~'
RELEASE
ý RELEASE CONDITION STATUS-
~
SIGNI'FICANCE
~
CATEGORY NO Core Damage NO release NR (orclad challenged)
Release in progress
<NOL, NS NO release NR Clad Barrier Lost Release in progress PAG NO release NR Core Melt EHE (PAG* Florida Release in progres's 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 occurring if it has NOT been detected. If a release occurred but has now stopped, maintain the appropriate category below until EPZ doses have dissipated.
- NOL: RELEASE WITHIN NORMAL OPERATING LIMITS (ITS/ODCM)
K-.4his 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.
SPAG: AT OR NEAR PROTECTIVE ACTION GUIDELINE VALUES This category indicates releases that are occurring after the fuel clad barrier has been lost. 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. This category addresses fuel damage in the core only. Spent fud damage will be
- addressed on a case-by-case basis.
EHE: EARLY HEALTH EFFECTS (NOT on Florida Nuclear Plant Emergency 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 evauation of 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 is posted on status boards in the TSC and EOF.
I Page 45 of 63
.Rev. 71 EM-202
ENCLOSURE 3 (Page 1 of 5)
Considerations for a Security Emergency READ items 1 through 5.
- 1.
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)?
- 2.
IF Security is NOT aware of the potential Security Emergency,
- THEN NOTIFY the Security Shift Supervisor immediately.
- 3.
Security personnel determine the type of security emergency that exists. Maintain contact between the Control Room and the Security Shift Supervisor.
- 4.
Do NOT delay off site notifications beyond the required time while implementing this enclosure.
- 5.
The following considerations are intended to aid in decision-making during each type of security emergency. Only one section applies unless multiple conditions exist.
SELECT the following condition(s) that apply, AND GO TO the appropriate section(s) of this enclosure.'
I.
Credible Thr'eat: Susoects (threat outside the Protected Area*
II.
Intruder penetrates Protected Area.
-Ill.
Confirmed Insider (Badged Employee)
P Rev. 71.a 6
6
.Page 46 of 63 EM-202
/ENCLOSURE 3
(Page2of5)
Credible Threat against the CR-3 Nuclear Plant Suspect (threat) Outside the Protected Area 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.'
"K.)
- 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. Is it a localized area versus larger scale area? What is the time frame of the threat (i.e., is there enough time to allow the staff to evacuate or would sending people onto the berm expose them to a threat)?
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.
Os e
fe
-5. Sepage 5 of 5 for Plant Op erations Considerations for large-s cale threats.
EM-22;'Rev. 71 EM-202 Page 47 of 63
ENCLOSURE3 (Page 3 of 5)
II.
Intruder(s) Penetrates Protected Area Security announces the Security Emergency directing personnel to take suitable cover immediately until an "All Clear" announcement is made. Additionally, Security may initiate a public address announcement directed toward the intruder(s).
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 Assembly Area or the Main Assembly "Area.
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. 71 Page 48 of 63
ENCLOSURE 3 (Page 4 of 5)
Confirmed Insider (Badged Employee)
Following a CREDIBLE NOTIFICATION of an insider, 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 plantvital areas. The individuals must remain in continuous visual contact unless personnel or plant safety will be adversely impacted.
- 3.
Direct Site 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 yital 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.
1 "Rev. 71
-g "III.
Page 49 of 63
,-EM-202
ENCLOSURE3 (Page 5 of 5)
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. Notify Dispatcher and inform them that CR-3 may be coming off-line in a controlled manner or possibly tripped due to actions caused by intruders.
- 3. 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.
- 4. 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.
- 5. 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.
- 6. 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.
"7. 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 servic'e 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 action.
"EM-202 Rev. 71 Page 50 of 63
I NRC FORM 361 (12-2000)
)RC OPS CENTER COMMUNICATOR REACTOR PLANT EVENT NOTIFICATION WORKSHEET
" EN#
- 1) Use ENS phone sticker number for NRC direct IF ENS IS OUT OF SERVICE, use 21 Commercial 1-301-816-5100 or 1-301-951-0550 or 1-301-415-0550 or 1-301-415-0553 NOTIFICATION TIME FACILITY UNIT -
NAME OF CALLER CALL BACK:
CRYSTAL RIVER 3,
ENS #700-821o0027
" "*Or
- 1-352-795-6958 EVENT TIME & ZONE EVENT DATE POWER I MODE BEFORE POWER I MODE AFTER EVENTCLASSIFICATIONS* *. [
1 -HOUR NON-EMERGENCY 50.72 (bXp1)
[I (v)(A) Safe SID Capability 0 GENERAL EMERGENCY 0 TS Deviation
[] (v)(B) RHR Capability El SITE AREA EMERGENCY
[6U3NN MERENCY50.72 (bX2)
Er (v)(C) Control of Radiological Release
[o ALERT
_[3 (i) TS Required S/D
[3 (v)(D) Accident Mitigation
[o UNUSUAL EVENT
[3 (iv)(A) ECCS Discharge to RCS 0 (xii) Offsite Medical 0l 50 72 NON-EMERGENCY (see next column) 0 (iv)(B) RPS Actuation 0 (x)01 Loss ComnVAsmtlResp
[I PHYSICAL SECURITY (73.71) 0l (xi) Offsite Notification
. 60-DAY OP1IONAL50.73 (5Xl)!<Y*
iY
[I MATERIALIEXPOSURE (20 2202)
B-HOUR NON-EMERGENCY 50.72(b)(3);
El Invalid Specified System Actuation r_ FITNESS FOR DUTY 0 (ii)(A) Degraded Condition Other Unspecifed RequiremFnt (Identifyg Y F
[]OTHER UNSPECIFIED REQMT (see last colurm) 0 ({)(B) Unanalyzed Condition 0
o INFORMATION ONLY El Specified System Actuation 0
EVENT DESCRIPTION Include Systems affected, actuations & their initiating signals, causes, effect of event on plant, actions taken or planned. etc (Continue on back)
I.R4NOTIFICATIONS '., 1YES 5 ýNO iýWlLLBE ANYTHING UNUSUAL OR NRC RESIDENT I
I
_I____NOT UNDERTOOD?
[I YES (Explain above) 0l NO I
-4--4 I
I ijirriiuuvi Dr4.s
MEDINPRESS RELEASE DID ALL SYSTEMS FUNCTION AS REQUIRED?
MODE OF OPERATION UNTIL CORRECTED YES ESTIMATED RESTART DATE El NO (Explain above)
SADDITIONAL INFO ON BACK 1 -YES 0 NO
'Page 51 of 63
,TATE LOCAL EM-202
--ENCLOSURE 4 S- (Page 1 of 4)
" Rev. 71
NOTIFICATION TIME ADDITIONAL INFORMATION I RADIOLOGICAL RELEASES Check or iIi Apphcabte ters (specific detailsexplanatons should be iovered in event description)
[o LIQUID RELEASE 0] GASEOUS RELEASE ol MONITORED E0 UNMONITORED o PERSONNEL EXPOSED OR CONTAMINATED
[I UNPLANNED RELEASE
[I PLANNED RELEASE 0 OFFSITE RELEASE 0 TS EXCEEDED 0 OFFSITE PROTECTIVE ACTIONS RECOMMENDED O'0 ONGOING.
0 TERMINATED
[I RM ALARMS 0 AREAS EVACUATED State release path in descnption
- Release Rates1mts
- Ii Release Rýkate o
L%
ODCMLlmutý otafActvii>
.ODCMimit U
- i Noble Gas Iodine Particulate Liquid (excduchng t"tium & dissolved noble gases)
Uquid (titium)
Total Activity
- '-' Plant.Srackd eCndeW/Ai Ejecl t,.mMaI ste'ar" Line
- Other (List)
~RAD MONITOR RE-ADINGS..~-
~
~
Y RAD MONITOR READINGS ALARM SETPOINTS
% ODCM UMIT IFAPPLICABLE)
RCS OR SG TUBE LEAKS CHECKO FILLIN APPUCABLE ITS- (SPECFIC DETAJLSEXPLANATIONS SHOULD BECOVERED IN EVENT DESCRIPTION)
LOCATION OF THE LEAK (E.G. SG#, VALVE, PIPE, ETC.)
LEAK RATE UNITS GPMIGPD T S. Umits
[I Sudden or 0 Long Term Development LEAK START DATE.
TIME:
COOLANT ACTIVITY. PRIMARY_
_ vCI/ML SECONDARY _
pCI/ML
) LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL EVENT DESCRIPTION (Contnued from front)
EC INITIALS DATE:________
Page 52 of 63 ENCLOSURE 4 (Page 2 of 4)
EM-202 Rev. 71
"ENCLOSURE 4 (Page 3 of 4)
NRC Operations Center Notification Protocols NOTE: The initial NRC notification may be performed using the information from Items 4 through 7 and Item 12 of the LORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM, in order to expedite notification from the Control K..Aoom. Use the form for subsequent notifications, unless continuous communication is established.
NOTIFY the NRC as soon as practicable after the State of Florida, but NO later than sixty minutes from declaration of an emergency condition.
NOTE: The NRC automatically records communications on the NRC Event Notification System (ENS).
USE the ENS telephone as primary means of communication and Commercial telephones as secondary means of communication. The ENS number is located on a sticker affixed to the telephone. The Commercial numbers are located on the REACTOR PLANT EVENT NOTIFICATION WORKSHEET.
ENSURE the appropriate sections of the REACTOR PLANT EVENT NOTIFICATION WORKSHEET are completed and, SSO/ EC approval has been granted before making the notification.
The communicator making the notification ensures the person receiving the report has an adequate understanding of the
-event and the related safety significance to ensure appropriate NRC response.
Include insight if known to the following: (information source)
- Is there any change to the classification of the event? If so, what is the reason? (Accident Assessment Coordinator)
- What is the ongoing / imminent damage to the facility, including affected equipment and safety features? (Accident Assessment Coordinator or Repairs Coordinator)
- Have toxic or radiological releases occurred or been projected, including changes in the release rate? If so, what are the projected on-site and off-site releases, and what is the basis of assessment? (Radiation Controls Coordinator)
- What are the health effect consequences to on-site I off-site people? How many on-site / off-site people are /will be affected and to what extent? (Radiation Controls Coordinator)
- Is the event under control? When was control established or what is the planned action to bring the event under, control? What is the mitigative action underway or planned? (Accident Assessment Coordinator)
- What on-site protective measures have been taken or planned? (Florida Nuclear Plant Emergency Notification Form)
- .What off-site protective actions have been recommended to State /County officials? (Florida Nuclear Plant Emergency Notification Form)
- What is the status of State County other Federal agencies responses, if known? (EOF Staff)
- -If applicable, what is the status of public information activities, such as siren,'broadcast, or press releases? Has the "Emergency News Center been activated? (EOF Staff)
RESPOND to any request for additional information that you can answer; otherwise, state that the information is NOT yet available and will be provided in a follow-up message. Any questions asked by the NRC and the associated responses given should be documented in writing and attached to the REACTOR PLANT EVENT NOTIFICATION WORKSHEET.
NOTE: For Alert or higher classifications, the Headquarters Operations Officer will be attempting to patch the Region II Administrator and other Region I1 personnel into the call concurrent with recording your message. You may be interrupted_
by patch-ins and / or requested to repeat information, and you should comply with these requests. If the Regional Administrator or deputy have NOT been patched in by the time you have completed your message, the Headquarters -
Operations Officer will probably request additional information.
,Upon declaration of an Alert or higher, the NRC Operations Center will most likely request the communicator stay on the line. If the notification originates from the Control Room, tell the NRC you are signing-off ENS. If requested to maintain an open communications line, notify the SSO / EC to provide an altemative communicator or take other action.,
"If an open communications channel is established, routine use of the form is NOT required, provided that verified changes in plant / equipment status are communicated to the NRC verbally and a summary of the communications with the NRC is maintained in the log.
,Jpon arrival of the NRC Site Response Team and with the concurrence of or at the request of the Headquarters Operations Officer, face-to-face communication begins between the FP NRC Liaison and the lead NRC representative at the TSC. This information includes emergency classification changes, Protective Action Recommendations changes, and the non emergency reporting requirements including invoking 10CFR50.54 (x)(y).
EM-202 Rev. 71 "Page 53 of 63
S......~
r "ENCLOSURE 4
"(Page 4 of 4)
SGuidance for Completing the Reactor Plant Event Notification Worksheet IOTE: The following items are completed at the time of the notification.
- Print the name of the Headquarters Operations Officer (HOO) in the NRC Operations Center Communicator space provided.
0 Print the Event Notificatior number (EN #) provided by the HOO in the space provided.
- Enter the notification time (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) provided by the HOO when communication is established.
- Provide the Call Back numbers as applicable.
NOTE: The following items are completed before the notification.
- Print the individual making the notification in the "Name of Caller" space provided.
- Enter the "Event Time and Zone (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock and EDT)," "Event Date (MM/DD/YY)," "Power / Mode Before," and "Power / Mode After."
-Enter the "Mode of Operation Until Corrected (numeric)" and "Estimated Restart Date (MM/DD/YY)" at the bottom of page. 1.
Event Classifications Section
- Check the applicable block for the current emergency classification.
1-Hour. 4-Hour, and 8-Hour Non-Emergency Sections
- Check all blocks that apply and are separate reportability items from the reason CR-3 has declared an emergency condition. The determination of these items is the responsibility of the TSC Accident Assessment Team Operations Support representative when the TSC is operational.
Event Description Section (additional space is provided on page 2 of form)
- Provide a clear and concise description of the event. Do NOT use plant-specific acronyms or abbreviations.
- Discuss each reportable event, as necessary.
"* Report the failure of significant components.
' Include those plant specific systems or components, which were available to perform the same function as any system or component that failed during the event.
- Include information which will promote understanding of the report, such as any extenuating circumstances (good or bad) or any related generic concerns within the industry.
I If the "Other" block was checked in the Event Classifications Section, provide amplifying information to explain this
- choice.
Notifications Section
- Check the appropriate box based on the notifications made before the notification to the NRC Operations Center. All are normally checked "Yes", except "Media / Press Release" for the initial notification.
"- "Other Govt Agencies" is Department of Health - Bureau of Radiation Control during a declared emergency.
Questions Posed by the Headquarters Operations Officer Section
- Be prepared to answer these questions based on the event and provide explanations in the "Description" section as applicable.
- Check appropriate box for"Additional Information on Back,.`".
Radiological Releases Subsection
- Check or fill-in applicable items based on information from the Radiation Controls Coordinator, logs, SWPT notification forms, and status boards and provide specific details / explanations in "Description" section.
RCS or SG Tube Leak Subsection
- Check or fill-in applicable items based on information from the Accident Assessment Coordinator, logs,,SWPT notification forms, and status boards and provide specific details / explanations in "Description" section.
"After the Emergency Coordinator or designee approves the REACTOR PLANT EVENT NOTIFICATION WORKSHEET, any "information added to or any changes to existing information requires re-approval before transmittal off-site unless continuous
-ommunication is established where the form is NOT required.,
k,*o correct an error on the form, drawi a single line through the error, enter the correct information, and initial and date.
Obtain SSO / EC approval of the NRC form before transmittal of the information unless continuous communication is established when the form is NOT required.
Rev. 71 P
5 o 6 Page 54 of 63 EMo202
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.
State that CR-3 is in a(n) LIEmergency LI' Drill
- 3.
"Sta~te cR.3has declared'a(n) UUnusual Event Alert U Site Area Emergency U General Emergency
- 4.
Briefly explain plant conditions using basic facts:
5.'
STATE if conditions are:
-IMPROVING" (Plant conditions are improving in the direction of a loweremergency classification ortermination of the event)..
L
-[
"STABLE" -(Plant conditions are NOT degrading and the emergency Is under control)
U DEG RADING" (Plantconditons continue to degrade and t is evident that the situation will worsen or a higher classification is inerne)
)
- 6.
STATE one of the following based on plant conditions:
SU !"NO RADIOACTIVE MATERIAL HAS BEEN RELEASED."
"U'"RADIOACTIVE MATERIAL IS BEING RELEASED AT LOW LEVELS" (when NO fuel is damaged)
."RADIOACTIVE MATERIAL IS BEING RELEASED."
- 7.
STATE one of the following based on declared emergency:
U IF UNUSUAL EVENT OR ALERT) "NO ASSEMBLY OR EVACUATION IS.NECESSARY AT THIS TIME."
U'(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."
U (General Emergency, NO release and release NOT likely within 3 hrs; see Enclbds're 7) "BEGIN STANDARD ASSEMBLY AND ACCOUNTABILITY. REFER TO THE CRYSTAL RIVER COAL PLANT SITE ACCOUNTABILITY/EVACUATION MANUAL. ONCE ACCOUNTABILITY IS S"
COMPLETE, NOTIFY CR-3 SECURITY AT EXTENSION 3258 OR 795-5078, AND EVACUATE "NON-ESSENTIAL PERSONNEL. STANDBY FOR FURTHER INSTRUCTION."
U (G6neral 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. 71 Page 55 of 63
"ENCLOSURE6 K>
Initiation of the-Emergency Response Dat5aSystem (ERDS)
[NOCS40730]
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 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. -
71)_
DEPRESS button "B" on the COMMANDER for ERDS deactivation.
.2)
ALT-TAB to ERDS Display
- 3)
DEPRESS ALT-C on thie keyboard.'
A series of messages will appear in the ERDS window. When the shut down is finished, the message "Shutdown Completed" is displayed.
Rev. 71 It Page 56 of 63 EM-202
S-.,.
r r
]=-*3*,*!
-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 Site 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 Site Security at extension 3258 or 795-5078.
"EVACUATE NON-essential personnel (including Main Assembly Area personnel).
KU ' -
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 ECGuide.
"3.
ENSURE Site Security coordinates'these protective action instructions to all areasof 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 evacuatiorl 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 K.>
during normal operations).
Page 57 of 63 Rev. 71 EM-202
-'
Evacu'tion Plani ng'Guide (Continued)
"Wind Direction Data K~ V~ N' b, -WN F, RM 0~ M' WVINDI FROM~&i~'
SECTORS~
~
D~IRECTION D GREE AFFEC-TED~
N 349-11(349-371)
-HJK NNE-12-33 (372-393)
J K L NE 34-56 (394-416)
KLM
-ENE 57-78 (417-438)
,LM N E
79-101 (439-461)
IM N P ESE
,102-123 (462-483)
N P Q SE P124-146 (484-506)
PQ R SSE 147-168(507-528)'
QRA S
- 169-191 (529-540)
RAB SSW 192-213 ABC SW 214-236 B C D WSW 237-258 C D E W
259-281 DEF
-,,WNW
'. -,282-303.
-EFG NW 304-326 F G H NNW 327-348 GHJ Page 58 of 63 ENCLOSURE 7 (Page 2 of 4)
I Rev. 71
' EM-202
II)
ENCLOSURE 7 (Page 3 of 4)
Evacuation Planning Guide (Cbntinued)
Contacts for Personnel Assembly
,p
""0Rev.
71 Pg59o6 Units 4 & 5 Control A
Units4 &5 Ro S....
Room B/C Nuclear Administration Building Public Address Nuclear System Units 4'& 5 Control B/C' North Coal Yard Room D
-I E
CR-3 Warehouse'Area cry
-D/E Site Administration Building Site Security D / E Mariculture Center Site Security'
- Coal Ti Yd
-Units 4 & 5'Control E/F/G/H CoalTrain.Yard Room
.J/K/L South Coal Yard Units 1 & 2 Control Room N
Units 1 & 2 1Units 1 & 2 Control
--U-.
.tsl&2' Room N
Ralston Purina Building Site Security EM-202
-Page 59 of 63
ENGLOSURE7 (Page 4 of 4) 349-it, 0000 ASHSTCAA ISSIA Tý Am U
ýMws' FACWTV C.4 CýA
'A CAL.
ýSff 304 ASM MAM MAD A.;l 61 SMSTATIIM AW" CA $a 3
ý TuRff esmTER AS 0
ýýKm C'kiaz CA-3 TIC 0
WAKE COW.Cft 1010 2sq*
2 0 141 COAL STVAAQ9 AREA 0 7 mues A
EM-202 Rev. 71 Page 60 of 6 3
"Guidelines for Protective Action Recommendations for Non-Essential Energy Complex Personnel and General Population
[NOCS 1128, 1592]
PLANT CONDITIONSIOFF-SITE DOSE ESTIMATES RECOMMENDED ACTION 0-5 MILES 5-10 MILES
- PARs within the first hour of an event should be based on PLANT CONDITIONS ONLY until the Dose Assessment Team Is operational.
i-?"
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 > 5.0 REMThyroid CDE.
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:V.F projected dose from an actual release is >1.0 REM TEDE or5 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. 71
'Page 61 of 63
- 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 R/hr; or
- c. PASS results.
- 2.
CONDITION:
GENERAL EMERGENCY DECLARED.
CLAD DAMAGEJGAS 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: 2:5.0 Rem
- 3.
CONDmON:
GENERAL EMERGENCY DECLARED.
CORE MELT OCCURRING OR LIKELY.
"CORE DAMAGE INDICATIONS-
- b. Core uncovered for > 30 minutes; or "c. RM-G29/30 reading > 75,000 R/hr (RB spray off) or > 25.000 R/hr (RB spray on).
WITH:
WITH:
Evacuate Zone 1 Shelter Zones 2 & 3 NO projected containment failure and NO release underway.
(See Note 2.)
(See Note 1.)
Evacuate Zone I Evacuate Zones 2 & 3 Projected containment failure and/or release underway.
(See Note 2.)
(See Note 2.)
(See Not 2.)"
(See Note 3.)
ENCLOSURE 8 S, (Page 1 of 2)
- 'V.-
e g I
- -
ENCLOSURE 8 (Page 2 of 2)
Guidelines for FP Emergency Worker Exposure CONDITION (RMTED
~ j G UIDANCE
- 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
_espirators.
- 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 e
, 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.
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).
Page 62 of 63 NOTE:
EM-202
-*Rev. 71
Iisbn Summary Revised item 3.1.15 intruder definition to clarify an insider versus an outsider and remove information about active and passive as this is determined by Site Security.
- Added new bullet under item 3.2.8 to identify approval of media releases by EC.
Added new responsibility ite'r 3.2.13 to recognize the Site'Security function during an emergency condition.
Revised 3.3.3 to allow the use of the Florida Nuclear Plant Emergency Notification Form for initial NRC notification to expedite the notification. This includes revising the EC Guide steps 4.1.9, 4.2.10, 4.3.11, and 4.4.12 to reflect use of the form.
Revised 3.3.5 to add a request to the PGM or EC On-Call to notify the EOF Director or the EC may establish a conference call.
Revised 3.3.7 to state any exceptions to transfer of turnover responsibilities to the EOF must be clearly communicated during turnover.
Added new item 3.3.10 as information moved from Enclosure 3.
Revised 4.0.7 to allow EC to establish a conference call with the EC On-Call and EOF Director.
Added new item 4.0.9 to discuss protocols for downgrading classifications.*
Added new item 4.0.10 to address the termination of an emergency and transition into the recovery phase (AR 61610-09).',
Revised 4.2.12, 4.3.14, and 4.4.15 to notify ANI and added new steps 4.2.13, 4.3.15, and 4.4.16 to notify NEIL during a declared emergency.
Revised steps 4.2.16, 4.3.20, and 4.4.20 to add ANI to termination notification.
Revised renumbered steps 4.2.15 and 4.3.17 to address downgrading of an emergency classification by consulting with the EC On-Call and EOF Director.
Changed Licensing title to Licensing/Regulatory Programs Unit on all applicable steps.
-. Added new steps 4.3.18, 4.3.19, 4.4.18, and 4.4.19 to address termination of an emergency condition (AR 61610-09). This includes removing the termination criteria and referencing the REP-03 location.
Revised FPB Matrix, Loss of Fuel Clad EAL #2, to add DEl'and make consistent with NEI
- guidance (AR 67792-05).,
Revised Enclosure 2 notification protocols and guidance for completing the form to address human performance concerns from drills/exercises, and training (ARs 62155-05, 58882-07,.
59192-05).
Revised the.Release Significance Categories PAG description to address spent fuel damage (AR 64285-05) and revised Clad Failure Lost condition of table to Clad Barrier Lost.
Revised Enclosure 3 to address logical progression through Security-related emergencies based on Simulator feedback. The contents have remained the same for each section, just the order has changed. Added new item 2 under "Plant Operations Consideration" to-notify the Dispatcher and inform them when the pleit is being taken off-line and renumbered remaining items.
Revised Enclosure 4 to add NRC Operations Center notification protocols and guidance for
-completing the NRC form (AR 61583-09). Minor changes made to worksheet.
Revised Enclosure 5 to add check boxes for ease of use and added description for plant conditions."
Replaced Enclosure 7 sector map with updated version.
Replaced reference to Corporate Security with Site Security throughout the procedure based on organizational responsibility changes.
EM-202 Rev. 71 Page 63 of 63