ML14311A641

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Radiological Emergency Response Plan, Revision 045
ML14311A641
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Site: Callaway Ameren icon.png
Issue date: 08/31/2014
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Attachment 2 to ULNRC-06140 September 23, 2014 CALLAWAY PLANT RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP)

Revision 045 August 2014

CALLAWAY PLANT RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP)

Revision 045 August 2014 Page 1 of 139

RERP Rev. 045 RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP)

TABLE OF CONTENTS Section Page Number 1.0 GLOSSARY ................................................................................................................................... 7 1.1. Definitions ........................................................................................................................... 7 1.2. Acronyms and Abbreviations ............................................................................................. 16 2.0 SCOPE AND APPLICABILITY ................................................................................................ 18 2.1. Purposes and Objectives .................................................................................................... 18 2.2. Planning Description .......................................................................................................... 18 2.3. Plan Interrelationships ........................................................................................................ 19 3.0

SUMMARY

OF THE CALLAWAY PLANT EMERGENCY PREPAREDNESS PROGRAM.................................................................................................................................. 20 3.1. Radiological Emergency Response Plan (RERP)................................................................ 20 3.2. Emergency Implementing Procedures (EIP)s ..................................................................... 22 3.3. Maintenance of the Emergency Preparedness Planning Program ........................................ 23 4.0 EMERGENCY CONDITIONS ................................................................................................... 24 4.1. Emergency Classifications ................................................................................................. 25 4.2. Spectrum of Postulated Accidents ...................................................................................... 27 4.3. Detection of Postulated Accidents ...................................................................................... 30 TABLE 4-1, Emergency Action Level Classification Matrix .................................................................... 31 5.0 ORGANIZATIONAL CONTROL OF EMERGENCIES ......................................................... 34 5.1. On-Shift Emergency Response (Figure 5-1, Table 5-1) ...................................................... 35 5.1.1. Shift Manager ......................................................................................................... 35 5.1.2. Operating Supervisor .............................................................................................. 35 5.1.3. Operations Personnel .............................................................................................. 36 5.1.4. Other Operations Personnel .................................................................................... 36 5.1.5. Chemistry Technician ............................................................................................. 36 5.1.6. HP Operations Technician ...................................................................................... 37 5.1.7. Health Physics Technical Support (HPTS) Technician............................................ 37 5.1.8. Shift Security Supervisor ........................................................................................ 37 5.1.9. Security Force ........................................................................................................ 37 5.1.10. Control Room Communicator................................................................................. 37 5.1.11. Emergency Teams .................................................................................................. 38 5.2. Emergency Response Organization (Figure 5-2, Table 5-2)................................................ 39 5.2.1. Emergency Coordinator (EC) (Minimum Staffing) .................................................. 39 5.2.2. Operations Group ................................................................................................... 40 5.2.3. Operations Support Group ...................................................................................... 40 5.2.4. Technical Assessment Group.................................................................................. 41 Page 2 of 139

RERP Rev. 045 RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP)

TABLE OF CONTENTS Section Page Number 5.2.5. Health Physics Group ............................................................................................. 41 5.2.6. TSC Communicator (Minimum Staffing) ................................................................ 42 5.2.7. Security .................................................................................................................. 42 5.2.8. Administrative Support Group ................................................................................ 42 5.2.9. Recovery Manager (RM) (Minimum Staffing)......................................................... 43 5.2.10. Protective Measures Group..................................................................................... 43 5.2.11. Logistical Support Group ....................................................................................... 44 5.2.12. Off-site Liaison Coordinator (OSL) ........................................................................ 45 5.2.13. EOF Communicator (Minimum Staffing) ................................................................ 45 5.2.14. The Joint Public Information Group ....................................................................... 45 5.3. Emergency Response Organization Support ....................................................................... 46 5.3.1. Private Sector Organizations................................................................................... 46 5.3.2. Governmental Organizations .................................................................................. 46 FIGURE 5-1, On-Shift Emergency Response ........................................................................................... 51 FIGURE 5-2, Emergency Response Organization (On-Site) ..................................................................... 52 FIGURE 5-3, Functional Interfaces Of Emergency Response Organizations ............................................ 55 TABLE 5-1, Emergency Staffing Requirements / On-Shift Emergency Response + .................................. 56 TABLE 5-2, Emergency Staffing Requirements / Emergency Response Organization (On-Site/TSC) ...... 57 6.0 EMERGENCY MEASURES ...................................................................................................... 63 6.1. Recognition and Evaluation ............................................................................................... 63 6.2. Classification and Declaration ............................................................................................ 63 6.3. Notification ........................................................................................................................ 64 6.3.1. Emergency Coordinator (TSC) ............................................................................... 64 6.3.2. Nuclear Regulatory Commission (NRC) ................................................................. 64 6.3.3. State and Local Notification Points ......................................................................... 65 6.4. Mobilization ...................................................................................................................... 66 6.5. Assessment Actions ........................................................................................................... 67 6.5.1. Assessment Action for Control of Plant Operations ................................................ 67 6.5.2. Environmental Assessment for Protection of Health and Safety of the Public ......... 68 6.5.3. In-Plant Radiological Controls................................................................................ 69 6.5.4. Reactor and Core Damage Assessment ................................................................... 70 6.6. Corrective Actions ............................................................................................................. 70 6.7. Protective Actions .............................................................................................................. 70 6.7.1. Protective Actions for Plant Personnel .................................................................... 70 6.7.2. Off-Site Alerting and Protective Actions ................................................................ 73 Page 3 of 139

RERP Rev. 045 RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP)

TABLE OF CONTENTS Section Page Number 6.7.3. Use of On-Site Protective Equipment and Supplies ................................................. 75 6.7.4. Contamination Control Measures............................................................................ 76 6.8. Aid to Affected Personnel .................................................................................................. 76 6.8.1. Emergency Response Personnel Exposure Criteria ................................................. 76 6.8.2. Decontamination and First Aid ............................................................................... 77 6.8.3. Medical Transportation........................................................................................... 77 6.8.4. Medical Treatment ................................................................................................. 77 6.9. Public Information ............................................................................................................. 77 6.9.1. Public Information During Emergencies ................................................................. 77 6.9.2. Rumor Control ....................................................................................................... 78 FIGURE 6-1, Field Monitoring Team Map Composite (All Sections) ...................................................... 79 TABLE 6-1, Assessment Actions ............................................................................................................. 80 TABLE 6-2, Protective Action Guidelines Plume Phase (Early Phase) General Population ...................... 81 TABLE 6-3, Post Plume Phase (Intermediate And Late Phases) Recommended Protective Actions .......... 82 TABLE 6-4, Food Chain Considerations Recommended Protective Actions 1,2 ......................................... 83 7.0 EMERGENCY RESPONSE FACILITIES AND EQUIPMENT .............................................. 84 7.1. Emergency Response Facilities .......................................................................................... 84 7.1.1. Control Room (CR) ................................................................................................ 84 7.1.2. Technical Support Center (TSC) (Figure 7-1) ......................................................... 85 7.1.3. Emergency Operations Facility (EOF) (Figure 7-2) ................................................ 86 7.1.4. Joint Public Information Center (JPIC) ................................................................... 86 7.1.5. Corporate Headquarters Support ............................................................................. 86 7.1.6. County/City Emergency Operations Centers (EOC)s .............................................. 87 7.1.7. State Emergency Operations Center (EOC) ............................................................ 87 7.1.8. Ameren Corporate Communications ....................................................................... 87 7.2. Communications Systems .................................................................................................. 88 7.2.1. Public Address (PA) System................................................................................... 88 7.2.2. Touchtone Telephone System ................................................................................. 88 7.2.3. Communication Systems ........................................................................................ 89 7.2.4. Sentry..................................................................................................................... 90 7.2.5. Back-Up Radio System (BURS) ............................................................................. 90 7.2.6. State and Local Forward Command Post ................................................................ 90 7.2.7. Radio Communication Systems .............................................................................. 90 7.2.8. Emergency Communications with the NRC ............................................................ 90 7.3. Assessment Equipment ...................................................................................................... 92 Page 4 of 139

RERP Rev. 045 RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP)

TABLE OF CONTENTS Section Page Number 7.3.1. On-Site Systems and Equipment ............................................................................. 92 7.3.2. Facilities and Equipment for Off-Site Monitoring ................................................... 98 7.4. Protective Facilities and Equipment ................................................................................... 98 7.5. Decontamination Facilities and Supplies ............................................................................ 99 7.6. Medical and First Aid ........................................................................................................ 99 7.7. Damage Control Equipment and Supplies .......................................................................... 99 FIGURE 7-1, Technical Support Center ................................................................................................. 100 FIGURE 7-2, Emergency Operations Facility ........................................................................................ 101 FIGURE 7-3, Emergency Response Facility Locations .......................................................................... 102 FIGURE 7-4, Backup Emergency Response Operations Facility ............................................................ 103 8.0 MAINTAINING EMERGENCY PREPAREDNESS .............................................................. 104 8.1. RERP Training ................................................................................................................ 104 8.1.1. RERP Training for On-site Personnel ................................................................... 104 8.1.2. RERP Training for Off-site Personnel .................................................................. 106 8.1.3. News Media Orientation ....................................................................................... 106 8.1.4. Public Information Program ................................................................................. 107 8.2. Drills and Exercises ......................................................................................................... 107 8.2.1. Communications Drills ......................................................................................... 109 8.2.2. Medical Emergency Drill ..................................................................................... 109 8.2.3. Radiological Monitoring Drills ............................................................................. 109 8.2.4. Health Physics Drills ............................................................................................ 109 8.2.5. Fire Drills ............................................................................................................. 109 8.2.6. Security Based Event Drill (COMN 50110, ULNRC-05189) ................................. 109 8.3. Review and Updating of the RERP and EIPs.................................................................... 110 8.4. Review and Updating of the Emergency Preparedness Program ....................................... 110 8.5. Maintenance and Inventory of Emergency Equipment and Supplies ................................. 111 8.6. Emergency Preparedness (EP) Organization..................................................................... 111 9.0 RECOVERY .............................................................................................................................. 113 9.1. Transition from Emergency Operations to Recovery Operations ...................................... 113 9.2. Recovery Organization..................................................................................................... 114 9.2.1. Recovery Manager (RM) ...................................................................................... 114 9.2.2. Operations Coordinator ........................................................................................ 114 9.2.3. Engineering Coordinator ...................................................................................... 114 9.2.4. Work Control Coordinator .................................................................................... 115 9.2.5. Licensing and Fuels Coordinator .......................................................................... 115 Page 5 of 139

RERP Rev. 045 RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP)

TABLE OF CONTENTS Section Page Number 9.2.6. Radiological Assessment Coordinator .................................................................. 115 9.2.7. Administrative Services Coordinator .................................................................... 115 9.2.8. Public Information................................................................................................ 115 9.2.9. Additional Support ............................................................................................... 115 9.3. Objectives of the Recovery Organization ......................................................................... 116 9.3.1. Short-Term Objectives ......................................................................................... 116 9.3.2. Long-Term Objectives .......................................................................................... 116 9.4. Concept of Operations ..................................................................................................... 116 9.5. Reentry ............................................................................................................................ 116 9.6. Exposure Control ............................................................................................................. 117 9.7. Restoration....................................................................................................................... 117 FIGURE 9-1, Suggested Recovery Organization .................................................................................... 118 APPENDIX A, NUREG-0654/ Callaway Plant Radiological Emergency Response Plant (RERP)

Cross-Reference .......................................................................................................................... 119 APPENDIX B, Policy Statement Scope Of Authority And Responsibility Of Emergency Coordinator And The Recovery Manager ........................................................................................................ 128 APPENDIX C, Letters Of Agreement .................................................................................................... 129 APPENDIX D, Deleted, Rev. 017, 01/94 (See 6.7.2.1, Alerting The General Public) ............................. 130 APPENDIX E, Deleted, Rev. 017, 01/94 (See 6.7.3, Use Of On-Site Protective Equipment And Supplies)...................................................................................................................................... 131 APPENDIX F, List Of Emergency Plan Implementing Procedures (EIPS) ............................................. 132 APPENDIX G, Evacuation Time Estimate For The Callaway Nuclear Plant Emergency Planning Zone ............................................................................................................................................ 133 APPENDIX H, Public Alert System....................................................................................................... 134 TABLE H-1, Alert Systems For Specific Population Segments .............................................................. 135 FIGURE H-1, Public Alert System Siren Coverage................................................................................ 136 FIGURE H-2, Access Control Points ..................................................................................................... 137 APPENDIX I, List Of Supporting Radiological Emergency Response Plans .......................................... 138 APPENDIX J, Callaway Plant - On-Shift Staffing Analysis Report ....................................................... 139 Page 6 of 139

RERP Rev. 045 RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP) 1.0 GLOSSARY 1.1. Definitions Accountability - The process of identifying personnel remaining in the Protected Area following an assembly or site evacuation.

Affecting Safe Shutdown - Event in progress has adversely affected functions that are necessary to bring the plant to and maintain it in the applicable HOT or COLD SHUTDOWN condition. Plant condition applicability is determined by Technical Specification LCOs in effect.

Example 1: Event causes damage that results in entry into an LCO that requires the plant to be placed in HOT SHUTDOWN. HOT SHUTDOWN is achievable, but COLD SHUTDOWN is not. This event is not AFFECTING SAFE SHUTDOWN.

Example 2: Event causes damage that results in entry into an LCO that requires the plant to be placed in COLD SHUTDOWN. HOT SHUTDOWN is achievable, but COLD SHUTDOWN is not. This event is AFFECTING SAFE SHUTDOWN.

ALERT - Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guide exposure levels. (COMN 50110, ULNRC-05189)

Assembly - The process of reporting to designated buildings outside the Protected Area to evaluate personnel resources and accountability.

Assessment Actions - Steps taken during or after an accident to obtain and process information necessary to make decisions in order to implement specific protective and/or corrective actions.

Automated Calling System - Automated calling service provided by a vendor. This system is a backup to the Sirens and Tone Alert Radios for notifying the general public. In addition, the system can also be used as a backup to the Cellular Paging System for notifying selected ERO personnel.

Backup Emergency Operations Facility (BEOF) - Alternate facility for the EOF, set up in the States Emergency Operations Center (EOC) at the Ike Skelton Training Site southeast of Jefferson City, Missouri.

Bomb - Refers to an explosive device suspected of having sufficient force to damage plant systems or structures.

Cellular Paging System - A commercially provided cellular notification service capable of delivering alphanumeric messages to pre-designated personal notification devices (e.g.,

pagers, cell phones, etc.) carried by Emergency Response Duty Personnel. Messages are initiated by on-shift personnel via the paging service.

Civil Disturbance - A group of people violently protesting station operations or activities at the site.

Page 7 of 139

RERP Rev. 045 Committed Dose Equivalent (CDE) - The dose equivalent to organs or tissues of reference that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

Committed Effective Dose Equivalent (CEDE) - The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues.

Containment Closure - Is the action to secure Containment as a functional barrier to fission product release during cold shutdown conditions. Containment closure means that all potential escape paths are closed or capable of being closed (ref. 3.1.6). Containment Closure exits if, for each containment penetration (ref. 3.1.7)

1. The system associated with the penetration is in service providing pressure or providing a water seal to prevent escape of Containment atmosphere to outside of containment, or
2. The inside containment isolations of a penetration are in their required state or the outside Containment isolations of the penetrations are in the required state, or
3. Alternate means of isolating at least one side of a penetration have been established per OSP-GT-00003 Attachment 6, or
4. Administrative controls have been established to isolate a breached penetration when required as described in OSP-GT-00003 Attachment 7.

Contiguous - Being in actual contact; touching along a boundary or at a point.

Control Room (CR) - The area located on the 2047'-6" elevation of the Control Building from which the reactor and its auxiliary systems are controlled.

Corrective Actions - Emergency measures taken to mitigate or terminate an emergency situation at or near the source of the problem.

Deep Dose Equivalent (DDE) - The dose equivalent at a tissue depth of 1 cm.

Department of Health (DOH) - A department of the State responsible for evaluating the effects of a radiological emergency on the population at risk.

Desired Numbers - As this term appears in Table 5-2, it is the complete or full staffing of the organization (all positions filled with the optimum number of responders) so as not to be confused with minimum staffing or numbers.

Dose Equivalent (DE) - The product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest. The unit of dose equivalent is the rem.

Drill - A supervised instruction period aimed at testing, developing, and improving skills.

Duty - Rotating on-call coverage, scheduled around the clock, to ensure response during off normal working hours.

Duty Manager (DM) - A designated member of the Callaway Plant management staff who is assigned the responsibility of being the initial contact for problems when the Shift Manager needs guidance during normal plant operations.

Emergency Action Levels (EAL)s - Predetermined conditions or values which, when exceeded, require implementation of the Radiological Emergency Response Plan (RERP).

Page 8 of 139

RERP Rev. 045 Emergency Classifications - The grouping of emergency situations into four (4) mutually exclusive categories, allowing for proper emergency response. The four categories are utilized industry-wide and in this RERP as follows: (1) UNUSUAL EVENT, (2) ALERT, (3) SITE AREA EMERGENCY, and (4) GENERAL EMERGENCY.

Emergency Communications Center (ECC) - A designated facility designed and equipped to handle incoming and outgoing communications for a County Emergency Operations Center.

Emergency Coordinator (EC) - The designated on-site individual having the responsibility and authority to implement the Callaway Plant RERP, and who will coordinate efforts to limit consequences of the emergency, and bring it under control. The Shift Manager is considered the Emergency Coordinator (SM) until relieved by the Emergency Coordinator (TSC).

An Emergency Coordinator (TSC) is on-call 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 days a week.

Emergency Operations Center (EOC) - A State or county facility designed and equipped coordination and control over emergency operations within their jurisdiction.

Emergency Operations Facility (EOF) - An off-site emergency response facility for management of overall Callaway Plant emergency response. This response includes coordination with off-site authorities, coordination of radiological and environmental assessment, and determination of recommended protective actions for the public. The personnel that respond to the EOF are mobilized at the ALERT (or higher) classification.

Emergency Planning Zone (EPZ) - The area around the Plant which is defined to facilitate off-site emergency planning for a finite emergency response base. There are two areas for which EPZs apply. These areas are: (1) Plume Exposure Pathway EPZ, and (2) Ingestion Exposure Pathway EPZ.

Emergency Plan Implementing Procedures (EIP)s - Specific procedures providing actions required to put into effect the provisions of the RERP in order to mitigate and/or terminate the emergency situation. Procedures addressing maintenance of emergency preparedness are also included. Emergency Plan Implementing Procedures are numbered as EIP-ZZ-XXXXX, where X is an alphanumeric character.

Emergency Response Facility (ERF) - A collective name for specifically designated locations which are equipped to facilitate the control and coordination of emergency activities and assessment.

Emergency Response Organization - An organization that has been established to provide technical and logistical direction in the event of a radiological emergency declaration at the Callaway Plant. This organization is structured to provide Plant control and coordination of on-site response, coordination of off-site response and dissemination of information to the public.

Emergency Response Personnel - Pre-designated Personnel, including Minimum Staffing, who staff the Emergency Response Facilities to make them capable of fulfilling all intended emergency functions.

ERF Activation - When the ERF is ready to accept respective functions from the Control room (On-shift Emergency Response). These functions include classifications, notifications, dose assessment, protective action recommendations, technical assessment, communications, radiological controls, and emergency repairs.

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RERP Rev. 045 Essential Personnel - Personnel who are filling an emergency response position or providing support to an emergency response organization.

Event Closeout - The condition declared after Emergency Action Level (EAL) closeout criteria has been met. This condition initiates the transition from emergency operations back to normal operations. Event closeout is typically declared after response to an UNUSUAL EVENT or ALERT has been completed.

Exclusion Area - The area that encompasses the land surrounding the Plant to a radius of 1,200 meters (3,937 feet) from the midpoint of the Unit 1 Reactor Building and the canceled Unit 2 Reactor Building. Control of access to this area is by virtue of ownership and in accordance with 10CFR100.

Exclusion Area Boundary (EAB) - The border of the Exclusion Area.

Exercise - An observed evaluation that tests the integrated capability of the Emergency Response Organization as well as a major portion of the basic elements of the Radiological Emergency Response Plan.

Explosion - Is a rapid, violent, unconfined combustion, or catastrophic failure of pressurized/energized equipment that imparts energy of sufficient force to potentially damage permanent structures, systems, or components.

Faulted - In a steam generator, the existence of secondary side leakage that results in an uncontrolled lowering in steam generator pressure or the steam generator being completely depressurized.

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.

Fission Product Barriers (FPB) - Multiple physical barriers any one of which, if maintained intact, precludes the release of significant amounts of radioactive fission products to the environment. The FPBs are the Reactor Fuel Clad (FC), Reactor Coolant System (RCS) and Containment (CMT).

GENERAL EMERGENCY - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels off-site for more than the immediate site area. (COMN 50110, ULNRC-05189)

Health Physics - The terms Health Physics and Radiation Protection have the same meaning and may be used interchangeably in the RERP, EALs, and procedures.

Hostage - Person(s) held as leverage against the station to ensure that demands will be met by the station.

Page 10 of 139

RERP Rev. 045 Hostile Action - An act toward a Nuclear Power Plant or its personnel that includes the use of violent force to destroy equipment, take hostages, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included. Hostile Action should not be construed to include acts of civil disobedience or felonious acts that are not a part of a concerted attack on the Nuclear Power Plant. Non-terrorism based EALs should be used to address such activities, (e.g. violent acts between individuals in the owner controlled area). (COMN 50110, ULNRC-05189)

Hostile Force - One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.

Immediately Adjacent - Contiguous.

Immediately Dangerous to Life and Health (IDLH) - A condition that either poses an immediate threat to life and health or an immediate threat of severe exposure to contaminants which are likely to have adverse delayed effects on health.

Imminent - Mitigation actions have been ineffective, additional actions are not expected to be successful, and trended information indicates that the event or condition will occur. Where Imminent timeframes are specified, they shall apply.

Ingestion Exposure Pathway EPZ - The area within a 50-mile radius of the Callaway Plant in which people may be indirectly exposed to radiation by eating or drinking contaminated food, milk, and water.

Inoperable - Not able to perform its intended function.

Intruder - Person(s) present in a specified area without authorization.

Intrusion - The act of entering without authorization. Discovery of a bomb in a specified area is indication of intrusion into that area by a hostile force.

Joint Public Information Center (JPIC) - An off-site Emergency Response Facility from which coordinated news releases can be issued and news media briefings can be held. The JPIC is normally mobilized at the ALERT or higher classification levels.

Low Population Zone (LPZ) - A 2 1/2 mile circular area immediately surrounding the Plant which contains residents, the total number and density of which are such that there is a reasonable probability that appropriate protective actions could be taken on their behalf in the event of a serious accident.

Lower Flammability Limit (LFL) - The minimum concentration of a combustible substance that is capable of propagating a flame through a homogenous mixture of the combustible and a gaseous oxidizer.

Maintain - Continuously control a parameter to some required guideline. Example:

MAINTAIN steam generator levels at 50% (45%-55%).

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RERP Rev. 045 Minimum Staffing - Pre-designated Emergency Response Personnel assigned to activate the Technical Support Center and the Emergency Operations Facility sufficiently to relieve Control Room personnel of emergency functions not directly related to operation of the Plant.

Minimum Staffing personnel are designated on a rotating basis to be available for mobilization via the Cellular Paging System. When designated on duty, personnel must remain fit for duty and within their designated response time of the Plant.

Mobilization - The process of staffing the Emergency Response Facilities. This includes announcements over the Plant Gai-tronics system and activation of the Cellular Paging System.

Non-Essential Personnel - All personnel who are not actively filling an emergency response position or providing support to the Emergency Response Organization.

Normal Plant Operations - Activities at the plant site associated with routine testing, maintenance, or equipment operations, in accordance with normal operating or administrative procedures. Entry into abnormal or emergency operating procedures, or deviation from normal security or radiological controls posture, is a departure from Normal Plant Operations.

Normal Working Hours - Current standard core hours per Company and Plant policies and procedures. Off hours are the remaining hours in the week, including weekends and holidays.

Off-site - Any area outside of the Protected Area fencing.

On-site - Any area located within the Protected Area fencing.

Operable - Able to perform its intended function.

Owner Controlled Area - The fenced area contiguous to the Protected Area, designated by Callaway Plant to be controlled for security purposes.

Personnel Monitoring Devices - Any device designed to be worn or carried by an individual for the purpose of measuring the radiation exposure received, such as film badges, self-reading dosimeters, thermoluminescent dosimeters, optically stimulated luminescent dosimeters, etc.

Physically Operable - Plant systems, equipment, or devices shall be physically operable when they are capable of performing their specific function, regardless of Technical Specifications criteria, and could be available for use during emergency operations.

Plant Operating Procedures - A set of procedures to be used to provide the guidance and control of the Plant operation.

Plume Exposure Pathway EPZ - The area around the Plant where the principal exposure would be from external and inhalation exposure of radioactive materials from a passing plume. This area applies to an area around the Plant out to a radius of about 10 miles.

Projected Dose - A calculated or estimated total effective dose equivalent which affected populations may potentially receive if protective actions are not taken.

Projectile - An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.

Protected Area - The area encompassed by physical barriers and to which access is controlled by Security. The Callaway Plant Protected Area includes all areas within the security fence that immediately surround the major Plant structures (i.e., Reactor Building, Auxiliary Building, Turbine Building, Service Building, and Fuel Building).

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RERP Rev. 045 Protective Actions - Emergency measures taken to prevent or minimize radiological exposure (i.e., sheltering, evacuation).

Protective Action Guides (PAG)s - Projected TEDE or CDE values to individuals in the general population and to emergency workers that warrant protective action before or after a release of radioactive material.

Radiation Protection - The terms Radiation Protection and Health Physics have the same meaning and may be used interchangeably in the RERP, EALs, and procedures.

Radiological Controlled Area (RCA) - The area of the Plant where access is controlled for the purpose of protection of personnel from exposure to radiation and radioactive materials.

This area includes the Auxiliary Building, Containment Building, Radwaste Building, Fuel Building, and Laundry and Decon Facility.

Radiological Emergency Response Plan (RERP) - The document which establishes concepts and mechanisms that, when implemented during emergencies, provides safety and dose savings measures for site personnel and the general public.

Recovery - The condition declared after the immediate hazards to life and safety due to the emergency have been removed and efforts are directed to returning affected areas to normal operations.

Recovery Operations - Actions taken after the emergency to restore the Plant as nearly as possible to its pre-emergency condition.

Recovery Manager - The individual who has overall command and control of the entire Callaway Plant emergency response.

Reduced Inventory Condition - Plant condition when fuel is in the reactor vessel and Reactor Coolant System level is lower than 3 feet below the Reactor Vessel flange

(< 64.0 in.). (OTG-ZZ-00007 Refueling Preparation, Performance and Recovery)

Reentry - Return of personnel into areas evacuated due to Plant conditions during a radiological emergency.

Response Time Goal - The expected time that expires from emergency declaration to the responder arriving at the Emergency Response Facility (ERF).

Restore - Return to a former original condition. Used to require the reinstatement of a system or broad function to a pre-tripped or a ready/standby condition (ref. 3.1.9).

Ruptured - In a steam generator, existence of primary-to-secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.

Sabotage - Deliberate damage, misalignment, or mis-operation of plant equipment with the intent to render the equipment inoperable. Equipment found tampered with or damaged due to malicious mischief may not meet the definition of Sabotage until this determination is made by security supervision.

Safe Plant Shutdown - Hot or cold shutdown (reactor subcritical) with control of coolant inventory and decay heat removal.

Security Condition - Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A Security Condition does NOT involve a Hostile Action.

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RERP Rev. 045 Sentry - A computerized notification system linked between the Callaway Plant, the State Emergency Management Agency and the four (4) EPZ risk counties. It allows the Communicator to fill out a notification form on screen and transmit the data simultaneously.

Notifications on Sentry can be initiated from the Control Room, the Emergency Operations Facility (EOF), or the Technical Support Center (TSC).

Severe Accident Management Guidelines (SAMG) - Guidelines and aids that incorporate strategies for decision making for responding to and recovering from a severe accident condition beyond normal operating and emergency procedures.

Shift Manager - The terms Shift Manager and Shift Supervisor have the same meaning and may be used interchangeably in the RERP, EALs, and procedures.

Significant Transient - An unplanned event involving any of the following:

  • Automatic turbine runback > 25% thermal reactor power
  • Electrical load rejection > 25% full electrical load
  • Safety injection activation
  • Thermal power oscillations > 10%

SITE AREA EMERGENCY (or SITE EMERGENCY) - The terms Site Emergency or Site Area Emergency have the same meaning and may be used interchangeably in the RERP, EALs and procedures. Events are in progress or have occurred which involve an actual or likely major failure of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment 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 beyond the site boundary. (COMN 50110, ULNRC-05189)

Site Boundary - Exclusion Area Boundary is a synonymous term for Site Boundary. The Exclusion Area is defined as the area that encompasses the land surrounding the Plant to a radius of 1,200 meters (3,937 feet) from the midpoint of the Unit 1 Reactor Building and the canceled Unit 2 Reactor Building. Control of access to this is by virtue of ownership and in accordance with 10CFR100.

Site Evacuation - A controlled, pre-planned evacuation, which can be initiated by the Emergency Coordinator, that ensures all non-essential personnel are safely and expeditiously evacuated from the Callaway Plant Exclusion Area.

State - The State of Missouri.

Strike Action - Work stoppage within the protected area by a body of workers to enforce compliance with demands made on Callaway. The strike action must threaten to interrupt Normal Plant Operations.

Support Area - Area of the Technical Support Center (TSC) used to assemble manpower for emergency team formation.

Sustained - Prolonged. Not intermittent or of a transitory nature.

Page 14 of 139

RERP Rev. 045 Technical Support Center (TSC) - An on-site Emergency Response Facility for centralized control and coordination of on-site emergency response. This response includes the Support Area. The personnel that respond to the TSC are mobilized at the ALERT (or higher) classification.

Total Effective Dose Equivalent (TEDE) - The sum of the deep dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).

Trip - Manually activate a semi-automatic feature. Direct the operator to manually actuate a control which will cause the associated device to cease operation. Example: TRIP Breaker NB0211 (ref. 3.1.9).

Uncontrolled - An evolution lacking control, but is not the result of operator action.

Unisolable - A breach or leak that cannot be promptly isolated.

Unplanned - A parameter change or an event that is not the result of an intended evolution and requires corrective or mitigative actions.

UNUSUAL EVENT (or NOTIFICATION OF UNUSUAL EVENT) - The terms Unusual Event or Notification of Unusual Event have the same meaning and may be used interchangeably in the RERP, EALs, and procedures. Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection have been initiated. No release of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs. (COMN 50110, ULNRC-05189)

Valid - An indication, report, or condition, is considered to be VALID when it is verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant personnel, such that doubt related to the indicators operability, the conditions existence, or the reports accuracy is removed. Implicit in this definition is the need for timely assessment.

Visible Damage - Damage to equipment or structure that is readily observable without measurements, testing, or analysis. Damage is sufficient to cause concern regarding the continued operability or reliability of affected safety structure, system, or component.

Example damage includes: deformation due to heat or impact, denting, penetration, rupture, cracking, paint blistering. Surface blemishes (e.g., paint chipping, scratches) should not be included.

Vital Area - Any plant area which contains vital equipment. Any area, normally within the protected area, which contains equipment, systems, components, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

Page 15 of 139

RERP Rev. 045 1.2. Acronyms and Abbreviations ANI .......................American Nuclear Insurers CDE .....................Committed Dose Equivalent CEDE .................Committed Effective Dose Equivalent CFR ......................Code of Federal Regulations CR ........................Control Room CTMT ................Containment DAC.....................Dose Assessment Coordinator DDE .....................Deep Dose Equivalent DE .........................Dose Equivalent DM ........................Duty Manager DOE .....................Department of Energy DOH ....................Department of Health EAB .....................Exclusion Area Boundary EAL......................Emergency Action Level EAS ......................Emergency Alert System EC ..........................Emergency Coordinator ECC......................Emergency Communications Center ENS ......................Emergency Notification System EOC .....................Emergency Operations Center EOF ......................Emergency Operations Facility EPA ......................Environmental Protection Agency EIP ........................Emergency Plan Implementing Procedure EPZ.......................Emergency Planning Zone ETC ......................Emergency Team Coordinator FCP .......................Forward Command Post FEMA ................Federal Emergency Management Agency FSAR ..................Final Safety Analysis Report GET......................General Employee Training HP ..........................Health Physics HPC......................Health Physics Coordinator HPN .....................Health Physics Network I&C .......................Instrumentation and Control INPO ...................Institute for Nuclear Power Operations JPIC......................Joint Public Information Center Page 16 of 139

RERP Rev. 045 KI ...........................Potassium Iodide LAN .....................Local Area Network LOCA .................Loss of Coolant Accident LPZ.......................Low Population Zone MCA....................Multi Channel Analyzer MCL ....................Management Counterpoint Link MIDS ..................Moveable Incore Detector System NCRP .................National Council on Radiation Protection NRC .....................Nuclear Regulatory Commission NSSS ...................Nuclear Steam Supply System OSC......................Operations Support Coordinator OSLD .................Optically Stimulated Luminescent Dosimeter PAC ......................Plant Assessment Coordinator PAG .....................Protective Action Guide PCS.......................Plant Computer System PMC.....................Protective Measures Coordinator PMCL .................Protective Measures Counterpoint Link QA .........................Quality Assurance RCA .....................Radiological Controlled Area RCP ......................Reactor Coolant Pump RCS ......................Reactor Coolant System RERP ..................Radiological Emergency Response Plan RP ..........................Radiation Protection RSCL ..................Reactor Safety Counterpoint Link RWP ....................Radiation Work Permit SAMG ................Severe Accident Management Guidelines SEMA ................State Emergency Management Agency (Missouri)

SPDS ...................Safety Parameter Display System SMD ....................Secondary Monitoring Device STA ......................Shift Technical Advisor TAC .....................Technical Assessment Coordinator TEDE..................Total Effective Dose Equivalent TLD......................Thermoluminescent Dosimeter TSC ......................Technical Support Center USCG .................United States Coast Guard Page 17 of 139

RERP Rev. 045 2.0 SCOPE AND APPLICABILITY 2.1. Purposes and Objectives The purpose of emergency preparedness is to provide direction and control for response to classified emergencies and to ensure that necessary equipment, supplies, and essential services are available.

The primary objective of emergency preparedness is to develop and maintain a Radiological Emergency Response Plan (RERP), Emergency Implementing Procedures (EIP)s, and Severe Accident Management Guidelines (SAMG)s, to ensure a coordinated means for mitigating the consequences of emergencies in order to provide safety and dose savings for the general public and site personnel, and to prevent damage to property. As such, objectives of the Callaway Plant Radiological Emergency Response Plan (RERP) are as follows:

  • Establish a means to identify and classify emergency conditions.
  • Establish a means to reclassify emergency conditions should the severity increase.
  • Detail the on-shift emergency response and the Emergency Response Organization, including assignment of responsibilities and authorities necessary to direct the response in an emergency situation.
  • Provide guidelines and specific details of off-site support organizations' assistance (including governmental organizations) and availability.
  • Provide guidance for evaluating protective action recommendations to protect the general public and site personnel.
  • Provide guidance for terminating or mitigating the consequences of an emergency, both on-site and off-site.
  • Establish and provide specific details on Emergency Response Facilities (ERF)s, assessment equipment, communications equipment and their utilization during normal and emergency conditions.
  • Provide for the training of emergency response personnel.
  • Outline the most effective course of action in order to protect site personnel and recommend protective actions for the general public in the event of an emergency.

2.2. Planning Description Callaway Plant, in defining the Emergency Planning Zones (EPZ)s, has taken into consideration population densities, political and physical boundaries, and on-site and off-site organizational capabilities, as well as the guidance given in NUREG 0654/FEMA REP 1, Rev. 1.

Two primary zones have been identified for the purpose of development and implementation of the RERP. The first EPZ has a radius of about 10 miles and is referred to as the "Plume Exposure Pathway Emergency Planning Zone". Within this zone, evacuation and/or sheltering may be used as immediate protective actions to protect the general public. The principle concern with the Plume Exposure Pathway is that of external exposure and/or exposure to the thyroid due to inhalation and ingestion from a radioactive plume passing over the area.

Page 18 of 139

RERP Rev. 045 The second EPZ has a radius of about 50 miles and is referred to as the Ingestion Exposure Pathway Emergency Planning Zone. The principle concern with the Ingestion Exposure Pathway is from ingestion of contaminated water or foods such as milk or fresh vegetables.

2.3. Plan Interrelationships The RERP should not be used alone in response to an emergency, but in conjunction and coordination with procedures, other plans, and emergency arrangements.

These interrelationships are summarized as follows:

  • Emergency Implementing Procedures (EIP)s provide detailed actions to be taken by individuals in response to on-site emergency situations. These procedures direct the implementation of the RERP.
  • The Plant Operating Procedures include: Emergency Operating Procedures utilized to control the Plant during abnormal and accident conditions; Administrative Procedures; Radiation Protection Procedures; Chemistry Procedures; and Operations Procedures. Pertinent information from this document has been either incorporated into or referenced in the RERP and/or EIPs.
  • Security Plan and Procedures have been coordinated to ensure that appropriate emergency actions can be taken.
  • Coordination and liaison with off-site organizations and agencies having radiological emergency responsibilities ensures compatibility and proper interface with the RERP. Governmental agency interrelationships with the Callaway Plant RERP include:
  • Callaway County/City of Fulton
  • Montgomery County
  • Gasconade County
  • Osage County
  • Federal government The development of Federal, State, County, and Callaway Plant Radiological Emergency Response Plans has been closely coordinated. In addition, State and local preferences for reporting emergencies, providing information and data, recommending protective actions, etc., have been integrated directly into the RERP and the associated EIPs.

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RERP Rev. 045 3.0

SUMMARY

OF THE CALLAWAY PLANT EMERGENCY PREPAREDNESS PROGRAM This chapter of the Radiological Emergency Response Plan provides a summary of the Callaway Plant Emergency Preparedness Program. Information contained in this chapter is detailed in subsequent chapters of this Plan.

3.1. Radiological Emergency Response Plan (RERP)

This document establishes the concepts, evaluation and assessment criteria, and protective actions necessary to limit and mitigate the consequences of potential or actual emergencies.

The RERP incorporates the necessary pre-arrangements, regulatory guidance and requirements, and organizations necessary to provide dose savings for the protection of the health and safety of the general public and site personnel. During the developmental stage of this document, components of other planning documents were integrated into the RERP to ensure proper coordination of actions required by all associated planning documents as listed in Appendix I, List of Supporting Radiological Emergency Response Plans.

This RERP satisfies the requirements of 10CFR50.34, 10CFR50.47, and 10CFR50, Appendix E. This document also satisfies the intent of the guidance stated in NUREG 0654/FEMA REP 1, Rev. 1, as indicated in Appendix A, NUREG 0654/Callaway Plant Radiological Emergency Response Plan Cross Reference.

Supplemental guidance has been provided by additional documents. A sample of these documents is listed below:

  • Regulatory Guide 1.145 3.1.1. Summary of RERP 3.1.1.1 Chapter 1 - Glossary This chapter provides definitions of key words, terms, or phrases that are unique and used throughout the RERP. In addition, a list of commonly used acronyms and abbreviations and their meanings is provided.

3.1.1.2 Chapter 2 - Scope and Applicability This chapter provides a basic discussion of the purposes and objectives of emergency planning. Included in this chapter is a brief description of planning considerations and the interrelationships of this Plan to other planning documents.

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RERP Rev. 045 3.1.1.3 Chapter 3 - Summary of the Callaway Plant Emergency Preparedness Program This chapter provides a brief synopsis of each chapter in the RERP, a summary of the Emergency Plan Implementing Procedures, and a brief discussion of maintaining emergency preparedness.

3.1.1.4 Chapter 4 - Emergency Conditions This chapter establishes and defines the four classifications of emergencies utilized at the Callaway Plant (UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY). Included in this chapter are the trigger mechanisms or Emergency Action Levels (EAL)s used to determine which class of emergency should be declared. In addition, this chapter provides a discussion of postulated accidents in relation to the appropriate classification of that emergency.

3.1.1.5 Chapter 5 - Organizational Control of Emergencies This chapter provides a discussion of how the normal Callaway Plant operating organization and other Licensee organizations relate to the emergency response organizations and agencies that are utilized to mitigate and/or terminate the circumstances of an emergency. Each position within Callaway Plant Emergency Response Organization is discussed with emphasis on positional authority, responsibilities, and interrelationships with other factions of Callaway Plants or off-site agencies' organizations. Levels of augmentation including definable points where augmentation would occur are also included in this chapter.

3.1.1.6 Chapter 6 - Emergency Measures This chapter establishes the methodology of emergency response, and is the basis for the Emergency Plan Implementing Procedures which define emergency actions to be taken. A discussion of the following topics is included:

  • Recognition and evaluation
  • Classification and declaration
  • Notification
  • Assessment actions
  • Corrective actions
  • Protective actions
  • Aid to affected personnel
  • Public Information Page 21 of 139

RERP Rev. 045 3.1.1.7 Chapter 7 - Emergency Response Facilities and Equipment This chapter provides general descriptions of Emergency Response Facilities, communications equipment, assessment equipment, protective facilities and equipment, decontamination facilities and equipment, medical and first aid facilities, and damage control equipment and supplies that are available during an emergency. Included in this chapter are the functions and anticipated use of the facilities and assessment equipment located in the facilities.

3.1.1.8 Chapter 8 - Maintaining Emergency Preparedness This chapter summarizes the emergency response training program; describes the requirements for emergency drills and exercises (including joint exercises); details the methods utilized to review and update the RERP, EIPs, and Emergency Preparedness Program; describes the methods utilized to maintain an adequate inventory of emergency equipment and supplies; and describes the Callaway Plant's Emergency Preparedness Organization.

3.1.1.9 Chapter 9 - Recovery This chapter defines, in general terms, post emergency reentry, and recovery plans and organization.

3.2. Emergency Implementing Procedures (EIP)s The EIPs provide detailed action steps, in procedure format, necessary to be performed to implement the commitments/requirements as stated in the RERP. Information from other related planning documents has been integrated into the EIPs to ensure a coordinated response between and within organizations responding to an emergency at the Callaway Plant.

In general, the EIPs consist of the following:

  • The criteria or specific emergency action levels utilized to recognize, classify, and declare an emergency;
  • The Callaway Plant initiated notifications and communications equipment utilized;
  • Emergency actions to be taken by appropriate personnel to assess emergency conditions, and the steps taken to correct and/or mitigate the situation;
  • Duties and responsibilities of Emergency Response Organization members, facilities, equipment, etc., necessary to implement the RERP;
  • Actions to be taken for emergency response assistance;

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RERP Rev. 045 3.3. Maintenance of the Emergency Preparedness Planning Program Planning program maintenance consists of mechanisms designed to ensure a state of emergency preparedness.

Various departments at the Callaway Plant are involved in the maintenance of the Emergency Preparedness Planning Program. The Senior Vice President and Chief Nuclear Officer has the ultimate responsibility for management and direction of the Emergency Preparedness Program for Callaway Plant.

The maintenance of the Emergency Preparedness Program is described in detail in Chapter 8.0.

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RERP Rev. 045 4.0 EMERGENCY CONDITIONS Emergencies are classified into four classes: (1) UNUSUAL EVENT, (2) ALERT, (3) SITE AREA EMERGENCY, and (4) GENERAL EMERGENCY. Section 4.1 describes the purpose of each emergency classification level.

The possibility exists that particular situations may have characteristics in two or more classes. In such an event, the emergency will be categorized in the more severe class to ensure a conservative approach is taken.

A system of EALs that can be implemented in a timely and accurate manner was developed per NEI-99-01 Rev. 5. The Callaway EAL categories are grouped by applicable operating mode and listed with their subcategories below.

EAL Group / Category Any Operating Mode R - Abnormal Rad Release / Rad Effluent

1. Offsite Rad Conditions
2. Onsite Rad Conditions H - Hazards
1. Natural & Destructive Phenomena
2. Fire or Explosion
3. Toxic, Corrosive, Asphyxiant & Flammable Gas
4. Security
5. Control Room Evacuation
6. Judgment Hot Conditions S - System Malfunctions
1. Loss of Power
2. RTS Failure
3. Inability to Reach or Maintain Shutdown Conditions
4. Instrumentation / Communications
5. Fuel Clad Degradation
6. RCS Leakage
7. Inadvertent Criticality F - Fission Product Barrier Degradation Page 24 of 139

RERP Rev. 045 Cold Conditions C - Cold Shutdown / Refuel System Malfunction

1. Loss of Power
2. RCS Level
3. RCS Temperature
4. Communications
5. RCS Leakage
6. Inadvertent Criticality
7. Fuel Clad Degradation These initiating conditions and their indicators are depicted in the EAL Classification Matrix (Table 4-1). The EAL Technical Bases Document is available for the EAL Matrix user to refer to (but the user is not required to) in order to determine a classification declaration. The initiating conditions are used for classifying events and are provided in the Emergency Plan Implementing Procedures.

The initial assessment of plant conditions and classification of an emergency using the guidance of the Emergency Implementing Procedures is performed by operating shift personnel under the direction of the Shift Manager. This assessment is performed as quickly as possible. The goal is to have the emergency classified within 15 minutes after recognition of the initiating condition.

4.1. Emergency Classifications Each of the four emergency classes, represent distinct classes of events and have a genuine purpose as described in the following sections.

4.1.1. UNUSUAL EVENT This classification is characterized by events in progress or which have occurred indicating a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs. This event status places the Plant in a readiness position for possible cessation of routine activities and/or augmentation of on-shift resources.

The purposes of this class are to:

1) Assure that the first step in any response has been carried out;
2) Inform the operating staff; and
3) Provide systematic handling of UNUSUAL EVENT information and decision making.

Events in this class are selected based upon a potential to degrade to a more severe situation rather than an actual public hazard.

Initiating Conditions that require an UNUSUAL EVENT declaration are given in Table 4-1.

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RERP Rev. 045 4.1.2. ALERT This classification is characterized by events in progress or that have occurred which involve an actual or potential substantial degradation of the level of safety of the Plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of intentional malicious dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. As in the case of an UNUSUAL EVENT, the ALERT class includes emergency situations that are expected to be minor in nature. The entire Emergency Response Organization is mobilized. In addition, because of the nature of the ALERT class, broader assessment actions will begin.

The purposes of the ALERT class are to:

1) Assure that emergency response personnel are readily available to respond if the situation becomes more serious or to perform confirmatory radiation monitoring if required; and
2) Provide off-site authorities current status information;
3) Provide updates for the public through off-site authorities.

Initiating Conditions that require an ALERT declaration are provided in Table 4-1.

4.1.3. SITE AREA EMERGENCY The SITE AREA EMERGENCY class includes accidents in which major failures of Plant functions needed for protection of the public have occurred or are likely to occur. Events are in progress or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or security events that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the public Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.

The purposes of this class are to:

1) Assure that response centers are manned;
2) Assure that monitoring teams are dispatched;
3) Assure that personnel required for evacuation of near site areas are at their duty stations;
4) Provide current information to off-site authorities;
5) Provide updates for the public through off-site authorities.

Initiating Conditions that require a SITE AREA EMERGENCY declaration are given in Table 4-1.

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RERP Rev. 045 4.1.4. GENERAL EMERGENCY The GENERAL EMERGENCY class includes accidents which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity, or security events that result in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels off-site for more than the immediate site area.

The purposes of this class are to:

1) Initiate predetermined protective actions for the public;
2) Provide continuous assessment of information from the Callaway Plant and off-site organization measurements;
3) Initiate additional measures as indicated by actual or potential releases;
4) Provide consultation with off-site authorities; and
5) Provide updates for the public through off-site authorities.

Initiating Conditions that require a GENERAL EMERGENCY declaration are given in Table 4-1.

4.2. Spectrum of Postulated Accidents This section of the RERP shows that each of the accidents that have been hypothesized for the Plant can be properly evaluated using the preceding emergency characterization classes. A summary analysis of their implications for emergency planning is included.

4.2.1. Classification of Hypothetical Accidents All of the events hypothesized in Chapter 15 of the Standardized Nuclear Unit Power Plant Systems Final Safety Analysis Report (SNUPPS FSAR) fall into one of the four emergency classes outlined in Section 4.1. Listed below is a spectrum of these events and the emergency class into which each would likely fall. A complete discussion of any of these hypothetical events may be found in Chapter 15 of the Standard Plant FSAR. Conservative assumptions with respect to the accidents described in Chapter 15 have been made. Therefore, occurrence of some of these accidents (for example, with no failed fuel) may not result in as high a class as noted. Also, equipment assumed to work in the Chapter 15 analysis was assumed to successfully operate for the evaluation. Failures of required equipment in any of the accident scenarios may result in higher classes of emergencies.

4.2.1.1 Leaks of Radioactive Materials Outside the Containment Building Loss of radioactive materials (liquids) from the support systems or subsystems for the reactor and the waste processing systems may occur. The components (piping, valves, pumps, tanks, etc.) are located within the buildings in the Radiological Controlled Area (RCA). The floor drain system in the RCA is designed to collect any such leakage. The ventilation systems for the RCA are filtered and effluent monitors sample the effluent discharge. The ventilation systems are designed for the collection and removal of particulates and Iodine gas from the RCA that might be released as a result of this leakage.

Page 27 of 139

RERP Rev. 045 If leakage should occur, the initial assessment would be performed by the operating crew based on system indication, observation by personnel, area radiation monitors, process monitors, or the building effluent monitors. If the effluent monitors indicate a release level that would cause the declaration of an ALERT or higher emergency classification, further assessment could be provided by radiological surveys and field monitoring.

4.2.1.2 Loss of Coolant Accident A loss of coolant accident results from the failure of the primary system pressure boundary to contain the coolant. As the coolant is released to the containment, the Reactor Coolant System (RCS) is depressurized and the containment pressure increases. The classification of this type of accident would be based on Fission Product Barriers, Abnormal Radiation Events, Off-site Events, and could include classifications of Unusual Event, Alert, Site Area Emergency, or General Emergency based on severity.

Initial assessment would be performed by the operating crew based on data from RCS instrumentation (pressure, level, flow, etc.), containment monitoring system, subcooling indications, and containment pressure indications. Further assessment would be provided by radiological surveys.

4.2.1.3 Main Steam Line Break A main steam line break outside containment could result in the loss of secondary coolant from an entire steam generator. If there were any radioactivity in the secondary coolant, it could be released to the atmosphere. The classification of this type of accident would be based on Fission Product Barriers, and Abnormal Radiation Events, Off-site Events, and could include classifications of Unusual Event, Alert, Site Area Emergency, or General Emergency based on severity.

Assessment of a steam line break would be made by the operating crew based on steam generator and reactor coolant parameters. Radiation levels would be determined by radiological surveys and field monitoring.

4.2.1.4 Steam Generator Tube Rupture In the event of a steam generator tube rupture, primary coolant is released to the secondary system. Radioactive gases entering the condenser air removal system discharge to the unit vent. Should the steam generators Power Operated Relief Valves (PORV)s or safeties lift, radioactive gases would be released directly to the environment. This incident may be classified as an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY depending on the concentration of radioactive materials in the primary coolant and the severity of steam generator tube leakage. This classification would be based on Fission Product Barriers, and Abnormal Radiation Events, Off-site Events.

Initial assessment would be based on readouts in the Control Room from the Condenser Air Discharge Monitoring System, Steam Generator Blowdown Processing System Monitors, the Unit Vent Monitoring System, and the PORV monitors.

Page 28 of 139

RERP Rev. 045 4.2.1.5 Reactor Coolant Pump Locked Rotor The instantaneous seizure of a reactor coolant pump rotor results in a reactor trip on low coolant flow signal. With the coincident loss of off-site power, the Plant condenser is not available so the excess heat is removed from the secondary system by releasing steam through the main steam safety relief valves. Steam generator tube leakage is assumed to occur and continue until the pressures in the reactor coolant and secondary systems are equalized. This incident may be classified as an ALERT or SITE AREA EMERGENCY depending on the concentration of radioactive materials in the primary coolant and the severity of steam generator tube leakage. This classification would be based on Fission Product Barriers, and Abnormal Radiation Events, Off-site Events.

Initial assessment would be performed by the operating crew based on data from RCS instrumentation and radiation monitoring instrumentation. Further assessment would be provided by radiological surveys and field monitoring.

4.2.1.6 Fuel Handling Accident A fuel handling accident could occur if an irradiated fuel assembly is dropped, if an object is dropped onto an irradiated fuel assembly, if a cask containing an assembly is dropped, or if an assembly is deformed during any of the manipulations of loading, unloading, or storage. An UNUSUAL EVENT or ALERT based on Abnormal Radiation Events, On-site Events, would be declared in the event of a fuel handling accident in which the fuel clad was damaged and radioactivity was released.

Area radiation monitors in the containment building, cask handling area, fuel pool bridge crane and spent fuel pool area are available to determine radiological conditions. Radiation monitoring would be required during the initial re entry into the affected area. If a release of radioactive materials occurred or was suspected, field monitoring would be activated.

4.2.1.7 Rod Cluster Control Assembly Ejection Following a postulated rod ejection accident, 10% of the activity from the fuel-pellet-clad gap is assumed to be instantaneously released to the reactor coolant.

The activity released to the containment from the reactor coolant through the ruptured control rod drive mechanism pressure housing is assumed to be mixed throughout the containment and could result in leakage to the atmosphere. In the case of primary to secondary leakage coincident with loss of off-site power, activity is also released to the atmosphere by releasing steam through the steam generator PORVs and safeties. Depending on the leak rate and fuel damage, the situation could result in a declaration of an UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY based on Abnormal Radiation Events, Off-site Events, or Fission Product Barriers.

Initial assessment would be performed by the operating crew based on indications in the Control Room. Further assessment would be provided by radiological surveys and field monitoring.

Page 29 of 139

RERP Rev. 045 4.3. Detection of Postulated Accidents The detection of abnormal conditions or accidents by station personnel may be a result of alarms, instrument readings, off-site information, personnel observations, or a combination thereof. The first person to detect such conditions has been trained to immediately notify the Shift Manager who will then evaluate and classify the situation.

Instrumentation that can be utilized to detect anomalies for hypothetical accidents is listed and/or discussed in the FSAR or Technical Specification or Emergency Operating Procedures.

Emergency Operating Procedures are procedures that govern the plant operation during emergency operations.

Page 30 of 139

Table 4-1 RERP Emergency Action Level Classification Matrix Rev. 045 Sheet 1 of 3 Table Table R-1 R-1 Effluent Monitor Monitor Classification Classification Thresholds Thresholds ReleasePoint Release Point Monitor Monitor GE GE SAE Alert UE 200 X Hi-Hi Plant Vent GT-RE-21B GT-RE-21B 5.82µCi/sec 5.82 E+8 E+8 µCi/sec5.82E+7 5.82 E+7 µCi/sec 200 X Hi-Hi alarm 2 X Hi-Hi alarm

µCi/sec alarm Atmospheric Steam Dump (ASD) AB-RE-111/112 AB-RE-111 /112 Gaseous 3 .58mr/hr 3.58E+2 E+2 mr/hr 35.9 mr/hr 35.9 mr/hr 113/114113 /114 Monitors (STM LINE A, B, C, D Mon.)

Gaseous TD TDAFW AFWSteam SteamDischarge Discharge FC-RE-385 2 .08 mr/hr FC-RE-3852.08 E+3 E+3 mr/hr 2.09 E+2 mr/hr Radwaste Bldg Vent GH-RE-10B 200 X Hi-Hi alarm 2 X Hi-Hi alarm Page 31 of 139

Table 4-1 RERP Emergency Action Level Classification Matrix Rev. 045 Sheet 2 of 3

. . GENERAL EMERGENCY SITE AREA EMERGENCY ALERT I UNUSUAL EVENT

~A1 AC. ~owerca~p llb~ iry tc et'l'le!'(lency tklae1 redLJced m a llin~te ~U1 Lcs1 ot al cttsite power tCl eme~ eMC\' bu1e1 !Cl r ~ 1~ minutes.

~ll1 l'r()Jcn!:j ed lou ot all nttsite ~ower and prolon~ e d lo* Cll d ~~18. Loss at d oti&Jte powerancllon ct MIClMi ite AC power tc power source !Clr~ 1~ minutes such thllt&fri adclticne.lsinqle Llll '!.'il~ /\C ~UV".l l lu \llll\:r~~lll..)' l.oLI SU:O ~~~~~rycu\.-y Lw,;~ '!l'.

f'-libll wookl r~ :.nill in >t<J., utr Lln.- lw\ll SG11 I 1 I 2 I 3 4 ss1.1 C:::I::] 2 I 3 I 4 I SA11 I 1 I 2 I 3 I 4 I SU1.1 ,_1 -;:1'-;--'-:-::2,_.LI--"---'-I_4_,_-'-I---,.--'---,-::7c=J ,----_,

Loss oral offsite and onsite AC power to emergency Loss of all offsite and ons1te AC power to emsrgency AC power capab~ity to emergency buses NB01 and Lnss of all offsite AC power to emergency buses NB01 1 buses NB01 and N802.

AND EITHER buses NB01 and NB02 IDI' 2: 15 min N802 reduced to a single power source ror-= 15 min. and NB02 for-= 15 min.

L.ws of Restorati<ln of at least one emergency b~Js within P..-r 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is not likety'  ;<;;<; lh Loss af all v~af DC power OR CSFST Core Cooli1g- RED or ORANGE p;ath ss1.2 C:::I::] 2 I 3 I 4 Loss of all Division 1 and 2 v<<al DC power based on

< 107.0 VOC b~Js indjcations IDI" ~ 15 min SG2 f~IIIC ul f1~ R ~udLH Tri11 Spl~m lll \:\.0/ll)'l~li.: '-'fl u \1\.u rm.ltit.: SS2 F-..lliiC urRu\.l~lu r Try Sy:ol\:fll imtrlllll~llluliuulu CUIII!~k.W Ul SA'/ r.,;.n., nf R.. ~ntro.. T rir Sy"'"'"' ~ ...mm, ~ nt~ tinn t ro r.nmpMt.. n~

LIYuri\Juii.IIHI'-II liY..,..... .,Mo.A.>l.l~c\i\oifLIIuralll..:rui:. iri\Jicutiuu iu il.i-..lc i.lll Ullluu*u* ~ rc""--lu' bY ur...-..: u Rcu\!lu1 T1i~ Sy.,lcul ir.iti"'" """ """trm1.J1tir. ,., ..,ntn r trir ronn~ "'F:.,,...,..,~ Trir :<iy ~ t..m rol ~ n ~ :rtn*m ., .-.h..,b n'J II tnft.., ...hilitytn r-.11nllh.,..,.,.., ~ ~*ronint I* ~ ~ howlll ., ,.,....., ~ ..tl ~ ntl m""",.j t rip w..,,., n*t,.,ur.r.~ ,.,~ ~~~ "'~ 'f'n~lt 1, ~,., r... ~ n ~.. r... ~ tl.. rt .JOnrt m~n1ultrir "'"" "' !;nnn.. ~..f"l SG21 I 1 I 2 I ss2.1 c::l:-:=[1:00:2C[I= =r:==[ = :J:= :J:==:J SA21 2 Automatic and all m.;~nual trips failed to generate a negative SUR ;and prompt lowering in reactor power ta Automatic and all man~Jal trips (us1ng SB*HS*1 or SB-HS-42} fJiled to generate.;~ negative SUR .;~nd prompt Indication of all of the following:

  • Artf RTS setpoint w.;~s exceeded RTS .r:: :5% after any RTS setp.~nt is exceeded. lowe ring in re;actm power to < 5% after any RTS setpaint is
  • Succ:essfuJ manu;al t rip oc:cu rred (using SB-HS-1 CSFST Core Coo~ng +RED or SB*HS-42)

OR CSFST Heat ~nk +RED.

LI_1~L~~2~_LI~3~L~~4~.LI___ L_ _ _,c==J

~;ant is not brought to required operating mode within Technic::al Specifications LCO action st;atement time Uu ~ umi<..-..ll\l :.;:.; urna.olilu !ial-,;ufdy*,;l" :.;lcru urm'-'fi Liuliuuul Ur1111'-'r111CU lu\i\oi ulrM11slu1 d :.;;.tl\lly ~y\iU:u1 '-'flllllll~lillr1 111 ili\li\.:u* ull iu Cuullul Ruur11 with \l~ ~~~r (1) " ~y ui"MJrlt lrurt~ ~lll ir1Uiu-..lillrt ir1 ll1c cuulrul ruuu1 fu1 ~ 1G ruirl\ll\:\oi ill ~IUYI\l\oi \oi, \II (l) 1:\IIIYIJII-,;ul\.lry II \Ill '-lli.IIHiill~ iruJiciJI.UI:O '-'f\l "n,....,,a..,~-o~ ~

s System following c::I:-:=1 2 I 3

  • 3 of 4 field power supplies indicate < 1 05 VDC I

Loss of .;~nnun ciators and indic.;~tors based on any of the 4 SA4.1 I 1 I 2 I 3 I 4 I Unplanned loss or annunciators or indic.;!tors for-= 15 min.

b;ased on "illY of the fu~ awing

  • 3 rJ 4 field power supplies indicate < 1 Q5 VDC SU4.1 UnpJ.;~nned

[I::1C[I:00:2CII::3C[I::4'CII = =r==lc =J loss or annunciators or in dic.;!tors lor-= 15 min.

b;ased on "illY of the fa~awing

  • 3 of 41ield power supplies indicate < 1 Q5 VDC Malfund
  • Field Power S~Jp.~y Bus voltsge is .r:: 105 VDC.
  • Fi8Jd Power Supply Bus VJ"Jttage is < 105 VDC.
  • Field Power Supply Bu s VJ"Jttage is < 105 VDC
  • > 9 logic power supp lies have fJiled. * > 9 logic power supplies t1.;~ve railed. * :. 9 logic power supplies t1ave railed.
  • > 4 Mu~iplexer Adapter Rack Fuses t1ave failed. * > 4 Muttiplexer Adapter Rack Fuses have failed * :. 4 Muttiplexer Adapter Rack Fuses have failed.
  • OR BOlH of the following: ,. OR BOTH of tt1e following: ,. OR BOTH of tt1e following:

4 Arry failure of.;~ CXlmj)jn.;~tion of power supplies (induding Optical Isolators) m Multiplexer Adapter R;ack Fuses Anyfail ure or a com bination or power supplies (including Optical I salatms*) or Multiplexer Adapter Rack Fuses Art{ failure or a com bination or power supplies (including Optical I solatms*) or Multiplexer Ad;apter Rack Fuses AND ANO ANO Arry minim urn CXlmpensatory actio ns Any minimum compensatory actions Artf minimum compens.;~tory actons (OTO-RK-()('()01') cannot be maintained (OTO-R K-00001) cannm be m;ai1tained (OTO-R K-00001) cannm be m;aintained AND AND EITHER

~Uolb UMpla~Mned lo

  • nl 811 oo ~ t e or chite oommurak:RIIicns Any signilic.;!nt transient is in progress, Table S-1 Any signilic.;!nt transient is in progress, Table S-1 ca~p 11.b~ iries.

AND OR SU4.2 I 1 I 2 I 3 I 4 I Comp.ensstory plant parameters monitored via tt1e Comp.ensstory plant parameters monitored via tt1e Lnss of all Table S-2 onsJte (intem;al) cammunic;ations plant computer (OTO-RK-00001) are not valid or plant computer (OTO-RK-00001 ) .;~re not valid or capability affecting the abjlity to perform routine operations.

cannot be obtained cannot be abtaJned OR Lnss of all Table S-2 offsJte (extern;al) communications cap;ability Coo!ant activity> frlyof the fo~owing

  • 1.0~CL'gm Dose Equivalentl-131 lor > 48 hr continuous pe riod
  • 60~Ci:gm Dose Equiv alentl-131.

225 ~C~ gm Dose Equivalent X e-133 1

RCSiu<1kuyc Ll_1~1~2~~~3~I_4~LI___ L_ __ ,c==J Unidentified or pressure boundary leak;age >- 10 gpm OR (Note 4)

Arry Lrlplanned sustained positive startup rate observed an nudear instrument;ation F Loss of any two barriers.

AND Loss or potential loss of any two barriers (Table F *1).

(Notes 1, 2, 3)

Any k:lss or any potenti&J lo ss of either Fu8J Clad or RCS (Tabje F* 1). (Notes 1, 2. 3)

!vry loss Dl" any potential loss of Contsjnment (Table F* 1}

(Notes 1, 2.3)

Fission ProdJct Loss or potential loss or third barrier (Table F-1).

Barriers (Nates 1. 2, 3)

Table F-1 Fission Product Barrier Matrix Fuel Cladding Barrier Reactor Coolant System Barrier Containment Barrier A. Critical Safety Ftmction Status CSFST Heat Sink- RED an d t1eat sink required.

B. Core Exit TCs C ore exit TCs > 1,2WF 2 CDI"e exit TCs > 7062f'. 2. Core exit TCs > 1 ,20CfF AND Restoration procedures not effective within 15 min.

3. All or the following :

l Core e>dt TCs:. 706"F I Re;adm Vessel wat er level

- S 06 E+04 R:"hr GT-RE-59 >-2.SE-t-03 R:hr (591') m GT-RE-60 (601') GT-RE-59 (:591) or GT-RE-60 (601). 5. Une>illained rise in radi.;~tion levels in areas
adjacent ta Cont;ainment
1. R.;~pld unexpl.;~in ed Containm ent pressure drop 6 Containment pressure 48 psig and rising D. Inventory 2. RCS leak rate ::>> availabJe make~Jp. capacity as following initi;al rise
7. Contsjnment t1ydrogen concentration~ 4%.
indicated by a loss of RCS 2. Fo~owing LOCA, Containment press~Jre or sump. subcooling (:!!: 30"F [50"FJ) level response not consistent with LOCA conditions 8 Containment pressure> 27 psig with< one full train af depressuriz ation equipment operating
3. SGTR tt1at res~Jits in an 3 Ruptu red SG is also f;aulted outside of Containment Note: Qrae (.;ootllliMmenr ~pmy ~~~stem tnlin e.rtcl orae ECCS (SI) .;~ct\.J.;~tion Cuuluinrr..:r1l Cu~i11~ S y:.;i..cr11 buir1 \NIII~r r..<.: ur11: h1~ lruiu
4. Prim.;~ry-to-second.;~ry le.;~krate > 10 gpm witt1 non-isoJ.;~ble ste.;~m rele.;~se lrom affected SG to tt1e ur U~:IJr~:.;:.;o,Hi..:utiuu ~l.jlli11rn~r1l.
environment E. O'tt1er :5. Conta inment isolaUon valve(s} not clos&d after Conta inment isolaUon AI\[) Oawnstre;am p;att1way to the errviro001ent exists F. Judgment 6 Arry rnnditioo in tt1e opinion of the Emergency 9 Arry condition in the opJnion af th e Em ergem::y Coordinator that indicates loss of the Containment Coordinator that indicates patenti;alloss of the barrier. Contsinment barrier Note1 Note2 The logic used far these initi;ating conditions reflects the fa~awing consJder;ations Ftss1on Prod~Jc:t Barrier EALs must be capable of addressin g event dynamics. Imminent {i.e The Fuel Clad barrier and the RCS barrier are weigt1ted more heavily tt1an the Containment barrier. UE wittlin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) Loss or Potential Loss st1ould result in a classification as ir the .;~rtected threshold(s) EALs .;~ssociated wittl RCS .;~nd Fuel Clad barriers are addressed under System Malfunctio n E.ALs. are alre.;~dy exceeded, particularly for the t1i gt1er emergency classes. At tt1e Site Area Emergency level, tt1ere must be some ability ta dyn<W11 ically assess how f;ar present rnnditions are from the threshold for a Gener;al Emergency Far ex;ampJe. if Fuel Clad and R CS barrier Note3: loss EAls extsted. tt1at, in sddition to offsite dose assessments. wo~Jid req~Jire continual asse ssments of Dete rmine w hictl CXlmbin.;~tion of the three b.;~rrie rs are lost or have a potential loss and use FU1.1 radioactive inventory and containment integrity. Alternatively, il both Fuel Clad and RCS barrier **Potential FA1.1, FS1.1 and FG1.1 to classify 'tt1e event. Also an event or muttiple events could ocClJr wt1ict1 Lnss* EALs existed, tt1e Emergency Coordinator would have more ;assur;anc:e that tt1ere was no immediate result in the condusJan t h;at exceeding tt1e lass or potenti;allass thresholds is imminent (i_e_, within 21'% need to esc::alate to a Gener;al Emergency 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) In tt1ts imminent loss situation.~Jse judgment and dassify as if the threst1olds are Pumps On The ability to esc:alste to highsr emergency classes as an event deteriDI"ates must be msjntained. For exceeded. example, RCS le.;~kage ste.;~dily rising would represent .;~n escalating risk to public he.;~lth .;~nd safety. 4 HOT CONDITIONS (RCS > 200°F) Page 32 of 139 Table 4-1 RERP Emergency Action Level Classification Matrix Rev. 045 Sheet 3 of 3 I 5 I 6 I DEF I CU1.1 I 5 I 6 I Loss of all offsite and onsite AC power to emergency buses AC power capability to emergency buses NB01 and NB02 NB01 and NB02 for :2: 15 min. reduced to a single power source for :2: 15 min. 1 CU1 b Unplanned loss of required OC power for> 15 minutes. CU1.2 I 5 I 6 I Unplanned loss of vital DC power to required Division 1 and 2 DC buses based on< 107.0 VDC bus voltage indications. AND Failure to restore power to at least one required DC division within 15 min. from the time of loss. CG2 Loss of Reactor Vessel inventory affecting fuel clad in tegrity CS2a LossofReactorVesselinventoryaffectin g core decay heat CA2 Loss of Reactor Vessel inventory with irradiated fuel in the CU2 Unplanned loss of RCS inventory w ith irradiated fuel in the with Containment challenged. removal capability. Reactor Vessel. Reactor Vessel. CG2.1 I 5 I 6 CS2.1 I 5 I 6 CA2.1 I 5 I 6 CU2.1 I 6 RVLIS Pumps Off < 65% (Top of Fuel) for > 30 min. With Containment closure not established, RVLIS Loss of inventory as indicated by EITHER: Unplanned RCS level dropping below the Reactor Vessel AND Pumps Off< 72% (BBLI-53 AJ13 < 0 inches). Reactor Vessel level< bottom of RCS hot leg ID (RVLISflange (BBLI-53 A/B @1 00.1 inches) for :2: 15 min. Pumps Off< 73%- BBLI-53 AJ13@ 0 inches). Any Containment Challenge indication, Table C-5. CS2.2 I 5 I 6 OR CU2.2 I 6 Reactor Vessel level cannot be monitored for :2: 15 min. With Containment closure established, RVLIS Pumps Off Reactor Vessel water level cannot be monitored with unexplained rise in any Table C-1 sump /tank level. CG2.2 I 5 I 6 < 65% (Top of Fuel). AND Reactor Vessel level cannot be monitored with core uncovery Loss of inventory as indicated by unexplained rise in any indicated by any of the following for :2: 30 min.: Note: RVLIS is not operable in MODE 6. Table C-1 sump I tank level. CS2.3 I 5 I 6 I
  • ~~8i~~~~~or crane radiation monitor SD-RE-41 Reactor Vessel level cannot be monitored for :2:30 min.
with a loss of Reactor Vessel inventory indicated by any
  • Erratic source range monitor indication. of the following:
  • Unexplained rise in any Table C-1 sump /tank Table C-1 S001ps!fanks
  • ~~8i~~~~~or crane radiation monitor SD-RE-41 level.
AND
  • Erratic source range monitor indication. Containment Sump Any Containment Challenge indication, Table C-5. Containment Normal Sump
  • Unexplained level rise in any Table C-1 sump /tank level. Containment Instrument Sump 2 PRT RCDT Auxiliary Building Sump RCS Level Table C-5 Contairvnent Chal enge Indications Containment closure not established Containment hydrogen concentration :2: 4%
Unplanned rise in containment pressure CA3 Inability to maintain plant in cold shutdown with irradiated fuel in CU3 Unplanned loss of decay heat removal capability with irradiated the Reactor Vessel. fuel in the Reactor Vessel. I 5 I 6 I CU3.1 I 5 I 6 I Any unplanned event results in RCS temperature> 200°F Any unplanned event results in RCS temperature> 200°F Note: Begin monitoring hot condition EALs concurrently. for> Table C-3 duration. ORRCS pressure rise> 10 psig due to a loss of RCS cooling. CU3.2 I 5 I 6 I Note: Begin monitoring hot condition EALs concurrently. Loss of all RCS temperature and Reactor Vessel level indication for :2: 15 min. c ColdSD/ Refuel System CU4 Unplanned loss of al on site or offsite communications Mal ooct. capab ~ ities. I 5 I 6 I Loss of all Table C-2 onsite (internal) communications capability affecting the ability to perform routine operations. OR 4 Loss of all Table C-2 off site (external) communications capability. I 5 1@@1 Unable to establish or maintain pressurizer level > 17% for :2: 15 min. I 5 I 6 I Any unplanned sustained positive startup rate observed on nuclear instrumentation. COLD CONDITIONS (RCS < 200°F) Page 33 of 139 RERP Rev. 045 5.0 ORGANIZATIONAL CONTROL OF EMERGENCIES This chapter describes the organizational structure of the Callaway Plant Emergency Response Organization and transition from the normal operating organization in the event of a radiological emergency declaration. The Callaway Plant Recovery Organization and post-accident planning are discussed in Chapter 9.0. The Callaway Plant Emergency Response Organization (ERO) has been established to provide technical and logistical direction in the event of a radiological emergency declaration at the Callaway Plant. This organization is structured to provide for Plant control, coordination of on-site response, coordination of off-site response and dissemination of information to the public. The Callaway Plant On-shift Operating Organization provides the initial emergency response to any emergency situation. Minimum staffing of the normal On-shift Operating Organization is noted in Figure 5-1 which also illustrates the initial On-shift Emergency Response. The Shift Manager is the senior Callaway Plant management representative on-site during the absence of normal Plant management (i.e., back-shifts, weekends, holidays). The Shift Manager is responsible for directing safe, legal, and efficient Plant operations in accordance with established normal and emergency operating procedures. The Shift Manager is provided technical assistance by an Operating Supervisor or Engineer who meets the qualifications for Shift Technical Advisor (STA) as required by the NRC. The Emergency Coordinator (TSC) is a predesignated senior Plant management representative on-call (not required to be on-site) and available to provide the Shift Manager with management guidance and directives during emergency operations. The Emergency Coordinator (TSC) will receive notification of an event via the ERO Notification system. (The Duty Manager provides guidance and directive during normal operations and is the contact for support during an Unusual Event.) Immediate actions in response to an emergency are the responsibility of the On-shift (Figure 5-1) Emergency Response. On-site emergency management responsibilities are assumed by the Shift Manager who becomes the Emergency Coordinator until the Emergency Coordinator (TSC) arrives and assumes responsibilities. At ALERT (or higher) emergency classification levels, the Emergency Response Organization (Figure 5-2) is mobilized to provide additional support to the on-shift personnel. The Emergency Coordinator (TSC) assumes Emergency Coordinator responsibilities from the Shift Manager and directs emergency response after being briefed on the emergency situation. The oncoming personnel are briefed on the emergency situation prior to accepting responsibilities. After being briefed by the Emergency Coordinator, the Recovery Manager becomes the senior management representative for Callaway Plant emergency response. However, the Emergency Coordinator continues to direct and control on-site personnel and make all emergency declarations. Page 34 of 139 RERP Rev. 045 5.1. On-Shift Emergency Response (Figure 5-1, Table 5-1) The On-shift Emergency Response is directed from the Control Room. The On-shift Emergency Response is capable of responding unassisted to emergencies classified as UNUSUAL EVENTS as outlined in Section 4.1.1. The primary responsibilities of the On-shift Emergency Response are:
  • Initial classification and declaration of emergencies;
  • Requesting technical and operational support;
  • Initial coordination of on-site emergency actions/response;
  • Notification and communications with off-site organizations;
  • Making Protective Action Recommendations to off-site authorities;
  • Mobilizing the rest of the Callaway Plant Emergency Response Organization; and
  • Requesting local off-site support (i.e., firefighting, ambulance, law enforcement).
As the Emergency Coordinator, the Shift Manager assigns members of the On-shift Emergency Response to emergency duties, as necessary, to effectively control the situation. Minimum staffing levels for the On-shift Emergency Response are specified in Table 5-1. Responsibilities of the members of the On-shift Emergency Response are as follows: 5.1.1. Shift Manager Upon classification of an emergency, the Shift Manager assumes the position of Emergency Coordinator and initiates emergency actions including making Protective Action Recommendations to authorities responsible for implementing off-site emergency measures. The Shift Manager assigns on-shift personnel to emergency duties as deemed necessary, and notifies the Emergency Coordinator (TSC) of the emergency. The Shift Manager continues as acting Emergency Coordinator until relieved by the Emergency Coordinator (TSC). When relieved, the Shift Manager will resume normal duties in directing Plant Operations activities from the Control Room. 5.1.2. Operating Supervisor The on-shift Operating Supervisors are assigned the positions of Control Room Supervisor in charge of the Control Room and Field Supervisor in charge of actions outside the Control Room. The Control Room Supervisor is responsible for directing Reactor Operators, Operations Technician(s), and Assistant Operations Technician(s) in the appropriate actions necessary to maintain safe Plant conditions in accordance with established normal and emergency operating procedures and Severe Accident Management Guidelines. The Field Supervisor reports to the Control Room and performs actions as assigned by the Shift Manager. Page 35 of 139 RERP Rev. 045 At least one (1) Supervisor assumes the additional duties of a Shift Technical Advisor (STA), which includes monitoring Plant instrumentation and the Safety Parameter Display System (SPDS) throughout the course of the emergency and providing technical recommendations to the Shift Manager concerning reactor safety. These duties may be assumed by an STA qualified Engineer if one is available on-shift. One Fire Brigade Leader qualified Operations person is designated Fire Brigade Leader. This cannot be the Operating Supervisor designated as the Shift Technical Advisor (STA). If the Shift Manager is incapacitated or unavailable to assume Emergency Coordinator responsibilities, the Operating Supervisor with a NRC Senior License has the authority to assume that position. 5.1.3. Operations Personnel Upon declaration of an emergency, Reactor Operators, Operations Technician(s), and Assistant Operations Technician(s) report to, or makes contact with, the Control Room and are under the direction of an Operating Supervisor and/or Shift Manager. Operations personnel perform Plant operations in accordance with established normal and emergency operating procedures and Severe Accident Management Guidelines. These personnel may be assigned other emergency duties as necessary. One Fire Brigade Leader qualified Operations person is designated Fire Brigade Leader. 5.1.4. Other Operations Personnel Upon the declaration of an emergency, one designated operations person reports to the Shift Manager in the Control Room to assume the Control Room Communicator duties. The other person is responsible for emergency electrical repair, mechanical repair, assisting the Control Room Communicator, and other emergency duties assigned by the Shift Manager. These personnel may be assigned other emergency duties as necessary. 5.1.5. Chemistry Technician Upon declaration of an emergency, the Chemistry Technician reports to, or makes contact with, the Shift Manager. The Chemistry Technician is responsible for sampling and analysis as needed to identify the source and magnitude of the emergency. If an ALERT (or higher) emergency is declared, the Chemistry Technician will report to the Chemistry Coordinator in the TSC when released by the Shift Manager. Chemistry Technicians are qualified as Support Area Personnel in the Health Physics group (Section 5.2.5). Page 36 of 139 RERP Rev. 045 5.1.6. HP Operations Technician Upon declaration of an emergency, the HPOPS Technician reports to, or makes contact with, the Shift Manager. The HPOPS Technician is responsible for providing radiation protection support to Operators and Emergency Teams. If an ALERT (or higher) emergency is declared, the HPOPS Technician will report to or make contact with the Health Physics Coordinator located in the TSC when released by the Shift Manager. 5.1.7. Health Physics Technical Support (HPTS) Technician Upon declaration of an emergency, the HPTS Technician reports to the Shift Manager in the Control Room. The HPTS Technician is responsible for performing initial radiological release dose projections based on effluent release monitors and meteorological conditions. If an ALERT (or higher) emergency is declared, the HPTS Technician will report to or make contact with the Health Physics Coordinator located in the TSC after being relieved of dose projection responsibilities by the Dose Assessment Coordinator in the EOF and after being released by the Shift Manager. 5.1.8. Shift Security Supervisor Upon declaration of an emergency, the Shift Security Supervisor reports to the Shift Manager. The responsibilities of the Shift Security Supervisor include Plant access control, personnel accountability, and normal and emergency security activities as established by the Security Plan. The Shift Security Supervisor is assisted by the Security Force in carrying out these responsibilities. 5.1.9. Security Force The Security Force reports to the Shift Security Supervisor and performs duties in accordance with the Security Plan. Security personnel also provide security support as necessary. Security performs the paging function for Emergency Response Organization Augmentation upon direction from the SM/EC. 5.1.10. Control Room Communicator Upon declaration of an emergency, the Shift Manager assigns an Operations Technician, Assistant Operations Technician, or another qualified person as Control Room Communicator. The Control Room Communicator initiates notifications of off-site authorities as directed by the Shift Manager. The Communicator will maintain communications with the off-site authorities and others as directed by the Shift Manager. If an ALERT (or higher) emergency is declared, the responsibility for communication with the NRC via the ENS line will be transferred to the TSC Communicator in the TSC and responsibility for off-site notifications will be transferred to the Communicator in the EOF. After being relieved of communications responsibilities, the Control Room Communicator may be assigned other duties or report to the appropriate coordinator in the TSC as directed by the Shift Manager. Page 37 of 139 RERP Rev. 045 5.1.11. Emergency Teams Emergency Teams may be formed at the direction of the Shift Manager from available personnel. 5.1.11.1 Fire Brigade The Fire Brigade consists of on-shift Plant personnel in accordance with the Fire Protection Program. The Fire Brigade responds to on-site fires and/or hazardous chemical/oil spills and reports to the Shift Manager. 5.1.11.2 Medical Emergency Response Team (MERT) The MERT consists of a team leader and at least one team member, both of whom are trained in first aid procedures. The MERT reports to the Shift Manager and responds to illness or injuries on-site requiring immediate treatment beyond that which can be self-administered. During an emergency classification, MERT personnel will continue to be under the direction of the Shift Manager in the Control Room. 5.1.11.3 Search and Rescue Team The Search and Rescue Team consists of at least two personnel, at least one of which is qualified in first aid procedures. Health Physics support will be provided if necessary. The Search and Rescue Team is formed from on-shift personnel at the direction of, and reports to, the Shift Manager. If an ALERT (or higher) emergency is declared, Search and Rescue Teams will originate from the TSC and report to the Operations Support Coordinator. 5.1.11.4 Emergency Repair Team The Emergency Repair Team for Electrical and Mechanical repair consists of at least two Plant personnel with appropriate skills for the repair situation. Health Physics support will be provided if necessary. The Emergency Repair Team is formed at the direction of, and reports to, the Shift Manager. If an ALERT (or higher) emergency is declared, Emergency Repair Teams will originate from the TSC and report to the Operations Support Coordinator. Page 38 of 139 RERP Rev. 045 5.2. Emergency Response Organization (Figure 5-2, Table 5-2) Mobilization of the Emergency Response Organization (Figure 5-2) is initiated by the Shift Manager at the ALERT (or higher) emergency declaration. Direction and control of Emergency Response Organization activities are carried out from the TSC and EOF. Desired staffing levels and response time goals for filling emergency positions and activating the Emergency Response Facilities in the Emergency Response Organization are specified in Table 5-2. Positions in the Emergency Response Organization (ERO) that are considered essential to activate the Emergency Response Facilities (TSC/EOF) are defined as Minimum Staffing and are designated in Table 5-2. Minimum Staffing personnel functions include overall control of the Emergency Response Organization, technical assessment of Plant parameters, in-plant radiological controls, emergency repairs, dose assessment, offsite notifications, protective action recommendations, and communications with the NRC. Minimum Staffing personnel are trained and capable of performing tasks specified for their reporting staff. The remaining positions are necessary to fully staff and implement all intended functions of the Emergency Response Organization. The Staffing levels shown in Table 5-2 do not include members of the On-shift Emergency Response listed on Table 5-1. Responsibilities of the members of the Emergency Response Organization are as follows: 5.2.1. Emergency Coordinator (EC) (Minimum Staffing) The Emergency Coordinator is responsible for directing overall emergency response on-site. Initially, the Shift Manager assumes the responsibilities of Emergency Coordinator. At the ALERT (or higher) emergency classification levels, the Emergency Coordinator (TSC) will relieve the Shift Manager and assume the Emergency Coordinator duties. The Emergency Coordinator directs the Emergency Response Organization from the TSC after relieving the Shift Manager. Specific responsibilities of the Emergency Coordinator include:
  • Classifying and declaring emergencies;
  • Authorizing personnel exposure in excess of 10CFR20 limits;
  • Directing operations of Emergency Response Organization;
  • Requesting the formation of emergency teams;
  • Initiating the implementation of on-site protective actions;
  • Ensuring that Emergency Response Organization is kept up-to-date on emergency conditions; and
  • Ensuring that site-wide announcements are made on the Plant PA system.
The responsibilities that the Emergency Coordinator may delegate are indicated above with an asterisk (*). Page 39 of 139 RERP Rev. 045 The Emergency Coordinator position owner is trained as an Emergency Coordinator. Selected personnel are also trained for the position of Emergency Coordinator. 5.2.2. Operations Group 5.2.2.1 Shift Manager The Shift Manager continues to direct Plant operation activities from the Control Room after being relieved of responsibility for emergency response activities by the Emergency Coordinator. The Shift Manager reports to the Emergency Coordinator for the purpose of coordinating Plant operation activities with emergency response. 5.2.2.2 On-Shift Personnel On-shift personnel not required to support Plant operations may be released to the On-site Emergency Response Organization at the discretion of the Shift Manager. Remaining personnel and additional Operations department personnel responding to the emergency will continue to operate from the Control Room and Field Office. 5.2.2.3 Control Room/TSC Liaison (CTL) The CTL reports to the Shift Manager in the Control Room. The CTL is responsible for communicating information concerning Plant conditions and operations to the TSC. 5.2.3. Operations Support Group 5.2.3.1 Operations Support Coordinator (OSC) The OSC reports to the Emergency Coordinator in the TSC. The OSC assesses Plant information from the Control Room and technical support staff to establish emergency team priorities and direct operation support activities. 5.2.3.2 Emergency Team Coordinator (ETC) The ETCs report to the Operations Support Coordinator in the TSC. The ETCs assist the Operations Support Coordinator in formation, briefing, direction, and tracking of emergency teams. The Fire Brigade and MERT continue to report and take direction from the Shift Manager in the Control Room. 5.2.3.3 Support Area Personnel Mechanical, Electrical, and I&C Supervisors and labor force assemble in the Support Area of the TSC and report to the Emergency Team Coordinators to form emergency teams as needed. 5.2.3.4 Stores Personnel An individual knowledgeable of the materials systems reports to the Operations Support Coordinator in the TSC. The Stores person is responsible for obtaining parts, supplies, and materials from the warehouse when needed. Page 40 of 139 RERP Rev. 045 5.2.4. Technical Assessment Group 5.2.4.1 Technical Assessment Coordinator (TAC) (Minimum Staffing) The TAC reports to the Emergency Coordinator. The TAC is responsible for technical assessment of Plant conditions to identify EALs and emergency mitigating recommendations to the EC. The TAC is also responsible for coordinating Protective Action Recommendations (PAR)s consistent with Plant Conditions with the Recovery Manager and Dose Assessment Coordinator in the EOF prior to the arrival of the PMC or PAC. 5.2.4.2 TSCLead Engineer (TLE) The TLE reports to the Technical Assessment Coordinator in the TSC. The TLE is responsible for assisting the TAC in directing and controlling the Engineering staff. 5.2.4.3 TSC Engineering Staff The TSC Engineering Staff reports to the Technical Assessment Coordinator in the TSC. They are responsible for diagnosing and analyzing potential and actual Plant problems, and providing recommended courses of action to the Technical Assessment Coordinator. These responsibilities include: assessment of core physics, thermal hydraulics, and general plant conditions. They may be dispatched to Plant areas for surveillance purposes as directed by the Technical Assessment Coordinator. 5.2.4.4 Engineering Status Board Logkeepers (ESL) The ESLs report to the TAC and are responsible for maintaining the logs and status boards for the Technical Assessment Group. 5.2.4.5 Chemistry Coordinator (CC) The CC reports to the Technical Assessment Coordinator and assumes responsibility for Plant Chemistry operations from the Shift Manager. The CC directs primary and secondary Chemistry operations (including post-accident chemistry), and non-radiological environmental monitoring. The CC ensures the Technical Assessment Coordinator is aware of Chemistry activities and provides input to the TSC Engineering Staff in assessing Plant Chemistry problems. The CC directs Chemistry Technician(s). 5.2.5. Health Physics Group 5.2.5.1 Health Physics Coordinator (HPC) (Minimum Staffing) The HPC reports to the Emergency Coordinator. The HPC is responsible for assessing on-site radiological conditions, reviewing radiological EALs, and directing in-plant radiation protection activities. Page 41 of 139 RERP Rev. 045 5.2.5.2 Support Area Personnel Radiation Protection and Chemistry Technicians and Supervisors assemble in the Support Area of the TSC to provide radiation protection support for on-site emergency activities and those qualified as Chemistry Technicians may assist the On-shift Chemistry Technician in sampling and analysis to identify the source and magnitude of the emergency. Personnel from the Support Area are also dispatched to the EOF to support off-site field monitoring operations and dose assessment. 5.2.6. TSC Communicator (Minimum Staffing) The TSC Communicator reports to the Emergency Coordinator and, when requested by the NRC, will man the ENS line. 5.2.7. Security 5.2.7.1 Security Coordinator (SC) The SC reports to the Emergency Coordinator in the TSC. The SC assumes overall Plant security responsibility from the Shift Security Supervisor and directs the Security Force through the Shift Security Supervisor. These responsibilities include access control, personnel evacuation and accountability, coordination of any off-site law enforcement agency involvement, and normal and emergency security activities in accordance with the Security Plan. 5.2.7.2 Security Force Security Personnel continue to operate within their normal on-shift organization under the direction of the Security Coordinator. 5.2.8. Administrative Support Group 5.2.8.1 Administrative Coordinator (AC) The AC reports to the Emergency Coordinator in the TSC. The AC is responsible for updating the Emergency Coordinator on status of the TSC activation or deactivation. The AC is also responsible for ensuring that technical documents are available, providing food and beverage needs, and ensuring continuity of resources for the On-site Emergency Response Organization. The AC coordinates activities with the Logistical Support Coordinator in the EOF. 5.2.8.2 Clerical Support Staff The Clerical Support Staff reports to the Administrative Coordinator in the TSC. They provide clerical support, perform log keeping, technical drawing retrieval, records filing, delivery of messages, and maintain non-technical status boards as directed. Page 42 of 139 RERP Rev. 045 5.2.9. Recovery Manager (RM) (Minimum Staffing) The RM has overall command and control of the entire Callaway Plant Emergency Response Organization. The responsibilities of the RM include:
  • Authorizing notifications to off-site agencies;
  • Assuming responsibility from the Control Room for making Protective Action Recommendations;
  • Authorizing personnel exposure in excess of 10CFR20 limits (The Emergency Coordinator also has this authority).
  • Establishing and maintaining communications with the Emergency Coordinator;
  • Requesting off-site support (e.g., NSSS, A/E, INPO, Federal, State, and local);
  • Ensuring responsibility for communications with off-site agencies is transferred from the Control Room to the EOF Emergency Response Organization (excluding NRC ENS communications);
  • Maintaining command and control over personnel in the EOF and providing considerations necessary for their safety;
  • Ensuring coordinated emergency response among Callaway Plant and off-site agencies; The responsibilities that the RM may delegate are indicated with an asterisk (*).
5.2.10. Protective Measures Group 5.2.10.1 Protective Measures Coordinator (PMC) The PMC reports to the Recovery Manager in the EOF. The PMC is responsible for formulating Protective Action Recommendations. The PMC is also responsible for assisting the Recovery Manager, State officials and Federal officials in the interpretation of any Plant related data. 5.2.10.2 Plant Assessment Coordinator (PAC) The Plant Assessment Coordinator reports to the Protective Measures Coordinator in the EOF. The PAC reviews Plant conditions and EALs to verify the adequacy of the existing Protective Action Recommendations and assists in formulating of new Protective Action Recommendations when necessary. 5.2.10.3 Plant Assessment Staff The Plant Assessment Staff reports to the Plant Assessment Coordinator in the EOF. They are knowledgeable on Plant equipment, systems, and operations. They may provide additional technical expertise while maintaining the status boards displaying Plant conditions. Page 43 of 139 RERP Rev. 045 5.2.10.4 Dose Assessment Coordinator (DAC) (Minimum Staffing) The DAC reports to the Protective Measures Coordinator in the EOF. The DAC is responsible for performing dose projection calculations based on effluent monitors and field data, directing Field Monitoring Teams, reviewing effluent based EALs and assisting the Protective Measures Coordinator in the formulation of Protective Action Recommendations. 5.2.10.5 Assistant Dose Assessment Coordinator (ADAC) The ADAC reports to the Dose Assessment Coordinator and assists in performing dose projection calculations based on effluent monitors and field data, directing Field Monitoring Teams, reviewing effluent based EALs and assisting the Protective Measures Coordinator in the formulation of Protective Action Recommendations. 5.2.10.6 Dose Assessment Staff The Dose Assessment Staff reports to the Dose Assessment Coordinator in the EOF. The Dose Assessment Staff is responsible for field monitoring team communications and updating radiological status boards. 5.2.10.7 Field Monitoring Teams Field Monitoring Teams are dispatched within the Emergency Planning Zone under the direction of the Dose Assessment Coordinator. They are responsible for making direct radiation measurements and collecting air samples to provide data for off-site dose assessment. In cooperation with the State Department of Health, Field Monitoring Teams also assist in collection of environmental sample media. 5.2.11. Logistical Support Group 5.2.11.1 Logistical Support Coordinator (LSC) The LSC reports to the Recovery Manager in the EOF. The LSC is responsible for contracting with off-site vendors for engineering services, materials, and services needed for emergency mitigation and restoration of the Plant. The LSC is also responsible for providing administrative and logistical support to all of the Emergency Response Organization. 5.2.11.2 Logistical Support Staff The Logistical Support Staff reports to the Logistical Support Coordinator in the EOF. The Logistical Support Staff is responsible for the development of specifications for repair parts, equipment, and services, locating materials and services needed, and expediting their delivery to the site. They may initiate purchase orders, contracts for services or whatever procurement means approved by the Recovery Manager to obtain goods and services to assist in mitigation and recovery of this situation. The Logistical Support Staff also provides administrative support to the EOF Emergency Response Organization. Page 44 of 139 RERP Rev. 045 5.2.12. Off-site Liaison Coordinator (OSL) The OSL reports to the Recovery Manager in the EOF. The OSL is responsible for receiving responding representatives from off-site agencies, assisting in meeting their communications and logistic needs, keeping off-site authorities up-to-date on on-site emergency response activities, along with other duties assigned by the RM. 5.2.13. EOF Communicator (Minimum Staffing) The EOF Communicator reports to the Protective Measures Coordinator (PMC) in the EOF and assumes off-site notification responsibilities from the Communicator in the Control Room. The EOF Communicator transmits Protective Action Recommendations and emergency notification updates to State and local agencies and other off-site authorities. 5.2.14. The Joint Public Information Group 5.2.13.1 Company Spokesperson The Company Spokesperson provides Callaway Plants official response during news conferences and media events. The Company Spokesperson has access to information pertaining to the emergency through the Recovery Manager and Emergency Coordinator. The Company Spokesperson is the companys approval authority for all emergency related information released to the media. 5.2.13.2 Technical Representatives The Technical Representatives report to the Company Spokesperson and provide technical information to the JPIC Editor and the Company Spokesperson. They may also assist the Company Spokesperson in presentation of information and answering questions during media briefings. 5.2.13.3 JPIC Coordinator The JPIC Coordinator reports to the Company Spokesperson and coordinates the release of Callaway Plant emergency information at the JPIC. The JPIC Coordinator provides support to the Company Spokesperson for media presentations. 5.2.13.4 JPIC Administrator The JPIC Administrator reports to the JPIC Coordinator, to assist in equipment setup and administrative duties for the JPIC organization. 5.2.13.5 JPIC Editor The JPIC Editor reports to the JPIC Coordinator and is responsible for composition of written information to be released. 5.2.13.6 JPIC Media Host The JPIC Media Host reports to the JPIC Administrator and is responsible to provide accommodations and support to the media. Page 45 of 139 RERP Rev. 045 5.3. Emergency Response Organization Support 5.3.1. Private Sector Organizations Callaway Plant has arranged for additional support during emergencies from private sector organizations through letters of agreement listed in Appendix C. 5.3.2. Governmental Organizations Callaway Plant coordinates emergency response planning with Federal, State and local organizations and agencies involved with emergency response within the Emergency Planning Zone of the Callaway Plant. Each participating organization is assigned specific responsibility and authority for both planning and emergency response. This includes notifications and information exchange between on-site and off-site organizations. Callaway Plant, as appropriate, notifies and exchanges information with off-site agencies when emergencies are declared at the Callaway Plant. This notification or exchange of information to off-site agencies does not signify a request for assistance. However, assistance is provided as discussed below by Federal, State, and local agencies, if specifically requested. 5.3.2.1 Federal Agencies In the event of an emergency, notifications and requests for assistance are made to various Federal agencies and organizations. The Recovery Manager or Emergency Coordinator is responsible for ensuring the required support is requested. Air transportation for responding personnel and equipment can be accommodated at Lambert Field Airport, St. Louis, Missouri and limited accommodations are available at Columbia Regional Airport near Columbia, Missouri. Rental cars are available at these locations. The following agencies may, depending on the emergency situation, require notification and provide assistance. 5.3.2.1.1 U. S. Nuclear Regulatory Commission (NRC) The NRC is promptly notified upon declaration of any emergency at the Callaway Plant. Notification is made to the NRC Headquarters Operations Officer (HOO), who is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. The HOO notifies appropriate NRC Headquarters and Regional personnel. The NRC responds to emergencies in accordance with guidelines of NUREG 0728, "NRC Incident Response Plan" and the Region IV Incident Response Supplement. The anticipated arrival time for NRC Region IV representatives is 4-6 hours. Office space and communications for NRC representatives are provided in the Technical Support Center and Emergency Operations Facility. Page 46 of 139 RERP Rev. 045 5.3.2.1.2 Department of Energy (DOE) The DOE provides assistance during emergencies at the Callaway Plant as requested by the NRC or the Federal Emergency Management Agency (FEMA). Generally FEMA notifies, requests, and coordinates the Federal response. The anticipated arrival times for DOE representatives and the DOE mobile laboratory, if requested, are 6-8 hours and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, respectively. Office space and communication facilities for DOE representatives are provided in the Emergency Operations Facility. 5.3.2.1.3 Federal Emergency Management Agency (FEMA) FEMA ensures the development of effective State and local radiological emergency response plans, and coordinates planning efforts with State and Federal agencies. During emergencies, FEMA is contacted by the State, coordinates Federal agency response, and assists the State in emergency response, if requested. SEMA, requests, and coordinates the FEMA response. In the event of a major emergency or disaster, requests by the Governor of Missouri for a Presidential declaration of emergency or disaster could occur. FEMA, under this declaration, coordinates overall direction of Federal resources that could be brought to bear to alleviate loss, hardship, or suffering of local communities or individuals affected by the situation. 5.3.2.1.4 United States Coast Guard (USCG) The Missouri River flows through southern sectors of the Plume Exposure Pathway (10-mile EPZ). As such, restricted access of river vessel traffic may be required as a dose savings measure during emergencies involving off-site releases of radioactive material. The Missouri State Emergency Management Agency (SEMA) notifies the USCG, District 2, of emergencies which may require such action. The USCG has the authority to restrict vessel traffic in such instances. 5.3.2.1.5 Federal Aviation Administration (FAA) The FAA provides support to an emergency at the Callaway Plant if air restrictions have to be made to provide for dose saving. The FAA has the authority to implement any restricted air space control over the affected area. Any request for restricting air space will be coordinated through the State Emergency Management Agency. The FAA, using National Weather Service data, also provides Callaway Plant with meteorological information should on-site meteorological instrumentation fail. Information which can be obtained is wind speed, wind direction, and forecasts as needed. Page 47 of 139 RERP Rev. 045 5.3.2.16 Radiation Emergency Assistance Center/Training Site (REAC/TS) The Radiation Emergency Assistance Center/Training Site (REAC/TS) is a part of the Department of Energy response network. REAC/TS provides treatment capabilities and consultation assistance on a 24-hour basis for medical emergencies involving radiation. 5.3.2.2 State Agencies Various State agencies have roles in emergency planning and emergency response for emergencies at Callaway Plant. The "key" State agencies are discussed in this section. For detail of the roles of other participating State agencies, refer to the Missouri Nuclear Accident Plan Callaway. 5.3.2.2.1 State Emergency Management Agency (SEMA) SEMA serves as the lead agency for developing and maintaining State emergency response plans and assists local jurisdictions in the development of local plans. SEMA, in cooperation with the Missouri Department of Health (DOH), develops and conducts emergency response training for State and local agencies with emergency response roles. At the declaration of any emergency at the Callaway Plant, the Plant notifies SEMA. SEMA, after verification of the emergency, notifies DOH and any other State agencies which may be required to respond. If a liquid radioactive release is involved, the State Department of Natural Resources is also contacted directly by the Callaway Plant. SEMA will contact the Federal Emergency Management Agency (FEMA). Information obtained from Callaway Plant and local authorities is utilized to evaluate the support required by the State for emergency response. SEMA operates from the State Emergency Operations Center (EOC) in Jefferson City, Missouri. A Forward Command Post (FCP) may be established at the Callaway Plant's Emergency Operations Facility. The FCP staff normally consists of representatives from SEMA and the DOH. Local agencies may also send representatives to the EOF to provide face to face communications with Callaway Plant and State authorities. The FCP relays pertinent information to the State EOC and local EOCs. SEMA may exercise control of the States response from either the State EOC or the FCP. Callaway Plant Protective Action Recommendations for the general public are made to SEMA and local authorities. DOH evaluates the recommendations and provides independent recommendations to local authorities. SEMA continues to coordinate the support of State agencies until DOH determines that State assistance is no longer required. Callaway Plant has provisions for receiving SEMA representatives at the EOF at the ALERT (or higher) emergency classification level. Page 48 of 139 RERP Rev. 045 5.3.2.2.2 Missouri Department of Health (DOH) DOH serves as the lead State technical assistance agency and works with SEMA in the development and maintenance of State emergency response plans and radiological response training programs. DOH develops and establishes State Protective Action Guides. DOH is also responsible for establishing a medical record system for personnel exposed to radiation in State responses to emergencies. As the lead State agency for technical response, DOH performs radiological monitoring, dose projections, advises State and local agencies about protective actions, determines exposure levels for State response personnel, determines the need for decontamination, coordinates emergency medical support, and provides information and guidance for the public through SEMA. SEMA notifies DOH of emergencies at the Callaway Plant. DOH representatives operate from the FCP in the EOF. Upon mobilization of DOH, the agency establishes communication with Callaway Plant and SEMA. Initial off-site radiological assessment by DOH is based on information provided by Callaway Plant. Subsequent evaluation of the off-site radiological condition is based on information provided by Callaway Plant, as well as current data obtained by State field monitoring teams, changes in meteorological conditions, and any available dosimetry data. This information is used by DOH when recommending protective actions to SEMA and local authorities. DOH continues directing technical response for the State including off-site radiological monitoring and surveillance until off-site conditions are at acceptable levels as defined by State Protective Action Guides Restorative Actions. Callaway Plant has provisions for receiving DOH representatives at the EOF at the ALERT (or higher) emergency classification. 5.3.2.3 Local Agencies Callaway Plant coordinates with SEMA in emergency planning and emergency response with four (4) counties, which partially lie within the Plume Exposure Pathway (10-mile EPZ), and with the City of Fulton. The county jurisdictions are Callaway, Gasconade, Montgomery, and Osage Counties. Each jurisdiction is responsible for its own emergency planning and response. The four counties and Fulton coordinate the plans and have prepared for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day operations during emergencies. Upon the declaration of any emergency at the Callaway Plant, the Plant notifies the dispatch centers of the four counties. Callaway Plant makes off-site Protective Action Recommendations to local authorities. The County Commissioners, who are responsible for directing EOC activities, evaluate these recommendations and implement protective actions for protection of individuals within their jurisdiction. This may include activation of the public alert system. Page 49 of 139 RERP Rev. 045 Callaway Plant has provisions for receiving local authorities at the EOF at the ALERT (or higher) emergency classification. The local authorities work closely with the State and company authorities in coordinating off-site activities. Office space and communication facilities are provided in the EOF. Callaway Plant dispatches Technical Representatives to the local Emergency Operations Centers, if requested. These individuals provide supplemental information, as may be requested by the local authorities, to assist in interpretation and explanation of technical information pertaining to the Callaway Plant. These Technical Representatives provide supplemental information and do not replace the communication or notification chain. Callaway Plant has obtained agreements with specific local organizations as listed in Appendix C. Page 50 of 139 RERP Rev. 045 Figure 5-1 On-Shift Emergency Response Sheet 1 of 1 Page 51 of 139 RERP Rev. 045 Figure 5-2 Emergency Response Organization (On-Site) Sheet 1 of 3 Page 52 of 139 RERP Rev. 045 Figure 5-2 Emergency Response Organization (EOF) Sheet 2 of 3 Page 53 of 139 RERP Rev. 045 Figure 5-2 Emergency Response Organization (JPIC) Sheet 3 of 3 Page 54 of 139 RERP Rev. 045 Figure 5-3 Functional Interfaces of Emergency Response Organizations Sheet 1 of 1 Page 55 of 139 RERP Rev. 045 Table 5-1 Emergency Staffing Requirements / On-Shift Emergency Response + Sheet 1 of 1 Min. Response Response Emergency Position Function Major Tasks Location
  1. Level Goal Initial Direction and Control of Plant Operations, Shift Manager Accident Assessment, Protective Action Decision UNUSUAL Immediate 1 Initial Emergency Management CR (Acting Emergency Coordinator) Making, Requesting Support, and Off-site Notification / EVENT (on-shift)
Communications Coordination Supervises Control Room Operators, Technical Support and Assessment, Fire Brigade Leader, and Monitors UNUSUAL Immediate Operating Supervisor 2 Supervision, Assessment, CR SPDS, and Off-site Notification / Communications EVENT (on-shift) Coordination UNUSUAL Immediate Reactor Operators 2 Plant Operations Plant Operations and Accident Assessment CR EVENT (on-shift) Operations Technician(s) and 5 Auxiliary Plant Operations and Emergency Team UNUSUAL Immediate Plant Operations Plant Areas Assistant Operations Technician(s) *** Members As Required, Fire Brigade Leader EVENT (on-shift) Emergency Repair, Off-Site Notifications/Communications UNUSUAL Immediate Other Operations Personnel 2 Repair & Corrective Action Coordination, Emergency Teams As Required , and Safe Plant Areas Shutdown EVENT (on-shift) Perform Surveys, Sampling, Monitoring, Analysis, Job UNUSUAL Immediate Health Physics Operations 1 Health Physics Operations Plant Areas Coverage, Emergency Team Support EVENT (on-shift) Evaluate effluent monitors and perform off-site dose UNUSUAL Immediate CR or Health Physics Technical Support 1 Health Physics Tech Support projections EVENT (on-shift) Plant Areas UNUSUAL Immediate Chemistry Technician 1 Chemistry Chemistry Sampling and Radiochemical Analysis Plant Areas EVENT (on-shift) Security, Accountability, UNUSUAL Immediate Shift Security Supervisor 1 Supervise Security Force per Callaway Security Plan On-Site Evacuation EVENT (on-shift) Plant Security, Accountability, UNUSUAL Immediate Security Force
  • Per Security Plan On-Site Evacuation EVENT (on-shift)
Notify Licensee, State, Federal, and Local Authorities, Notification/Communications UNUSUAL Immediate Control Room Communicator ** Call-out Of Support Personnel, Coordination Of CR Coordination EVENT (on-shift) Communications Search and Rescue, Emergency Repair Activities, Fire UNUSUAL Immediate Emergency Teams ** Repair and Corrective Actions On-Site Brigade, MERT EVENT (on-shift) + Any vacancy in an emergency position created by sickness or injury to any personnel already On-shift should be filled as soon as practical
  • As per Security Plan
    • Position(s) filled by existing personnel on-shift
      • The Fire Brigade Leader position is filled with the fifth Operations Technician. (Qualified as a Fire Brigade Leader.)
Page 56 of 139 RERP Rev. 045 Table 5-2 Emergency Staffing Requirements / Emergency Response Organization (On-Site/TSC) Sheet 1 of 6 Desired Response Response Response Emergency Position Function Major Tasks Goal + Goal + Location Number Level Normal Hours Off Hours Direction and Control of On-Site Emergency Emergency Coordinator # 1 Emergency Management Response, accident assessment and emergency ALERT 15 Minutes 75 Minutes TSC declarations Notifications/ TSC Communicator (ENS) # 1 Maintain NRC ENS Communications link ALERT 15 Minutes 75 Minutes TSC Communications Coordination of Direct Administrative/Clerical Support including Administrative Coordinator 1 ALERT 15 Minutes 75 Minutes TSC Administrative Support logistics, Coordinates Activation of Facility Records retrieval, document reproduction, Clerical Support Staff
  • Administrative Support ALERT 15 Minutes As Needed TSC messengers, filing, etc.
Directs Assessment of On-Site Radiological Health Physics Coordinator # 1 Radiological Assessment Conditions, Directs Radiological Support for ALERT 15 Minutes 75 Minutes TSC Emergency Activities Directs and Coordinates corrective and emergency Operations Support Coordination of corrective 1 maintenance, and Forms, Briefs and Debriefs ALERT 15 Minutes 75 Minutes TSC Coordinator actions by Emergency Teams Emergency Teams Obtains parts, supplies, and materials from Stores Personnel 1 Supply Support ALERT 15 Minutes 75 Minutes TSC Warehouse Emergency Team Coordinators Coordination of Emergency Directs Emergency Team formation, briefing, ALERT 15 Minutes 75 Minutes TSC
  • Mechanical 1 Teams dispatch, tracking and support
  • Electrical 1 Coordination and transfer of Control CR/TSC Liaison 1 Coordinate CR to TSC Communications ALERT 15 Minutes 75 Minutes information Room
+ Facility activation will be done as soon as practical. Facility Activation Goals for the TSC and EOF are 90 minutes for off hours and 30 minutes during normal working hours (assumes 15 minutes from arrival at the facility). Response times may vary due to inclement weather and/or road conditions.
  1. Minimum positions needed for facility activation. A facility is considered activated when designated minimum personnel are ready to assume their responsibilities.
  • As needed Page 57 of 139
RERP Rev. 045 Table 5-2 Emergency Staffing Requirements / Emergency Response Organization (On-Site/TSC) Sheet 2 of 6 Desired Response Response Response Emergency Position Function Major Tasks Goal + Goal + Location Number Level Normal Hours Off Hours Technical Support and Directs technical analysis of plant conditions to Technical Assessment 1 Recommendations for formulate EAL and emergency mitigating ALERT 15 Minutes 75 Minutes TSC Coordinator # Emergency Declarations recommendations to the EC Assist TAC in command and control of Engineering TSCLead Engineer 1 Supervise Engineering Staff ALERT 15 Minutes 75 Minutes TSC Staff Engineering Maintains logs and status Maintains logs and statusboards for Technical 3 ALERT 15 Minutes 75 Minutes TSC Statusboard/Logkeepers boards Assessment group TSC Engineering Staff
  • Mechanical Engineer 1 Engineering evaluation of Analyze Plant Engineering Problems, Recommend
  • Electrical Engineer 1 Plant Systems and courses of Action, Maintain Technical Status ALERT 15 Minutes 75 Minutes TSC
  • Reactor/Nuclear Engineer 1 Conditions Boards, Evaluate EALs
  • I&C Engineer 1 Direct primary and secondary Chemistry activities, Chemistry Coordinator 1 Chemistry Support ALERT 15 Minutes 75 Minutes TSC evaluate chemical conditions Security Coordinator 1 Security Direct Security activities per Security Plan ALERT 15 Minutes 75 Minutes TSC See On-shift Emergency UNUSUAL See Table 5-1 Immediate Immediate Table Response EVENT 5-1
+ Facility activation will be done as soon as practical. Facility Activation Goals for the TSC and EOF are 90 minutes for off hours and 30 minutes during normal working hours (assumes 15 minutes from arrival at the facility). Response times may vary due to inclement weather and/or road conditions.
  1. Minimum positions needed for facility activation. A facility is considered activated when designated minimum personnel are ready to assume their responsibilities.
Page 58 of 139 RERP Rev. 045 Table 5-2 Emergency Staffing Requirements / Emergency Response Organization (On-Site/TSC) Sheet 3 of 6 Desired Response Response Response Emergency Position Function Major Tasks Goal + Goal + Location Number Level Normal Hours Off Hours Emergency repair, search and rescue, firefighting, Support Area Personnel TSC team members, support emergency operations. Emergency Team Support ALERT 15 Minutes Support Including: Obtaining supplies and materials from the Area Warehouse Health Physics Coordinator, Radiological Support for Emergency Teams, TSC
  • Rad/Chem Support 14 Chemistry Coordinator, and additional radiological support, Field Monitoring ALERT 15 Minutes 75 Minutes Support Emergency Team Support Teams, Dose Assessment Staff, Chemistry activities Area TSC Evaluation and repair of mechanical problems
  • Mechanics 2 Mechanical repairs ALERT 15 Minutes 75 Minutes Support impacting plant operations Area TSC Evaluation and repair of electrical problems
  • Electricians 2 Electrical Repairs ALERT 15 Minutes 75 Minutes Support impacting plant operations Area TSC Evaluation and repair of I&C problems impacting
  • I&C Technicians 1 I&C Repairs ALERT 15 Minutes 75 Minutes Support plant operations Area
+ Facility activation will be done as soon as practical. Facility Activation Goals for the TSC and EOF are 90 minutes for off hours and 30 minutes during normal working hours (assumes 15 minutes from arrival at the facility). Response times may vary due to inclement weather and/or road conditions. Page 59 of 139 RERP Rev. 045 Table 5-2 Emergency Staffing Requirements / Emergency Response Organization (EOF) Sheet 4 of 6 Desired Response Response Response Emergency Position Function Major Tasks Goal + Goal + Location Number Level Normal Hours Off Hours Manage Overall Callaway Plant Emergency Response, Protective Action Recommendations, Recovery Manager # 1 Emergency Management ALERT 15 Minutes 75 Minutes EOF Off- Site Notifications and Communication, Interface with Off-Site Authorities Review and Validate Recommendation for Protective Measures Recommend Protective 1 Protective Actions using Plant Conditions and ALERT 15 Minutes 75 Minutes EOF Coordinator Actions to RM Off-Site Dose Assessments Direct Field Monitoring Activities, Calculate Dose Assessment 1 Dose Assessment Off-site Dose Projections, Perform Assessments, ALERT 15 Minutes 75 Minutes EOF Coordinator # Confirm PARs based upon Dose Projections Calculate Off-site Dose Projections, Perform Assistant Dose Assessment 1 Dose Assessment Assessments, Confirm PARs based upon Dose ALERT 15 Minutes 75 Minutes EOF Coordinator Projections Communicate with and Record Field Monitoring Field Team Communications, Teams data, coordinate team efforts as directed by Dose Assessment Staff 2** ALERT 15 Minutes 75 Minutes EOF Maintain Status Boards Dose Assessment Coordinator, maintain status boards, man the HPN Line when directed Plume tracking, collection of Field Monitoring Teams 2** radiological data from the Collect radiological environmental data as directed ALERT 15 Minutes 75 Minutes Mobile field + Facility activation will be done as soon as practical. Facility Activation Goals for the TSC and EOF are 90 minutes for off hours and 30 minutes during normal working hours (assumes 15 minutes from arrival at the facility). Response times may vary due to inclement weather and/or road conditions.
  1. Minimum positions needed for facility activation. A facility is considered activated when designated minimum personnel are ready to assume their responsibilities.
    • Can be filled from paged personnel and/or dispatched from personnel in the TSC Support Area.
Page 60 of 139 RERP Rev. 045 Table 5-2 Emergency Staffing Requirements / Emergency Response Organization (EOF) Sheet 5 of 6 Desired Response Response Response Emergency Position Function Major Tasks Goal + Goal + Location Number Level Normal Hours Off Hours Review of Plant Conditions Reviews and validates plant conditions and EALs to Plant Assessment Coordinator 1 and Recommendation of verify existing and formulate new protective action ALERT 15 Minutes 75 Minutes EOFPARs recommendations Recommend PARs based on Analyze and interpret plant conditions to Evaluate Plant Assessment Staff 2 ALERT 15 Minutes 75 Minutes EOF Plant Conditions PARs, Maintain Technical Status Boards Direct Support activities and assist in procurement Logistical Support Procurement of goods and of identified materials, initiate contracts for goods 1 ALERT 15 Minutes 2 Hours EOF Coordinator services and services, Provide Administrative and Clerical direction and support Logistical Support Staff Develop Purchase specifications, solicit bids for
  • Material Eng. Buyer, etc. 2 Procurement of goods and goods and services, Assist Logistical Support ALERT 15 Minutes 2 Hours EOF services Coordinator, Provide Clerical Support
  • Clerical Support
  • General Clerical Tasks Notifications/
EOF Communicator # 1 Off-site Notifications/Communications ALERT 15 Minutes 75 Minutes EOF Communications Coordinate activities of Coordinate: EOF Activities, Support for Local, Off-site Liaison Coordinator 1 Off-Site personnel working State and Federal Responders. Man EOF ALERT 15 Minutes 75 Minutes EOF at the EOF communication links. + Facility activation will be done as soon as practical. Facility Activation Goals for the TSC and EOF are 90 minutes for off hours and 30 minutes during normal working hours (assumes 15 minutes from arrival at the facility). Response times may vary due to inclement weather and/or road conditions.
  1. Minimum positions needed for facility activation. A facility is considered activated when designated minimum personnel are ready to assume their responsibilities.
  • As needed Page 61 of 139
RERP Rev. 045 Table 5-2 Emergency Staffing Requirements / Emergency Response Organization (JPIC) Sheet 6 of 6 Min. Response Response Emergency Position Function Major Tasks Location
  1. Level Goal +
Official Company representative, Obtain and Company Spokesperson 1 Media Interface disseminate emergency information, Conduct Media ALERT 2 Hours JPIC briefings Provide technical information to Company JPIC Technical Representatives 2 Technical Support Spokesperson, Provide technical input for media ALERT 2 Hours JPIC / EOF briefings and news releases Support the Company Spokesperson, Coordinate JPIC Coordinator 1 Public/Media Relations ALERT 2 Hours JPIC information on Callaway Plant with SEMA JPIC Administrator 1 Public/Media Relations Administration and Logistics of JPIC ALERT 2 Hours JPIC JPIC Editor 1 Public/Media Relations Composes written news releases ALERT 2 Hours JPIC JPIC Media Host 1 Public/Media Relations Accommodate Media Needs ALERT 2 Hours JPIC + Facility activation will be done as soon as practical. Facility Activation Goals for the JPIC is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for off hours and normal working hours. Response times may vary due to inclement weather and/or road conditions. Page 62 of 139 RERP Rev. 045 6.0 EMERGENCY MEASURES This chapter establishes the methodology of the emergency response, and is the basis for the Emergency Plan Implementing Procedures (EIP)s which define emergency actions to be taken at a specific level of emergency. Emergency measures follow a process which contains the following definable elements:
  • Recognition and Evaluation;
  • Classification and Declaration;
  • Notification;
  • Mobilization;
  • Assessment Actions;
  • Corrective Actions;
  • Protective Actions;
  • Aid to Affected Personnel;
  • Public Information.
6.1. Recognition and Evaluation Initial recognition of emergency conditions normally occurs in the Control Room. Emergency conditions are indicated by alarms, instrument readings, and/or reports to the Control Room. The Shift Manager, with assistance from the Operating Supervisor will evaluate the conditions through the use of established Emergency Action Levels (EAL)s to determine if an EAL has been reached or exceeded. 6.2. Classification and Declaration If the Shift Manager finds that a specific Emergency Action Level (EAL) has been reached or exceeded, the emergency will be classified, as defined in Chapter 4.0, and the appropriate emergency classification will be declared. Certain situations may require the Shift Manager to make a judgmental decision. If a judgmental decision is necessary, the Shift Manager should take into account:
  • Potential effects on-site and off-site;
  • Potential for the situation to escalate or de escalate;
  • Need for manpower augmentation;
  • Need to activate any Emergency Response Facilities.
Upon declaring an emergency, the Shift Manager assumes the position of Emergency Coordinator and announces to Control Room personnel that an emergency has been declared. An announcement is made over the public address system to inform site personnel of the situation. Page 63 of 139 RERP Rev. 045 6.3. Notification After the declaration of an emergency, the Emergency Coordinator ensures that notifications are made to:
  • Emergency Coordinator (TSC);
  • State and local notification points;
  • Nuclear Regulatory Commission;
  • Recovery Manager;
  • Institute for Nuclear Power Operations (at ALERT or higher emergency classification);
  • American Nuclear Insurers (at ALERT or higher emergency classification).
Initial notifications to the State and local authorities shall be initiated within 15 minutes after the declaration of an emergency. Periodic updates are made to the State and local authorities upon activation of the State and local Emergency Operations Centers. These follow up notifications should be made whenever significant changes in Plant status occur, or approximately every half hour when conditions are relatively stable. Follow-up notifications should be made with the same urgency as initial notifications when changes in Protective Action Recommendations are involved. When conditions are relatively stable and the Plant remains at an UNUSUAL EVENT, the follow-up notification frequency may be reduced with the consensus of SEMA and the EPZ counties. Updates and notifications should be shared with State and local authorities present in the EOF. Notifications inform the State and local authorities of the emergency classification, release information, plant status, Protective Action Recommendations, and radiological and meteorological data used to form protective action recommendations. 6.3.1. Emergency Coordinator (TSC) The Emergency Coordinator (TSC) is notified by the Shift Manager (Emergency Coordinator) upon declaration of any emergency classification. At a minimum, the following topics should be discussed:
  • Classification of the emergency (potential need to reclassify);
  • Current Plant status and actions taken;
  • Augmentation/Paging of Emergency Response Organization (necessary or required augmentation);
  • Notification of authorities.
6.3.2. Nuclear Regulatory Commission (NRC) Notification of the NRC will be initiated by a Communicator (upon direction from the Emergency Coordinator) utilizing the Emergency Notification System (ENS). Once communications with the NRC is established, it will be maintained until the NRC directs otherwise. Page 64 of 139 RERP Rev. 045 6.3.3. State and Local Notification Points 6.3.3.1 Local Notification Point Notification to the four counties (Callaway, Montgomery, Gasconade, and Osage) and the City of Fulton is initiated, upon direction from the Emergency Coordinator or Recovery Manager, by a Communicator simultaneously transmitting the notification to all the county Emergency Communications Centers (ECC)s via the Sentry Notification System. These ECCs are manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, 7 days per week. If a back up method of notification is needed, the Communicator may use the Back-up Radio System (BURS) or telephone to notify the ECCs. 6.3.3.2 State Notification Point The first notification to the State Emergency Management Agency (SEMA), upon direction from the Emergency Coordinator, is initiated by a Communicator via the Sentry Notification System. During off normal hours, notification to the State will be made using the State Notification Point Telephone. The State Notification Point will then call the Callaway Plant to verify the emergency. If verification is not received within approximately 30 minutes, the Communicator will re-initiate notification to the State Notification Point. The State Notification Point will notify SEMA. Once SEMA mans the State EOC or State Forward Command Post at the EOF, use of the State Notification Point for notifications or updates is discontinued. 6.3.3.3 State Department of Natural Resources The State Department of Natural Resources (DNR) receives direct notification from the Callaway Plant whenever an emergency is declared that involves a release of a radioactive liquid. This notification is initiated by a Communicator contacting the State Department of Natural Resources via commercial telephone. If there is no liquid radioactive release from the Callaway Plant, the State Department of Natural Resources is notified of the emergency by the State Emergency Management Agency as outlined in the Missouri Nuclear Accident Plan - Callaway. Page 65 of 139 RERP Rev. 045 6.4. Mobilization The number and types of personnel needed to mitigate the circumstances of an emergency will depend upon three factors:
  • Classification of the emergency (providing a relative indication of the severity);
  • Probability for the situation to escalate or de-escalate;
  • Specific nature of the emergency (e.g., radiological, equipment failure, natural disaster).
The classification of an emergency is utilized for determining the minimum number and types of personnel anticipated to be needed. The Emergency Coordinator determines if additional personnel are necessary to mitigate or terminate the events leading to or resulting from the emergency. If necessary, the Emergency Coordinator may augment/page portions of the Emergency Response Organization prior to their mandated time. EIPs provide for both the timely callout of the Emergency Response Organization (Chapter 5.0) and the staffing of their associated Emergency Response Facilities (Chapter 7.0). In addition to personnel needed to mitigate the consequences of the emergency, personnel are also needed to ensure an accurate and timely release of information to the media and general public. The Emergency Response Organization also provides for the timely dissemination of emergency information to the media and general public. For emergency classifications, where greater media interest is anticipated, provisions are made for establishing a Joint Public Information Center (JPIC) for more extensive coordinated media briefings and conferences. During normal working hours, plant alarms, the public address system, and the cellular paging system are the primary means of notifying plant personnel. If an ALERT (or higher) classification is declared during normal working hours, all qualified personnel report to their Emergency Response Facility and then unnecessary personnel will be dismissed. Some departments have policies or procedures that designate specific personnel to respond during normal working hours. Emergency response during off hours is by Emergency Response Duty Personnel and Emergency Response Augmentation Personnel. During off normal working hours, the plant alarms, public address system, and the cellular paging system are used to notify personnel. An automated calling system is an alternate or additional method of mobilizing selected ERO personnel. The Emergency Response Organization is notified via the Cellular Paging System. Emergency Response Duty personnel (Minimum Staffing) report to the TSC and the EOF within approximately 75 minutes to relieve the Control Room of emergency response functions not directly related to Plant operation. Emergency Response Augmentation Personnel respond to their designated facilities within approximately 75 minutes (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for some positions). Together, the Emergency Response Organization is capable of fulfilling all intended functions for each Emergency Response Facility as detailed in Chapter 7.0. Page 66 of 139 RERP Rev. 045 6.5. Assessment Actions Effective coordination and direction of all elements of the emergency response organizations, including public agencies, requires continuing assessment throughout the emergency. Initial assessment and emergency classification are most often the result of exceeding predetermined Emergency Action Levels as discussed in Chapter 4.0. The initial assessment of Plant conditions, radiation levels, and on-site/off-site consequences is conducted by the Shift Manager as the Emergency Coordinator. During off-normal hours the Emergency Coordinator initiates the augmentation/paging of the Emergency Response Organization based on the emergency classification. Assessment actions continue throughout the emergency. Continued assessment may result in reclassification of the emergency with applicable subsequent emergency response actions taken. Upgrading of the emergency classification depends on experience, judgment, and specific limits as specified in the Emergency Action Levels (EAL)s for each emergency class. 6.5.1. Assessment Action for Control of Plant Operations The existence of any emergency condition causes increased monitoring of Control Room instrumentation, particularly the indicated values that triggered the emergency, and those that may be related. A Safety Parameter Display System (SPDS) within the Control Room is immediately accessible to Control Room personnel to aid them in rapidly and reliably determining the safety status of the Plant. The Shift Manager is responsible for initial assessment actions. When advised of an abnormal situation, the Shift Manager's first priority is to put the Plant into a safe condition. The Shift Manager's initial action is to assess Plant indications in accordance with emergency operating procedures. These procedures are located in the Control Room for immediate access by Control Room personnel. The applicable Plant indications refer the Shift Manager to appropriate emergency operating procedures to be implemented by Plant operating personnel. The procedures reference the appropriate EIP for classification of the emergency (as applicable). During the assessment phase, the operability of the Emergency Core Cooling System and the Containment Cooling System is of immediate concern. Operability of these systems may determine initial Protective Action Recommendations made to off-site authorities and protective actions taken for on-site personnel. Verification of the automatic activation of other engineered safeguard features is also an immediate concern. If proper activation of the engineered safeguard features is needed and has not occurred, manual initiation will be accomplished in accordance with established procedures. Proper activation of the engineered safeguard features should provide reasonable assurance that the Plant has stabilized. Page 67 of 139 RERP Rev. 045 If a complete failure of one or more safeguards functions occurs with indications of adequate core cooling, some Protective Action Recommendations may be advisable based on current Plant conditions or the potential for conditions to degrade. Should conditions indicate inadequate core cooling or the potential for a radiological release above normal operating limits, Protective Action Recommendations to off-site authorities may be warranted. Assessment actions to determine the correct operability of principal components of the Emergency Core Cooling and Containment Cooling Systems, and to ascertain activation of the other engineered safeguard features, will be conducted according to established procedures. Plant conditions that indicate inadequate core cooling may require additional actions beyond those identified in the Emergency Operating Procedures. A transition to the Severe Accident Management Guidelines may be necessary should this occur. 6.5.2. Environmental Assessment for Protection of Health and Safety of the Public Incidents involving potential or actual releases of radioactive materials to the environment require special methods of assessment to ensure that responses are appropriate for protection of site personnel and the population at risk. Rapid assessment of potential or actual releases of radioactive materials to the environment is critical for deciding appropriate protective actions. This assessment is based upon Plant parameters and meteorological conditions. This capability will be on-shift. 6.5.2.1 Short Term Assessment Upon determination that the emergency involves an actual or potential release of radioactive material, dose projection calculations will be performed. Based on off-site dose projections and Plant conditions, the Emergency Coordinator or Recovery Manager provides off-site authorities with Protective Action Recommendations. To determine the off-site doses, a number of factors are considered. These consist of weather conditions, the amount of radioactivity being released or having the potential to be released, the release pathway, flow rate, and field monitoring data. The atmospheric stability class is based upon the present weather conditions and inputs from the Meteorological Instrumentation System (RD). Using the stability class, the correct atmospheric dispersion factors can be used to approximate air concentrations at various off-site locations. USNRCRegulatory Guide 1.145 has been used as guidance. Page 68 of 139 RERP Rev. 045 The amount of radioactivity being released, or having the potential to be released, can generally be determined utilizing the Radiation Monitoring System. The Radiation Monitoring System has the capability of determining the amount of radioactivity in the effluent and in various systems or areas of the plant, including inside of containment. In addition, isotopic analysis can be performed to determine the specific isotopic makeup of the RCS, containment atmosphere, and sump. Dose projections can be performed using Effluent or Process Radiation Monitor readings or isotopic analysis data. Emphasis can be placed on specific isotopes of concern. These isotopes include the isotopes specified in NUREG 0654, Rev 1. Using the above information, personnel can perform dose projections for situations involving an actual release of radioactive materials. Field Monitoring Teams are utilized to track and quantify plume dose rates. Field Monitoring Teams are equipped with radios, cellular phones, and Geographical Positioning Units. Field Monitoring Teams are also equipped with radiation monitoring instruments to evaluate actual off-site dose rates and airborne radioactivity concentrations. Data is reported by Field Monitoring Teams via radio to the EOF. Samples collected are returned to the EOF, or other locations designated by the Dose Assessment Coordinator, for further analysis as necessary. Field monitoring activities continue throughout the duration of the incident (as required) so that the need for protective measures can be quickly assessed. 6.5.2.2 Long Term Assessment Long term assessment of contaminated soil, vegetation, milk, and water is accomplished in accordance with EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents. 6.5.3. In-Plant Radiological Controls During the course of an emergency, normal Radiation Protection procedures shall be followed with the understanding that higher than normal radiation and/or contamination levels may be experienced. Deployment of Search and Rescue Teams, Emergency Repair Teams, Fire Brigade Teams, and Medical Emergency Response Teams under emergency conditions may require continued monitoring of in-plant radiation levels for the protection of on-site personnel. In an emergency, priority is given to supporting efficient accident mitigation. The Health Physics Technical Support Technician has the initial responsibility for in-plant radiological controls. Upon activation of the TSC, the Health Physics Coordinator has responsibility for in-plant radiological controls and provides direction to Radiation Protection personnel. Initial in-plant radiological controls may be based on Control Room instrumentation readings, Radiation Monitoring System (RMS) readings, and system status reports. Additional information concerning in-plant radiological conditions may be gained during the debriefing of emergency teams. Page 69 of 139 RERP Rev. 045 6.5.4. Reactor and Core Damage Assessment Assessment concerning the status of the reactor core is performed by the Shift Manager with the assistance of a Shift Technical Advisor (STA) qualified Operating Supervisor or Engineer. Initial assessment of core conditions is based on readings from Control Room instrumentation and assessment of SPDS data. Data which is assessed to determine core damage include:
  • Radiation Monitoring System readings;
  • Nuclear plant instrumentation readings; Continued assessment of core conditions is performed under the direction of the TAC when engineers arrive at the TSC.
6.6. Corrective Actions Plant procedures contain steps for preventive and/or corrective actions to avoid or mitigate serious consequences of an emergency. Instrumentation and control systems provide indications, recordings, and control of systems necessary for the safe operation of the Plant. These systems provide the operator with the information and controls needed to start up; operate at power; shut down the Plant; and if necessary, cope with abnormal operating conditions or emergencies. Control and display of information from these systems are centralized in the Control Room, and limited displays are accessible at the TSC and EOF. The information provided by this instrumentation provides a basis for emergency classifications. Corrective actions may also involve response by emergency teams such as the Fire Brigade and Emergency Repair Teams. 6.7. Protective Actions Protective actions are emergency measures taken to ensure that Callaway Plant personnel and the general public's health and safety are protected. Protective actions are initiated in the event actual or projected radiation or airborne radioactivity levels exceed predetermined values. 6.7.1. Protective Actions for Plant Personnel Protective actions for Plant personnel and visitors include alerting, accountability, access control and evacuation. Protective actions are taken to the degree appropriate whenever a radiological emergency has occurred, or may occur, which may result in concentrations of airborne radioactivity or radiation levels in excess of normal limits for a specified area or areas. In addition, protective actions are taken for other emergencies such as fires or natural disasters where personnel safety is threatened. Page 70 of 139 RERP Rev. 045 6.7.1.1 Alerting When an emergency is recognized and classified, the Plant Emergency Alarm is sounded and an announcement is made on the Plant public address system. The announcement includes the classification of the event, a brief description of the event, and the required actions to be taken by personnel. Announcements for each emergency classification are in the emergency implementing procedures. Alerting of Plant personnel is accomplished as soon as assessment actions permit proper evaluation of conditions and corresponding actions. At an Alert or higher classification, on-site sirens are sounded. 6.7.1.2 Accountability Personnel accountability is initiated at the discretion of the Emergency Coordinator during any of the emergency classifications. Accountability is the process of identifying personnel who remain within the Protected Area. Personnel inside the Protected Area are notified of accountability by the sounding of the Plant Emergency Alarm and an appropriate announcement. Additionally, on-site sirens are sounded. Accountability is accomplished by assembly or as part of the evacuation process. When accountability is ordered, all essential personnel are accounted for in their designated Emergency Response Facility. They will log in utilizing a Security badge card reader or by signing on a status board or roster. Non-essential personnel (including emergency response personnel not needed to fill emergency positions) will assemble or evacuate as directed. The Shift Security Supervisor then reports the names of missing or unaccounted personnel to the Emergency Coordinator via the Security Coordinator. If needed, a Search and Rescue Team would be formed. Accountability shall be accomplished within 30 minutes from the time the order is given. Accountability can be continuously maintained by controlling access, restricting activities, monitoring activities on status boards, and/or utilizing Security access readers. 6.7.1.3 Assembly When an assembly is ordered, non-essential personnel assemble at pre-designated assembly areas. Visitors in the Protected Area are the responsibility of their escorts. Visitors are to be escorted to the access facility and directed to leave the site. Certain visitors, such as NRC employees, government officials, or specialists assisting with the emergency, may remain in the Protected Area if specific approval is obtained. This approval will typically be from the Emergency Coordinator or the Security Coordinator. Page 71 of 139 RERP Rev. 045 6.7.1.4 Evacuation The decision to evacuate non-essential personnel is made by the Emergency Coordinator, but is required during a Site Area or General Emergency. In the event that radiological or meteorological conditions would create hazards for evacuating personnel, alternate measures (sheltering, delayed evacuation, alternate evacuation routes, etc.) should be considered. When an evacuation is ordered, all non-essential personnel proceed to their assembly areas until radiological conditions and personnel requirements are established. Non-essential personnel in the Protected Area exit through the Security Access Facility at which they entered and are monitored for contamination by the portal monitors as they pass through the access. If an alternate access point is used, manual frisking for contamination will be performed. Personal vehicles are used to leave the area. Security officers may assist in controlling vehicles leaving the parking lot. If radiological and meteorological conditions indicate that personnel or their vehicles may have been contaminated, they will be directed to a Reception and Care Center established by the State for monitoring and if necessary, decontamination. 6.7.1.5 Security and Access Control When a level of emergency has been reached that requires personnel accountability, the Shift Security Supervisor or Security Coordinator is responsible for limiting facility access to emergency response personnel only. Security personnel control access and screen personnel at Security stations established at access points to the Protected Area and EOF. When an evacuation has been ordered, Security will patrol to verify that all visitors (see exceptions in Section 6.7.1.3) and non-essential personnel have evacuated the Owner Controlled Area and the Exclusion Area. The Callaway County Sheriff's Department will provide access control in areas around the Plant in support of Plant Security. Access is authorized for: Callaway Plant employees having proper identification or driving a company vehicle; State and Federal personnel with State or Federal identification or driving an official government vehicle; and emergency vehicles (e.g., ambulance, fire trucks). 6.7.1.6 Monitoring and Decontamination Personnel are monitored for contamination at the Security access point as they depart the Protected Area. On-site emergency response personnel will be monitored for contamination (if required) at their respective emergency stations. Decontamination of on-site emergency response personnel will be conducted during the course of the emergency at the on-site decontamination facilities. These facilities are located in the proximity of the Health Physics Access Control Area. If a release above normal operating limits is in progress, non-essential personnel will be directed to designated Reception and Care Centers for monitoring and decontamination, if necessary. Page 72 of 139 RERP Rev. 045 6.7.2. Off-Site Alerting and Protective Actions The Recovery Manager recommends appropriate protective actions to off-site authorities. This is the responsibility of the Emergency Coordinator until the Minimum Staffing personnel arrive. The action which affords the higher level of dose avoidance is normally preferred. However, other technical factors such as release duration and plume arrival time are important considerations affecting off-site Protective Action Recommendations. Off-site authorities will decide which protective actions are to be implemented after considering the Plant's recommendation, recommendations from the State Department of Health (DOH), road and weather conditions, or other factors which may affect the implementation of protective actions for the public. 6.7.2.1 Alerting of the General Public Prompt notification of the general public, in the event of an emergency at the Callaway Plant, is essential to provide reasonable assurance that sufficient time is available to implement protective actions, if warranted (i.e., sheltering, evacuation). Close coordination is required between the Callaway Plant, the counties within the 10-mile EPZ, and the State (SEMA). Notifications and Protective Action Recommendations are made to enable SEMA and the risk counties (Callaway, Gasconade, Montgomery, and Osage) to evaluate the impact of the emergency on their populations. The decision to implement protective actions for the public within its jurisdiction rests with each county and the City of Fulton. The County Commissioners for each county and the Mayor of Fulton have the authority to activate the Public Alert System in their jurisdictions. If they decide that protective actions are to be implemented, the Public Alert System is activated to alert the populace to listen to the local Emergency Alert System (EAS) station for instructions. The system is activated from each county's Emergency Communications Center. Sample draft EAS messages for release to the public by State and county authorities are contained in the Missouri Nuclear Accident Plan Callaway, and the Radiological Emergency Response Plans of Callaway County/Fulton, Montgomery County, Osage County and Gasconade County. The Public Alert System consists of fixed sirens and tone alert receivers. The fixed sirens are placed in various populated locations within the Callaway Plant 10-mile EPZ. The remaining population is alerted by use of tone alert receivers. This system provides alerting to approximately 100% of the population within the 10-mile EPZ. This system is discussed in detail in Appendix H. Page 73 of 139 RERP Rev. 045 6.7.2.2 Protective Actions for the General Public The responsibility and authority for deciding protective actions for the general public rests with local emergency response organizations, according to the Missouri Nuclear Accident Plan Callaway. Appendix G of the RERP contains maps showing the demography of the Plume Exposure Pathway EPZ, and population evacuation sectors and evacuation routing within the Plume Exposure Pathway EPZ. When Plant conditions warrant (i.e., a release above normal operating limits requiring a protective action recommendation is imminent or occurring) a recommendation to take immediate actions, such as sheltering or evacuation, is made by the Emergency Coordinator or the Recovery Manager to the State (SEMA) and local authorities responsible for deciding upon and implementing protective actions. Recommendations for protective actions are based on both actual and potential releases, taking into consideration reactor core and containment conditions as well as the anticipated duration of the release and the plume arrival times. At the GENERAL EMERGENCY classification, the preferred protective action recommendation is to evacuate. Evacuation will be recommended by the Plant for the public within a two-mile radius and five miles downwind, as a minimum. Sheltering should only be considered for the following situations:
  • Travel conditions that would present an extreme hazard, or
  • For controlled releases from containment if there is assurance that the release is short term and the area near the plant cannot be evacuated before the plume arrives.
The Emergency Coordinator or Recovery Manager makes recommendations to the affected local authorities. The local authorities evaluate the recommendations in light of any constraints, determine the area(s) to be evacuated, and communicate instructions to the public via the Public Alert System and EAS. Implementation of protective actions for the general public is described in the Radiological Emergency Response Plans for Callaway County/Fulton, Osage County, Montgomery County, and Gasconade County, and in the Missouri Nuclear Accident Plan Callaway. 6.7.2.3 Post Plume Phase Protective Actions During the post plume phase of the incident, when the primary concerns are exposure to and possible ingestion of deposited radioactive materials, the extent of environmental contamination will be evaluated by the State Department of Health assisted by the utility. Protective actions recommended by the Department of Health will be based upon the comparison of field data to the limits established in EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents. Page 74 of 139 RERP Rev. 045 6.7.3. Use of On-Site Protective Equipment and Supplies A variety of protective equipment is available on-site to minimize radiological exposures, contamination spread, and firefighting hazards. Portable Radiation Protection equipment is available for both normal operations and emergency situations. The portable instrument pool is accessible for use from various site locations. Emergency equipment kits are designated for storage at specific Plant locations (i.e., Control Room, Technical Support Center, etc.) and the actual contents and quantities of each kit are delineated in and maintained in accordance with Plant Procedures. The contents of emergency equipment kits vary between kits due to storage location and intended application. 6.7.3.1 Respiratory Protection Equipment Supplies of respiratory protection equipment are available on-site. It is the responsibility of Radiation Protection and Chemistry personnel to determine when the use of respiratory protective equipment is appropriate and to select the correct type of equipment for conditions expected to be encountered. 6.7.3.2 Protective Clothing A quantity of protective clothing is maintained on-site for routine use and is available for use during emergencies. Protective clothing is intended to keep contamination off the clothing and skin of individuals, and to control the spread of contamination. Generally, Radiation Protection personnel identify contaminated areas and specify the appropriate protective clothing that is to be worn. During emergencies, protective clothing may be worn when entering known or potentially contaminated areas and is removed when exiting these areas. Protective clothing is also available as a replacement clothing should personal clothing become contaminated. 6.7.3.3 Emergency Dosimetry Emergency dosimetry is located in close proximity to all on-site Emergency Response Facilities. Dosimetry will be issued to emergency response personnel as instructed by Radiation Protection personnel. 6.7.3.4 Potassium Iodide (KI) Potassium Iodide (KI) may be taken as a blocking agent to reduce the uptake of radioiodine by the thyroid. Potassium Iodide is administered in accordance with procedures. Page 75 of 139 RERP Rev. 045 6.7.4. Contamination Control Measures 6.7.4.1 On-Site Area To prevent or minimize ingestion of radioactive materials deposited within the Protected Area, affected areas are isolated, as necessary. Details of contamination control measures, exposure to elevated airborne activity levels, and control of contaminated tools and equipment for on-site areas are contained in Radiation Protection Operating Procedures and Emergency Plan Implementing Procedures. 6.7.4.2 Off-Site For areas beyond the Exclusion Area Boundary but within the Emergency Planning Zone, Field Monitoring Teams will identify contamination and radiation levels. Areas where contamination levels exceed EPA 400 Guidelines will be isolated and access restricted to minimize dose to the general public below these levels. 6.8. Aid to Affected Personnel 6.8.1. Emergency Response Personnel Exposure Criteria Radiological exposure is kept as low as reasonably achievable. Radiation Exposure is controlled in accordance with procedures. Exposure records are maintained for Plant personnel by the Radiation Protection Department. This information is used in determining emergency team assignments. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides. Self-reading dosimeters are available for emergency workers in addition to OSLDs. Dosimetry is read at periodic intervals dependent upon radiation levels. The Operations Support Coordinator and Health Physics Coordinator are responsible for coordinating emergency team assignments. In all cases where personnel may exceed the 10CFR20 occupational limits, authorization will be in accordance with the Callaway Plant Radiation Protection Program. Radiation Protection personnel are also responsible for distribution of self-reading and permanent dosimetry devices to emergency response personnel and assuring accountability of each worker's dose. Page 76 of 139 RERP Rev. 045 6.8.2. Decontamination and First Aid Provisions have been made to assist personnel who are injured or who may be contaminated by radioactive material. Portable first aid kits are available at strategic locations. Selected on-shift personnel are trained in first aid. In addition, on-site decontamination areas equipped with decontamination supplies, and other specialized equipment are located near the Health Physics Access Control Area on the 1984' elevation in the Control Building. Personnel found to be contaminated undergo decontamination under the direction of Radiation Protection personnel. Where contamination and major injuries are involved, personnel are transported to off-site medical facilities where they will receive prompt medical attention. Waste fluids and wastes from decontamination of personnel or material are collected and handled as radioactive wastes. 6.8.3. Medical Transportation Ambulance service is available through agreement with the Callaway County Ambulance District. 6.8.4. Medical Treatment For treatment of injuries with radiological complications, Callaway Plant will utilize the Callaway Community Hospital. Backup facilities are provided by University Hospital & Clinics, Columbia, Missouri. 6.9. Public Information Public information is an integral part of emergency preparedness. Public information is recognized as a continuous responsibility, and programs have been developed to keep the public informed during normal operations and during emergencies. 6.9.1. Public Information During Emergencies The Public Information function of the Emergency Response Organization assures that a steady flow of accurate, timely information is initiated and maintained. Callaway Plant will maintain open communications with the public, public officials, employees, and other groups at all times. Meeting these goals requires close continuing coordination between all emergency response organizations. The JPIC Coordinator assumes the responsibility of obtaining and releasing emergency information. The Joint Public Information Center (JPIC) Organization supports formal news conferences where the Company Spokesperson presents the company's official responses and answers questions. Page 77 of 139 RERP Rev. 045 6.9.2. Rumor Control A Rumor Control Center is established in the JPIC by SEMA. The Rumor Control Center may be staffed at the ALERT classification. The Rumor Control Center is considered an extension of the JPIC and is considered a cooperative operation of Callaway Plant, the State of Missouri, and the affected local governments for the purpose of rumor control. The Rumor Control Center functions with several telephones operating from a single rumor control number. The number is publicized through the Emergency Alerting System (EAS) when the Rumor Control Center is functional. Public information materials also advise the public of the rumor control number. Page 78 of 139 RERP Rev. 045 Figure 6-1 Field Monitoring Team Map Composite (All Sections) Sheet 1 of 1 LEGEND GRID (N) LATITUDE
  • 1.14 M ILES
!~(. V A 08 - 0!1-93 PRIMARY HIGHWAY, HARD SURFACE GRI D (W) LO NGITUDE ~ 0 . 90 M ILES o~~tt~o~~:n) SECONDARY HIGHWAY, HARD SURFACE CHKO . IDAT£l FIELD MONITORING TEAM MAP N/A COMPOSITE UGHT*DUlY ROAD, HARD OR IMPROVED SURFACE SUPV . t 0 A1£ l SCALE : ( IN M ILES) N/1. APPO. (DATE I (U!C"'o' l CALLAWAY PLANT 1 Cl*ss Nil* RIVERS, CREEKS, STREAMS 4 5 UN ION ELECTRIC COMPANY[ ST . LOUI S. MO. FMT- 003 ['A* HIGHWAY I ROAD IDENTIFYING NUMBER Page 79 of 139 RERP Rev. 045 Table 6-1 Assessment Actions Sheet 1 of 1 Action Description Radiation levels, pressure, temperature, flow, and meteorological data are monitored. Reactor Operators can assess Plant status by observing sensor readout. Most
1. Surveillance of Control Room sensors have visual and audible alarms. Data is provided Instrumentation to the Emergency Coordinator as necessary for his assessment. Reactor Operators will take corrective actions as necessary. Certain key safety and Plant parameters are accessible at the EOF and TSC.
Accountability is the responsibility of the Shift Security Supervisor or Security Coordinator. Personnel
2. Personnel Accountability accountability is performed and maintained in accordance with security instructions.
Health Physics personnel perform these surveys. The radiation levels from the Area Radiation Monitors (ARM)s and ventilation monitoring systems are monitored to assist
3. In-plant Radiological Surveys in these evaluations. Contamination surveys of equipment and personnel are conducted with portable instruments from the emergency equipment kits or at routine storage locations.
4. Exclusion Area Boundary Surveys Handled by Field Monitoring Teams.
Dose assessment personnel use computers, effluent
5. Off-site Dose Assessment monitors, meteorological data, and data supplied by deploying Field Monitoring Teams.
Samples of various environmental media are collected and analyzed by Field Monitoring Teams deployed by the Callaway Plant and the Missouri Department of Health. Additional analytical capabilities are provided at normal
6. Environmental Monitoring on-site facilities and from a contract laboratory if required.
Data from the permanently deployed off-site/TLD environmental monitoring stations is also used to assess off-site consequences. In the case of actual or potential off-site consequences, the State and local authorities are immediately notified in
7. Assessment Reporting accordance with the Missouri Nuclear Accident Plan-Callaway. Local authorities use predetermined criteria to initiate various protective actions for the public.
Page 80 of 139 RERP Rev. 045 Table 6-2 Protective Action Guidelines Plume Phase (Early Phase) General Population Sheet 1 of 1 PAG Recommended Comments (projected dose) Protective Actions a b Evacuation (or, for some situations, sheltering) 1-5 rem Evacuation (or sheltering) should normally be initiated at 1 rem. a The sum of the Deep Dose Equivalent resulting from exposure to external sources and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the early phase. Committed Dose Equivalents to the thyroid and to the skin may be 5 and 50 times larger, respectively. b The preferred Protective Action is to Evacuate. Sheltering should only be considered for the following situations. Travel conditions that would present an extreme hazard, or for controlled releases from containment if there is assurance that the release is short term and the area near the plant cannot be evacuated before the plume arrives. Page 81 of 139 RERP Rev. 045 Table 6-3 Post Plume Phase (Intermediate and Late Phases) Recommended Protective Actions Sheet 1 of 1 a Projected Dose Protective Actions Comments (rem) First priority should be given to cleanup of residences of >0.5 in first year Apply dose reduction techniques. pregnant women who exceed these levels. b Relocate affected population. Evacuation should have 2.0 in first year Maintain evacuation in affected occurred during the Plume areas. Phase. If not, relocate. If the projected dose in any year Relocate affected population, after the first year is projected consider implementing dose to exceed 0.5 rem, implement 0.5 in any subsequent year reduction techniques, consider Protective Actions. decontamination of essential cases, consider long-term relocation. Apply dose reduction techniques. If the summation of all the projected doses exceeds 5.0 for 50 years Same as above. 5.0 rem, then Protective Actions should be implemented. a The projected sum of Deep Dose Equivalent from external gamma radiation and Committed Effective Dose Equivalent from inhalation of resuspended materials from exposure or intake during the first year. Projected dose refers to the dose that would be received in the absence of shielding from structures or the application of dose reduction techniques. b Persons previously evacuated from areas outside the relocation zone defined by the PAG may return to occupy their residences. Cases involving relocation of persons at high risk from such action (e.g., patients under intensive care) should be evaluated individually. Page 82 of 139 RERP Rev. 045 Table 6-4 1,2 Food Chain Considerations Recommended Protective Actions Sheet 1 of 1 3 Projected Dose Ingestion Protective Actions Comments (rem) Preventative Actions These levels are considered to >0.5 rem Whole Body Take actions to prevent or be action levels for dose from reduce the concentration of or the food chain. radioactivity in animal feeds, >1.5 rem Thyroid foodstuffs, and water supplies. Protective Actions should be implemented as a minimum at these levels. Removal of products from >5.0 rem Whole Body commerce, condemnation of Emergency Actions materials, possible storage for Projected Dose at or above or decay unless loss of food these levels requires these >15.0 rem Thyroid source presents a more severe protective actions. problem than uptake. 1 Guidance on Off-Site Emergency Radiation Measurement Systems. Phase 3 - Water and Non-Dairy Food Pathway (FEMA REP-13/May 1990) 2 Guidance on Off-Site Emergency Radiation Measurement Systems. Phase 2 - The Milk Pathway (FEMA REP-12/September 1987) 3 Table 1, FEMA REP-13/May 1990 Page 83 of 139 RERP Rev. 045 7.0 EMERGENCY RESPONSE FACILITIES AND EQUIPMENT This Chapter describes Emergency Response Facilities, communication systems, assessment equipment, protective facilities and equipment, decontamination facilities and supplies, medical and first aid facilities, and damage control equipment and supplies. 7.1. Emergency Response Facilities 7.1.1. Control Room (CR) The Control Room is the on-site location from which the Plant is operated and is the point for on-site emergency response direction prior to staffing of the Technical Support Center. The Control Room is designed to enable operators to startup, operate, and shutdown the Plant during both normal and emergency conditions. It is located on the 2047'-6" elevation of the Control Building and habitability systems are provided to permit access and occupancy during Design Basis Accidents. The Control Room contains:
  • Plant public address system stations;
  • Commercial telephone links;
  • Dedicated telephone links;
  • Sentry and Back-up Radio System (BURS);
  • Control Room Instrumentation;
  • Pertinent mechanical and electrical drawings;
  • Controlled copies of applicable portions of the Callaway Plant Operating Procedures;
  • Status boards;
  • Plant Radio Console;
  • Protective breathing apparatus;
  • Emergency radiological monitoring equipment; Measurements and indications of required Regulatory Guide 1.97, Rev. 2; variables are available in the Control Room.
Page 84 of 139 RERP Rev. 045 The Operations Field Office Conference Room, across the hall from the Control Room, is used as an extension to the Control Room in case of an emergency. On-shift personnel assemble in this room during an emergency, in order to minimize personnel in the Control Room. Personnel in this conference room are under the direction of the Control Room. If the Operations Field Office Conference Room becomes uninhabitable, then personnel will be moved to the Control Room or TSC as needed. 7.1.2. Technical Support Center (TSC) (Figure 7-1) The TSC is the central point for direction of the emergency response on-site. The TSC provides the main communications link between the Plant and other Emergency Response Facilities. The TSC is staffed by designated technical, engineering, management, administrative, and NRC personnel. During emergencies, the TSC operates uninterrupted to provide plant management and technical support to Plant operations personnel. The TSC also relieves the Plant operators of peripheral duties not directly related to reactor system manipulations. The TSC is located within the Protected Area, adjacent to the Service Building. It has adequate shielding and ventilation to ensure habitability during Design Basis Accidents. An emergency diesel generator allows facility operation during loss of off-site power. The following functions are performed at the TSC:
  • Management of on-site emergency response;
  • Direction of on-site Radiation Protection activities;
  • Direction of on-site emergency maintenance;
  • Direction of site personnel accountability and security;
  • Direction of site safety and hazards control;
  • Performance of engineering and technical analyses for Control Room support;
  • Assemblage of emergency repair/support personnel;
  • Briefing, dispatching and direction of emergency repair personnel.
The TSC has the capability to support Plant management and technical personnel assigned there during an emergency. The TSC has access to important Plant parameters as required in Regulatory Guide 1.97, Rev. 2, via the Plant Computer System. Dedicated communications are available with the Control Room, EOF, and NRC. The TSC has the capability to transmit data and facsimiles. The TSC has access to controlled copies of the necessary Plant records, operational specifications, procedures, Severe Accident Management Guidelines, as built drawings, schematics, and diagrams essential for evaluation of the Plant under accident conditions. These include the NUREG-0696 specified documents. Page 85 of 139 RERP Rev. 045 7.1.3. Emergency Operations Facility (EOF) (Figure 7-2) The EOF is where coordination between on-site and off-site emergency response activities is done, and is staffed by predesignated emergency response personnel. It is located approximately 1 mile west of the plant, and houses the Recovery Center and offices for governmental representatives, the NRC, and a room that can accommodate small briefings. The EOF is designed to be habitable under Design Basis Accidents. In the event the EOF becomes uninhabitable, a backup EOF will be established at the Ike Skelton Training Site southeast of Jefferson City, Missouri, approximately 25 miles southwest of the Plant site. The EOF has the ability for communications with the following:
  • Control Room;
  • Field Monitoring Teams;
  • Joint Public Information Center;
  • State and Local Government;
  • NRC;
  • Corporate Headquarters.
The EOF has data access through the Plant Computer System (PCS). The EOF also has facsimile transmission and reproduction capabilities. The EOF is equipped with a diesel generator to be used as a source of emergency power. The EOF will be used as an alternate assembly area during hostile action(s). 7.1.3.1 Backup Emergency Operations Facility (Figure 7-4) This facility is set up when needed in the State's Emergency Operations Center at the Ike Skelton Training Site southeast of Jefferson City, Missouri. In the event the EOF becomes uninhabitable, EOF resources are distributed between the TSC and the Backup EOF. 7.1.4. Joint Public Information Center (JPIC) A Joint Public Information Center is located at the Ike Skelton Training Site southeast of Jefferson City, Missouri. News media briefings can be held here. The facility, when activated, has necessary equipment for communications with the EOF and St. Louis Corporate Office Building. 7.1.5. Corporate Headquarters Support Additional corporate support of Callaway Plant emergency operations is available from the Nuclear Division and Corporate Communications Area of Ameren Corporation Headquarters in St. Louis, Missouri. Any needed corporate support is directed and managed through the EOF Emergency Response Organization. Page 86 of 139 RERP Rev. 045 7.1.6. County/City Emergency Operations Centers (EOC)s Portions of the counties of Callaway, Osage, Gasconade, and Montgomery are within the boundary of the Plume Exposure Pathway EPZ. Each county's EOC is the focal point of the local emergency response. The City of Fulton and Callaway County share an EOC. The EOCs are in the following locations:
  • Callaway/Fulton - Callaway County Law Enforcement Center, Fulton, Missouri;
  • Osage - Osage County Administration Building, Linn, Missouri;
  • Gasconade - Gasconade County Courthouse, Hermann, Missouri;
  • Montgomery - Montgomery County Courthouse, Montgomery City, Missouri.
7.1.7. State Emergency Operations Center (EOC) The State Emergency Operations Center is the primary point through which the governor, or his authorized designee, exercises overall control and coordination of off-site emergency response operations through SEMA. SEMA coordinates actions and operations involving response and coordinates resources required to support decisions affecting the emergency. The State EOC is located in the Ike Skelton Training Site southeast of Jefferson City, Missouri. A Forward Command Post may be set up and utilized in the Emergency Operations Facility. 7.1.8. Ameren Corporate Communications The Corporate Communications Function is located in the Ameren Corporation Headquarters in St. Louis, Missouri. Equipment available in this facility includes telephones and facsimile equipment. The facility and available equipment provide the capability to communicate with the JPIC and EOF, and to disseminate information to news media, selected interest groups, employees, and the general public. Page 87 of 139 RERP Rev. 045 7.2. Communications Systems The communications systems in use at the Callaway Plant are designed to provide a reliable and timely flow of information during normal operations and during emergencies. These communication systems are available, on a 24-hour basis, to on-shift and Emergency Response Organization personnel for any communications, notifications, or activations needed. To ensure communication system reliability during an emergency, the following provisions have been incorporated into the systems:
  • Redundancy;
  • Backup/alternate communication systems;
  • Dedicated communication systems.
In addition, many of these systems are in routine use, which lessens the probability of undetected system failures. The following sections provide a description of the communication systems available for use in the event of an emergency. 7.2.1. Public Address (PA) System The PA system is used for communications between the emergency teams, Control Room, TSC, and EOF, as required. The PA system specifics are explained in the Plant FSAR. 7.2.1.1 Alarms A multi tone generator capable of producing a number of alarms is incorporated within the PA system. These alarms can be heard throughout the Plant area. In high noise areas a blue flashing light is activated with the alarm. The alarms are activated from the Control Room as directed by the Shift Manager. The alarms are as follows:
  • Plant Fire Alarm - A "siren" used only in the event of fire emergencies;
  • Plant Emergency Alarm - A "yelp" sound used to alert site personnel of unusual or abnormal conditions;
  • Containment Evacuation Alarm - A "pulse" used to alert site personnel that conditions in containment necessitate immediate evacuation of containment.
These alarms are followed by a clarifying announcement. 7.2.2. Touchtone Telephone System The touchtone telephone system consists of telephone stations located throughout the plant site (including the EOF and Intake Structure). Information pertaining to the telephone system design and operation is contained in Chapter 9 of the FSAR. Page 88 of 139 RERP Rev. 045 This system is the primary means of communications between members of the Emergency Response Organization, and with outside organizations that may provide emergency response resources. 7.2.2.1 Cellular Phone Mobile communications with the Emergency Coordinator (TSC) is provided by a cellular telephone. The cellular telephone is accessed through the touchtone telephone system. During an emergency, the cellular telephone system may be utilized to contact and maintain communications with the Emergency Coordinator (TSC), corporate personnel, and used as a backup for Field Monitoring Teams. 7.2.2.2 Cellular Paging System Personal notification devices (e.g., pagers, cell phones, etc.) will be worn by the Emergency Response Organization in order to ensure adequate and timely response to the Plant during an emergency situation. 7.2.3. Communication Systems Three independent telephone systems are available for backup communications between the Emergency Response Facilities. Each system operates independently from the other systems and allows for conference calls between the members of that bridge line group. These bridge lines have a normal power supply and in the event of a loss of power they are supplied by the ERF's backup power supply. The three systems are described in the following subsections. 7.2.3.1 Technical Assessment Bridge Line The Technical Assessment Line is a bridge telephone line between the Control Room, Technical Support Center, and Emergency Operations Facility. This line is used to relay information concerning the Plant status. This line is normally used by the following:
  • Control Room/TSC Liaison;
  • Technical Assessment Group;
  • Protective Measures Group;
  • Operations Support Coordinator.
7.2.3.2 Dose Assessment Bridge Line The Dose Assessment Line is a bridge telephone line between the Control Room, Technical Support Center, Plant Computer Room, and Emergency Operations Facility. This line's primary use is to relay information concerning dose assessment activities. This line is normally used by the following:
  • Health Physics Technical Support Technician;
  • Health Physics Group;
  • Dose Assessment Group.
Page 89 of 139 RERP Rev. 045 7.2.3.3 Emergency Management Bridge Line The Emergency Management Line is a bridge line connecting the Emergency Operations Facility to the Technical Support Center and Control Room. This line's primary use is communication between emergency management personnel. This line is normally used by the following:
  • Recovery Manager;
  • Emergency Coordinator;
  • Control Room/Shift Manager.
7.2.4. Sentry Sentry is a computerized notification system. It allows a notification form to be completed on screen and transmitted to the four (4) EPZ counties and the State Emergency Operations Center. This system can be activated from the Control Room and EOF. Its backup is the Back-Up Radio System (BURS). 7.2.5. Back-Up Radio System (BURS) The Back-Up Radio System is a communication link between the Callaway Plant and off-site emergency response agencies. The primary use of this system is the backup notification of off-site agencies and the coordination of off-site activities during a radiological emergency. The system uses 800 MHz radios. There are radio control base units in the Plant Control Room, TSC and EOF, as well as each county EOC and the State EOC. The backup to this system is the commercial touchtone telephone system. Notifications may also be initiated through the Callaway County/City of Fulton EOC via the Security radio. 7.2.6. State and Local Forward Command Post Commercial telephones are available in the State and Local office at the Emergency Operations Facility (State and Local Forward Command Post). These telephones are used by the State and local representative to maintain communications with their respective Emergency Operation Centers. 7.2.7. Radio Communication Systems Callaway Plant maintains a plant radio system that is in routine use and available for use during an emergency. This system is in the Field Monitoring Team vehicles and is used to communicate during emergencies. 7.2.8. Emergency Communications with the NRC The NRC telephone network is part of the Federal Telecommunications System (FTS) network provided for government use. This network connects the Callaway Plant to the NRC in Bethesda, Maryland. It is installed on uninterruptible power sources for reliability. Page 90 of 139 RERP Rev. 045 7.2.8.1 NRC Emergency Notification System (ENS) The NRC Emergency Notification System (ENS) is an FTS telephone used for official communications with NRC Headquarters. The NRC Headquarters has the capability to patch into the NRC Regional offices. The primary purpose of this phone is to provide a reliable method for the initial notification of the NRC and to maintain continuous communications with the NRC after initial notification. ENS telephones are located in the Control Room, TSC, and EOF. 7.2.8.2 Health Physics Network (HPN) The Health Physics Network (HPN) is an FTS line used for official communication between the Plant and the NRC used primarily for the transmittal of radiological information. The HPN phones are located in the EOF and TSC. 7.2.8.3 Reactor Safety Counterpart Link (RSCL) The Reactor Safety Counterpart Link is an NRC phone line established to conduct internal NRC discussions on Plant and equipment conditions separate from Plant personnel. This is the channel by which the NRC Operations Center supports NRC reactor safety personnel at the site. In addition, this link may be used between the Reactor Safety Team Director and Callaway Plant management at the site. RSCL telephones are located in the EOF and TSC. 7.2.8.4 Protective Measures Counterpart Link (PMCL) The Protective Measures Counterpart Link is an NRC phone line established to conduct internal NRC discussions on radiological releases and meteorological conditions, and the need for protective actions separate from Callaway Plant. This is the channel by which the NRC Operations Center supports NRC protective measures counterpart personnel at the site. In addition, this link may also be used for discussions between Protective Measures Team Director and Callaway Plant management at the site. The PMCL telephones are located in the EOF and TSC. 7.2.8.5 Management Counterpart Link (MCL) The Management Counterpart Link is established for any internal discussions between the Executive Team Director or Executive Team members and the NRC Director of Site Operations or top level Callaway Plant management at the site. The MCL telephone is located in the EOF. 7.2.8.6 Emergency Response Data System (ERDS) The Emergency Response Data System is the channel over which the raw reactor parametric data is transmitted from the site to the NRC Operations Center. Page 91 of 139 RERP Rev. 045 The ERDS can be activated from the Control Room or from the Technical Support Center Plant Computer System terminals. 7.2.8.7 Local Area Network (LAN) Access The Local Area Network Access is established for access to any of the products or services provided on the NRC Operations Center's local area network. This includes technical projections, press releases, status reports, E-mail, and various computerized analytical tools. The LAN channel is located in the EOF. 7.3. Assessment Equipment This section describes on-site and off-site facilities and monitoring equipment used in initial and continuing assessment during an emergency. 7.3.1. On-Site Systems and Equipment 7.3.1.1 Natural Phenomena Monitors Natural phenomena monitors are grouped into the meteorological and seismic categories. 7.3.1.1.1 Meteorological System The Meteorological System meets the applicable requirements of NUREG-0654 (Rev. 1) and Regulatory Guide 1.23 Revision 1 (March 2007), to the extent described in Section 2.3 of the FSAR. The system has two redundant sets of instrumentation on one tower. The instrumentation is installed on two separate elevators allowing for one set to be accessed for maintenance while the other set is obtaining data. There is an emergency auto start electric generator should there be a loss of power. The system is maintained by the Plant Surveillance and Preventative Maintenance program. The National Weather Service in St. Louis, Missouri is available for additional and backup meteorological data. 7.3.1.1.2 Seismic Instrumentation Seismic instrumentation is provided to supply information necessary for the evaluation of the effects of earthquakes on the plant Seismic Category I structures, systems, and components. Readout is available in the Control Room. All seismic detectors operate on three orthogonal axes and are oriented with one axis vertical and one axis related to the major horizontal axis used in the seismic analysis of the Plant. This system is maintained by the Plant Surveillance System and Preventive Maintenance Program. 7.3.1.2 Radiation Monitoring System The two general Radiation Monitoring Systems in use at the Callaway Plant are the Process/Effluent, and Area Radiation Monitoring Systems. Page 92 of 139 RERP Rev. 045 7.3.1.2.1 Process/Effluent Radiation Monitoring System The purpose of the Process/Effluent Radiation Monitoring System is to monitor, record, alert, and control the release of radioactive materials that may be generated during the Plant's operation under normal or accident conditions. The Process/Effluent Radiation Monitoring System is a digital system. A Control Room minicomputer, detector assemblies, and local microprocessors are the main components of this system. The Control Room minicomputer is the central computer which continuously communicates with local microprocessors through redundant data highways, provides radiological status display, and performs various system alarm and control functions. A radiation monitor is comprised of a lead shielded detector assembly, a local microprocessor, and accessories. A detector assembly can have Particulate (P), Iodine (I), Gas (G) or Gamma detectors and check source channels, specific to the type of radiation monitor. Each channel generates signals proportional to the noted radiation levels. The local microprocessor processes these signals, computes average concentration levels for various time intervals, stores this data, transmits the data to the minicomputer upon request, and performs alarm and control functions. In addition each safety related monitor is directly connected to a Control Room digital display module for redundancy. The Process/Effluent Radiation Monitoring System includes the following types of monitors:
  • Airborne Radiation Monitors - These are off-line monitors which measure particulate, iodine, and noble gas radiation levels. These monitors are listed in the FSAR.
  • Liquid Radiation Monitors - These are off-line monitors which measure the concentration of gamma producing nuclides in a liquid stream. These monitors are listed in the FSAR.
  • Wide Range Gas Monitors (WRGM) continuously monitor the expected range of radioactivity levels of noble gases discharge through unit and radwaste building vents during normal and accident conditions. The monitors are designed to meet the requirements of Reg. Guide 1.97 Rev 2, NUREG-0578 and NUREG-0737.
  • Containment High Range Area Radiation Monitors - These monitors are designed to measure the gamma radiation level inside the containment area, before and after a LOCA. These monitors are listed in the FSAR.
  • Secondary Side Release Monitors (SSRM) continuously monitor for the steam released from the steam-generator power operated relief valves (PORV)s and the auxiliary feedwater pump turbine exhaust for gamma radiation levels. The monitors are designed to meet the requirements of Reg. Guide 1.97, Rev. 2.
Page 93 of 139 RERP Rev. 045
  • TSC and EOF building continuous air monitors are stand-alone monitors which monitor the work area for airborne radioactivity. An alarm function on the continuous air monitor would indicate the need for additional air sampling.
This would be performed using a portable air sampler to obtain grab samples. Air sample filter media would be analyzed to determine particulate and radioiodine concentration levels. Monitoring is designed to meet the requirements of NUREG-0696 and NUREG-0654. The monitors are not connected to the Control Room minicomputer and do not perform any control functions external to their own system. 7.3.1.2.2 Area Radiation Monitoring System The purpose of the Area Radiation Monitoring System (ARMS) is to monitor radiation levels in the power block where personnel may be required to work and alert against abnormal or high radiation levels in those areas. The ARMS also provides a record of radiation levels in expected high radiation areas as a function of time. The Area Radiation Monitoring System detects and measures ambient gamma radiation at various points. It also provides an audible and visual alarm in the areas monitored and in the Control Room, if area radiation levels exceed a specified limit or, if there is a malfunction in a monitor's electronic circuitry. The areas under surveillance are the ones where radioactive material may be present, stored, handled, or inadvertently introduced. These areas are listed in the FSAR. In addition, monitors are provided in the Control Room to alert the operators in the event that abnormal radiation levels are present. The radiation level is indicated locally at the detector, at the ARMS cabinets and the Plant Computer for recording. Since all of the ARMS are connected to common annunciator alarms, verification of which channel has alarmed is done at the ARMS cabinets in the Control Room or on the Plant Computer. 7.3.1.3 Portable Monitoring Equipment Portable monitoring equipment includes radiation detection instruments and air sampling equipment. 7.3.1.3.1 Portable Radiation Detection Instruments Low and high range instruments are available to measure gamma radiation levels from a fraction of a mrem/hr to 1,000 Rem/hr. Instruments for alpha, beta, and neutron radiation measurements are available. A listing of the instruments typically available is given in FSAR. Portable instruments are also used to monitor habitability in Emergency Response Facilities. Page 94 of 139 RERP Rev. 045 7.3.1.3.2 Portable Air Sampling Equipment Air samplers are available to collect low volume air samples for analysis of particulate and radioiodine concentrations. The air samples are initially analyzed in the field using a portable count rate instrument. Emergency radioiodine sampling is done with silver zeolite cartridges. With minimal interferences from noble gases, gross radioiodine concentrations as low as 1E-7 µCi/cc can be measured. 7.3.1.4 Personnel Monitoring Equipment Personnel monitoring is provided by use of dosimeters, direct reading secondary monitoring devices (SMDs), and portable survey instruments. Personnel entering the Radiological Controlled Area (RCA) are issued dosimeters which are used to measure exposure to beta gamma and neutron radiation. Dosimeters are analyzed on a periodic basis by Plant personnel. This provides the official record of personnel exposure to beta gamma and neutron radiation. SMDs are also worn by personnel in the RCA and provide a day-to-day estimate of personnel exposure. Both dosimeters and SMDs are available in selected Emergency Equipment Kits for emergency use. 7.3.1.5 Personnel Survey Instrumentation Personnel survey instrumentation consists of G-M count rate meters (contamination friskers), portal monitors, and a whole body counting system. Portable count rate meters (friskers) are available at checkpoints and other areas that can be used to determine the presence and location of contamination. Portal monitors are available at the normal exits from the RCA. The whole body counting system is readily available to quickly supply information concerning internal contamination levels. 7.3.1.6 Control Room Instrumentation Information necessary to monitor the nuclear steam supply system (NSSS), the containment system, and the Balance of Plant (BOP) is displayed on the operator's console and the various vertical boards located within the Control Room. Hot shutdown information is also displayed on the auxiliary shutdown control panel outside the Control Room. These indications include the information to control and operate the unit through all operating conditions, including anticipated operating occurrences, and accident and post accident conditions. 7.3.1.7 Analysis Capabilities Laboratory facilities include the Hot Chemistry Laboratory and Counting Room adjacent to the HP Office, the Radwaste Lab, and a Cold Chemistry Laboratory in the Turbine Building. These facilities are designed to handle all chemical and radiological sampling and analysis during all normal modes of operation. External laboratory services have also been retained for analysis of high activity and environmental samples. If utilized, the EOF would operate as a central collection point for the receipt and analysis of field monitoring data and environmental sampling media. Page 95 of 139 RERP Rev. 045 7.3.1.8 DELETED per Rev. 024 CN 01-005. 7.3.1.9 Protective Action Assessment Capabilities Two methods are available for determining the potential radiological impact to the general public following a major accident. Initial off-site protective actions can be based on plant conditions using Plant Parameter Based Assessment, or a Release Path Dose Assessment can be performed using plant effluent monitors and meteorological monitoring equipment. 7.3.1.9.1 Plant Parameter Based Assessment Plant parameters will be evaluated by Control Room personnel to determine potential radiological impact to the general public. Indications to monitor these parameters are available on the Plant Computer. The evaluation is performed using a status tree that provides immediate predetermined Protective Action Recommendations based on the magnitude of the radiological source term and the potential for a release above normal operating limits to the environment. The estimate of the source term is based on the degree of core damage and modifying factors. The potential for release is based on fission product barrier integrity. This approach provides a basis for making Protective Action Recommendations before a release actually occurs. 7.3.1.9.2 Release Path Dose Assessment Protective Action Recommendations based on plume exposure pathway dose projections can be developed, using a computer based model for atmospheric dispersion. The model uses wind speed and atmospheric stability classification to determine relative concentrations and transit times. Default isotopic mixes for predefined accident types, or an actual isotopic mix based on sample analyses can be used. Dose conversion factors are taken from the document EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, dated May 1992. Information from field monitoring teams, in-plant grab samples, or effluent monitor data from the Plant Computer System can be input to the program along with estimated release duration to calculate doses at the Exclusion Area Boundary and at two, five, and ten miles from the plant. 7.3.1.10 Plant Computer System (PCS) The PCS is designed to gather, store, and display data on the general condition of the Plant including information to perform release path dose assessment. This system is also able to display data from other Plant subsystems such as the Safety Parameter Display System (SPDS). The PCS is able to display data at the TSC, EOF, Balance of Plant Computer Room, HP Office, and the Control Room. The displays come in a variety of formats such as group displays, point displays, summaries, alarm review, video trend, and bar chart displays. Page 96 of 139 RERP Rev. 045 The PCS enables emergency response personnel assigned to the TSC and EOF to aid Control Room operators in assessing emergency conditions. The PCS can be used for:
  • Reviewing the accident sequence;
  • Determining appropriate mitigating actions;
  • Evaluating the extent of any damage;
  • Determining Plant status during recovery operations;
  • Evaluating Plant radiological conditions;
  • Evaluating process radiation monitors for plume exposure pathway dose assessment;
  • Evaluating meteorological conditions and effluent flow rates for release rate and atmospheric dispersion characteristics.
The PCS meets the data system requirements of NUREG-0696 and has the ability to call up the Plant parameters identified in Regulatory Guide 1.97. 7.3.1.11 Safety Parameter Display System (SPDS) The Safety Parameter Display System (SPDS) is an application on the PCS. The Safety Parameter Display System is designed to provide Control Room operators with centralized and easily understandable Plant safety information in order to aid them in rapidly and reliably determining the safety status of the Plant and in rapidly detecting abnormal operating conditions. The SPDS meets the requirements of NUREG-0696 and some of the monitored parameters include:
  • Reactivity control;
  • Reactor core cooling and heat removal from the primary system;
  • Radioactivity control;
  • Containment integrity.
The SPDS provides graphical displays containing minimum sets of key parameters representative of the Plant safety status during normal, heat up and cool down, and cold shutdown operations. More detailed information is provided on multiple supporting displays. The displays use color coding and pattern recognition techniques to indicate off normal values, and are validated and updated on an essentially real time basis. The SPDS interfaces with the PCS to access Plant data. Page 97 of 139 RERP Rev. 045 7.3.1.12 Containment POST LOCAHydrogen Monitoring System Each redundant hydrogen monitoring train in the hydrogen monitoring subsystem consists of a hydrogen analyzer and two associated sample lines with isolation valves inside and outside the containment. These sampling lines are designed to be free of water traps (runs where liquid could accumulate), and are equipped with sufficient heat tracing to prevent condensation of the sample being supplied to the analyzers. After the sample has been analyzed, it is returned to the containment. The analyzers are located in accessible areas outside of the containment. The operation of the hydrogen gas analyzer is based on the measurement of thermal conductivity of the gaseous containment atmosphere sample. The operation of the hydrogen monitoring subsystem is not limited due to radiation, moisture, or temperature expected at the equipment location. The containment post LOCAhydrogen monitoring system is powered by a safeguards (1E) bus. In case of loss of power the system is automatically transferred to an emergency diesel generator. 7.3.1.13 Fire Protection System The Fire Protection System provides a means for detecting, alarming, and extinguishing fires. Alarms are provided to warn personnel of a fire in a specific area and of an impending system initiation. The Plant is designed to be self-sufficient from a fire fighting standpoint, as indicated in the FSAR, and is not dependent on off-site support. However, additional support may be requested from the local volunteer fire agencies if needed. 7.3.2. Facilities and Equipment for Off-Site Monitoring Off-site monitoring is accomplished with portable equipment for measuring radiation and airborne radioactivity levels. This equipment is stored in Emergency Equipment Kits for field monitoring activities. To provide surveillance during the operation of the Plant, continuously operating air particulate samplers are located around the Plant. The particulate samplers are equipped with a charcoal TEDA impregnated cartridge. The cartridge is mounted behind the filter paper attachment. To monitor radiation exposure levels, dosimeters are mounted in various environmental locations. 7.4. Protective Facilities and Equipment Control Room shielding and ventilation are designed to allow personnel habitability during Design Basis Accident conditions. The TSC and EOF have shielding and ventilation similar to the Control Room for habitability during the course of an accident. Essential emergency equipment is available in or near the Control Room, TSC, and EOF. Page 98 of 139 RERP Rev. 045 7.5. Decontamination Facilities and Supplies There is a decontamination facility located within the Plant on elevation 1984 of the Control Building and in the EOF. Both facilities are equipped with shower and decontamination supplies. The EOF decontamination area drains are connected to a radioactive waste storage tank. 7.6. Medical and First Aid During Refuel Outages there is a First Aid Room on elevation 1984' of the Control Building and additional first aid supplies are located at various locations within the Protected Area. 7.7. Damage Control Equipment and Supplies Fire hose stations, extinguishers, and hydrants are strategically located throughout the Plant for use in the event of fire. Self-contained breathing apparatuses are available to Plant Personnel for firefighting or entry into airborne radioactivity areas, toxic gas areas, or areas void of oxygen. Page 99 of 139 b /1 ~ rvL lt- 0 0 0 U\~ EN ~ 0 0 0 000 0 0 DDOSIMETRY 0 0 0 WOMEN H E ISSUE AREA 0 0 BRIEFING ROOM tt2 c_ "----' ~ II GENERATOR ROOM I I Figure 7-1 000 0 0 OPS SUPPORT AREA L.':::::=====::~ Page 100 of 139 0 0 I I BRIEFINGc_ ME CHAN I CAL & Sheet 1 of 1 ROOM tt1 ELECTRICAL EQUIPMENT ROOM ~~II I I EMERGENC Y OPS. Ji Technical Support Center SECURIT Y COORD. SUPPORT ENTRANCE u IIIII..., ~- II~ PORTAL BATT. ROOM .......~ MONITOR I I 1\J 7 LIBRARY/ CON FEREN CE ROOM I ADMIN. I TECHNICAL ASSESSMENT HEALTH PH YSICS NRC OFFICE 1 1 I I I c_ I CAD-0286A I TECHNJ CAL SUPPORT CENTER 06 / 15 / 10 <T YPlCAL TSC LA YOUT) RERP Rev. 045 COMMUNI CATION EQUIPMENT ROOM FIELD MONITORIN G DIE SEL STOR AGE GENER ATOR PROTECTI VE ROOM ROOM ME AS URE S f-z f-w f-z:::< <( Vl z _, Vl w CLW MECHANIC AL w:::< Vl DOCUMENT S AND VlVl O Vl Vl <( ROOM ELE CTRI CAL ow ROOM Vl Vl <( (.) 0:: z rn u_~ 00::
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w ENTRANCE D ._~ C/) CONSTRUCTION ======l ENTRANCE ROAD TELEPHONE D BUILDING STORES II COOLING:D TOWER CENTRAL PROCESSING FACILITY EMERGENCY OPERATIONS FACILITY ENTRANCE C POWER BLOCK ENTRANCE A TECHNICAL TRAINING CENTER SUPPORT CENTER AMEREN UE PARKING LOT MAIN ACCESS FACILil'Y SERVICE BUILDING SWITCHYARD CALLAWAY PLANT FIGURE 7-3 EMERGENCY RESPONSE FACILITY LOCATIONS Page 102 of 139 RERP Rev. 045 Figure 7-4 Backup Emergency Response Operations Facility Sheet 1 of 1 JPIC in State EOC (Typical Layout) Rumor Control PMC FTCDAC Co. SpkrsTech Rep Recovery Manager JPIC Fax OSL/COMM Copier Telephone Operators Page 103 of 139 RERP Rev. 045 8.0 MAINTAINING EMERGENCY PREPAREDNESS The Callaway Plant Radiological Emergency Preparedness Program is administered under the direction of the Manager, Emergency Preparedness. Maintenance of this program consists of:
  • Review and updating of the RERP and associated implementing procedures;
  • Coordination of emergency response plans and activities between Callaway Plant, State, and local agencies;
  • Assurance of on-site RERP training;
  • Conduct of drills and exercises;
  • Assurance of maintenance of Emergency Response Facilities;
  • Assurance of maintenance and inventory of emergency equipment and supplies;
  • Assurance of the administration and maintenance program of the Public Alert System.
8.1. RERP Training Training for all emergency response personnel is divided into four training programs: RERP training for on-site personnel who respond during an emergency; RERP training for off-site personnel; news media orientation; and a Public Information Program. All training, including drills and exercises, shall provide for formal critiques in order to identify weak or deficient areas that need corrections. Any weaknesses or deficiencies that are identified shall be corrected. 8.1.1. RERP Training for On-site Personnel Responsibility for RERP training is jointly shared between the Training and Emergency Preparedness Departments. Plant personnel granted unescorted access to the Protected Area receives an orientation on the RERP. In addition, personnel who may be assigned emergency response positions within an Emergency Response Organization, receive additional RERP training, as necessary. Personnel must meet the minimum criteria for the required training as specified for the emergency position and identified in the EIPs. Periodic retraining, typically on an annual basis, is conducted to update the knowledge and skills of on-site and corporate personnel. Personnel who do not complete retraining within the specified period are disqualified. All classroom training is tracked and documented in accordance with Callaway Plant Training Procedures. Page 104 of 139 RERP Rev. 045 8.1.1.1 Training for Non-Emergency Response Personnel Non-emergency response personnel (individuals not assigned a position in the Emergency Response Organization) receive General Employee Training (GET) in accordance with the Callaway Plant Training Procedure. RERP topics to be taught during GET should include:
  • Duties and responsibilities of emergency response and non-emergency response personnel;
  • Emergency classifications;
  • Assembly areas;
  • Alarms;
  • Emergency response;
  • Accountability and evacuation.
8.1.1.2 Training for Emergency Response Personnel Emergency response personnel receive training and retraining specific to their positions in the Emergency Response Organizations. Initial training and retraining programs are provided for personnel responsible for:
  • Directing or coordinating the Emergency Response Organization (directors and coordinators);
  • Accident assessment;
  • Radiological monitoring and radiological analysis;
  • Security and firefighting;
  • Repair and damage control/corrective action;
  • First aid and rescue;
  • Transmission of emergency information and instructions.
8.1.1.3 Training for Emergency Preparedness Staff Training for personnel responsible for the Callaway Plant's emergency planning effort is provided by participation in industry, NRC, INPO, and FEMA sponsored emergency planning seminars and workshops. Emergency Preparedness staff also receives training necessary for unescorted access to the Plant and training necessary to perform emergency planning functions as assigned by the Manager, Emergency Preparedness. Page 105 of 139 RERP Rev. 045 8.1.2. RERP Training for Off-site Personnel Off-site RERP training is the responsibility of the Missouri State Emergency Management Agency (SEMA) in conjunction with the Department of Health and local county agencies. The Callaway Plant provides support to these agencies as requested. Initial and follow up training of State and local personnel who implement radiological emergency response plans is provided. The training is designed to enhance comprehension of the plans and procedures, and to orient personnel to their specific emergency response function. In addition, those emergency response personnel who will conduct activities within the Plume Exposure Pathway (EPZ) receive training on radiological exposure control to include dosimetry, management of total dose through exposure time limitations, reading and recording of personnel dose data, and the use of radioprotective drugs. Training for off-site firefighting personnel includes radiological hazards which may be encountered while fighting fires in the Plume Exposure Pathway. Personnel who receive training include the following:
  • Directors or coordinators and staff of the emergency response organizations;
  • Law enforcement, security, and firefighting personnel;
  • First aid and rescue personnel;
  • Medical support personnel;
  • Communications personnel.
For those local support services who may enter the site, Callaway Plant provides training which includes site access procedures and the identity (by position and title) of the individual who requests the services. 8.1.3. News Media Orientation Orientation of the news media is aimed at acquainting them with the emergency plans and definitions, points of news media contact in emergencies, identification of Public Information personnel, basic Callaway Plant information, basic radiation information, and other matters of interest. This program is done on an annual basis. Page 106 of 139 RERP Rev. 045 8.1.4. Public Information Program Callaway Plant has developed a Public Information Program to adequately inform those individuals located within the Plume Exposure Pathway EPZ. A variety of public information materials have been developed and distributed to appropriate locations throughout the EPZ. These materials have been prepared through a joint effort with State and local authorities and are updated as appropriate. These materials may include:
  • Public information materials distributed to each residence within the EPZ and placed in locations frequented by transient populations;
  • Information placed in high visibility publications such as local newspapers;
  • Informational signs posted in areas frequented by transient populations such as the Reform Wildlife Management Area and Missouri River Accesses; Information booklets distributed with Tone Alert Radios.
At least annually, Callaway Plant, in conjunction with State and local authorities, reviews and updates the public information material and distributes it to individuals residing in the Plume Exposure Pathway EPZ. 8.2. Drills and Exercises Drills are supervised instruction periods aimed at testing, developing, and improving emergency response skills. Periodic drills are conducted at the Callaway Plant to evaluate emergency response capabilities and test specific aspects of emergency plans, implementing procedures and equipment. Evaluations of these drills are conducted and deficiencies identified and corrected. Some drills are scheduled while others are unannounced. Drills are also held under varying weather conditions. Exercises test the integrated capability of the Emergency Response Organization as well as a major portion of the basic elements of the RERP. Exercises involving the Callaway Plant Emergency Response Organization, the State, and local jurisdictions within the Plume Exposure Pathway will be conducted biennially in accordance with NRC and FEMA guidelines. Off year functional drills are conducted between biennial exercises. Off-site responders are invited to participate in off year functional drills. The drill and exercise scenarios are varied from year to year such that all major elements of the RERP and the preparedness of the Emergency Response Organization are tested within a six (6) year period (exercise cycle). Contingent on FEMA review and acceptance, during an exercise cycle, one of the three exercises will consist of a security based event. If the exercise includes State and local participation, plans for mobilization of personnel and resources adequate to verify their capability are coordinated with appropriate State and local authorities. Periodically, arrangements will be made for federal agencies to participate in exercises. Provisions are also made to start an unannounced drill or exercise between 6:00 p.m. and 4:00 a.m., once every six (6) years. Page 107 of 139 RERP Rev. 045 Each year, the following objectives will be met by the radiological emergency response drills and/or biennial exercise:
  • Demonstrate the ability to perform accident detection and assessment;
  • Demonstrate the ability to classify an emergency;
  • Demonstrate the ability to notify on-site and off-site emergency response personnel;
  • Demonstrate primary communications between the Plant, its various facilities and other emergency response organizations;
  • Demonstrate emergency radiological controls;
  • Demonstrate the ability to make Protective Action Recommendations to off-site authorities;
  • Demonstrate the ability to augment emergency response organizations;
  • Demonstrate the ability to staff the On-shift Emergency Response Organization.
The scenarios for use in exercises and selected drills include, but are not limited to, the following:
  • Basic objectives, guidelines, and evaluation criteria;
  • Participating organizations, date, time, and places;
  • A sequence of real and simulated events, and associated parameters and data;
  • A narrative summary describing the conduct of the exercises or drills to include such things as: simulated casualties, rescue of personnel, use of protective clothing, and deployment of radiological monitoring teams;
  • A description of the advance arrangements for materials to be provided to observers, controllers, and evaluators.
Drill and exercise scenarios are written to allow a certain amount of free play and decision making. Controllers are instructed at pre-drill or exercise briefings as to which portions of the scenario permit free play and which portions require control. One person is assigned as the Lead Controller and is responsible for overall drill or exercise control. The drill or exercise controllers should possess the necessary technical expertise to adequately control their respective functional areas. All drills and exercises are conducted and documented in accordance with the implementing procedure for drills and exercises or the Plant Preventative Maintenance and Surveillance Programs. Evaluators from the NRC and FEMA will be invited to evaluate and critique the exercises. A critique is scheduled at the conclusion of the exercise to evaluate the ability of organizations to respond as called for in the RERP. Formal evaluations are based on these critiques, including incorporation of participants' comments. Weak areas are noted, and corrective actions, including RERP and procedural changes and/or remedials, are initiated by the Manager, Emergency Preparedness or his designee. Page 108 of 139 RERP Rev. 045 8.2.1. Communications Drills Communications drills are tests performed and evaluated in accordance with the Plant Preventative Maintenance and Surveillance Programs. Communications with Federal, State and local governments will be tested monthly. Once a quarter, this will be done transmitting a simulated emergency notification to ensure the content of the message is understood. Field monitoring team communications are tested annually from the EOF and Backup EOF. These tests are done from different sectors in the field and also include the aspect of understanding message content. 8.2.2. Medical Emergency Drill A medical emergency drill involving a simulated contaminated individual, and providing for periodic participation by the local support service agencies (i.e., ambulance and off-site medical treatment facility) is conducted annually. The medical drill may be performed as part of the biennial exercise. 8.2.3. Radiological Monitoring Drills Plant environs and radiological monitoring drills (on and off-site) are conducted annually. These drills include collection and analysis of all sample media (e.g., water, vegetation, soil, and air) and provisions for communications and record keeping. Guidance is provided in the Plants surveillance program. 8.2.4. Health Physics Drills Health Physics related drills which involve response to, and analysis of simulated elevated airborne and liquid samples and direct radiation measurements in the environment are conducted semi-annually. 8.2.5. Fire Drills Fire drills are conducted in accordance with the Fire Protection Program. 8.2.6. Security Based Event Drill (COMN 50110, ULNRC-05189) Contingent on FEMA review and acceptance, security based event drills will be conducted in accordance with the guidelines established in NRC Bulletin 2005-02 (ULNRC-05189). Page 109 of 139 RERP Rev. 045 8.3. Review and Updating of the RERP and EIPs The Emergency Preparedness staff has responsibility for the development and updating of the RERP and its EIPs. Revisions to the RERP and associated EIPs are accomplished and distributed to appropriate organizations, agencies, and individuals in accordance with Plant procedures. Also, changes made to the RERP and EIPs are marked or documented to indicate the sections or areas changed in accordance with appropriate Plant procedures. The Senior Director Nuclear Operations reviews and approves changes and modifications to the RERP and its EIPs. Telephone numbers in the EIPs will be reviewed quarterly to ensure notifications, communications, and callout of emergency response personnel can be effectively facilitated. The Manager, Emergency Preparedness is responsible for assuring that the RERP and letters of agreement/purchase orders in the RERP are reviewed annually. The RERP and the letters of agreement are updated periodically, as needed, to maintain these documents in current condition. The Manager, Emergency Preparedness or designee, ensures through letters, meetings, seminars, or other means available, that all elements of the total emergency response organization are informed of the RERP, the associated EIPs, and revisions thereto. 8.4. Review and Updating of the Emergency Preparedness Program Problems, deficiencies, and areas needing improvement may be identified in a number of ways. These include but are not limited to: drills and exercises, regulatory changes, self-assessment, technical review, individual staff use or review, evaluations and tests, training, etc. The Manager, Emergency Preparedness, or a designee, is responsible for evaluating these comments and recommendations. Any deficiencies, recommendations, or improvement items are tracked to ensure a satisfactory resolution in accordance with appropriate Plant administrative procedures. An independent review by persons who have no direct responsibility for implementation of the emergency preparedness program is performed at12 month intervals per 10CFR50.54(t). The review shall include an evaluation of the following:
  • Interfaces with State and local governments;
  • Drills and exercises;
  • Emergency response capabilities;
  • EIPs.
The results of the reviews along with recommendations for improvements are documented, reported to corporate and Plant management, and retained for a period of at least five (5) years. The portion of the review involving the evaluation for adequacy of interfaces with State and local governments is made available to the appropriate State and local governments. The Emergency Action Levels (EAL)s are reviewed annually with off-site officials to renew familiarity and discuss questions. Page 110 of 139 RERP Rev. 045 8.5. Maintenance and Inventory of Emergency Equipment and Supplies To ensure the operational readiness of emergency supplies and equipment, Plant personnel conduct inspections of emergency equipment and supplies designated for emergency use in accordance with the Plant Preventive Maintenance and Surveillance Programs. 8.6. Emergency Preparedness (EP) Organization The EP Organization is responsible for development, implementation, and maintenance of the Radiological Emergency Response Program. This organization, under the direction of the Manager, Emergency Preparedness, has the responsibility and authority to ensure that Callaway Plant is prepared to handle a radiological emergency. 8.6.1. Organization The Emergency Preparedness Organization consists of a Manager, Emergency Preparedness, and supporting staff. A brief summary of responsibilities of the EP staff is enumerated in the following sub sections. Members of the EP staff have the authority to perform the duties and responsibilities to which they are assigned. 8.6.1.1 Manager, Emergency Preparedness The responsibilities of the Manager, Emergency Preparedness include:
  • Overall responsibility for the Radiological Emergency Response Plan and Emergency Plan Implementing Procedures;
  • Ensuring coordination of emergency response plans and activities between Callaway Plant, State, and local agencies;
  • Ensuring that Plant staff receive training for handling radiological emergencies;
  • Ensuring development and implementation of a Drill and Exercise Program;
  • Ensuring arrangement, administration, and maintenance of Emergency Response Facilities and emergency response equipment;
  • Ensuring development and implementation of the Public Alert System Maintenance Program;
Page 111 of 139 RERP Rev. 045 8.6.1.2 Emergency Preparedness Staff The Emergency Preparedness staff reports to the Manager, Emergency Preparedness and is generally responsible for planning and administering emergency planning activities. These responsibilities include:
  • Review and update of the RERP and EIPs, ensuring that information and data in the RERP and EIPs are consistent with each other and with federal regulations and guidelines;
  • Coordination of activities and emergency response plans between Callaway Plant, State, and local agencies;
  • Coordination of radiological emergency response drills and exercises;
  • Maintenance of Emergency Response Facilities and emergency response equipment;
  • Coordination of maintenance activities affecting the Public Alert System.
The EP staff consists of Callaway Plant employees knowledgeable in emergency planning regulations, Plant operations, health physics, and/or other related disciplines. Page 112 of 139 RERP Rev. 045 9.0 RECOVERY In any emergency situation the immediate concern is to limit the consequences of the incident such that the health and safety of the public, Plant personnel, and protection of equipment and property is afforded. Once the proper actions have been taken and control of the situation is established, emergency activities may shift to recovery activities. Recovery activities are directed to safely restore the Plant as nearly as possible to its pre-emergency condition. This chapter establishes criteria to be utilized for determining when to enter into a recovery phase and provides guidance for establishing a recovery organization and directing recovery operations. 9.1. Transition from Emergency Operations to Recovery Operations Certain conditions must be evident prior to shifting from emergency operations to recovery operations. A recovery organization can be established when Plant conditions are stable and no longer present a potential or actual hazard to the general public, and damage to the Plant has been substantially reduced. The Emergency Coordinator informs the Recovery Manager when the conditions are such that recovery can be declared. The Emergency Coordinator or Recovery Manager notifies the NRC of the intent to declare recovery prior to declaration, if possible. The following criteria sets guidelines for determining when recovery is to be declared and a recovery organization (if necessary) put into effect:
  • In-plant radiation levels are stable or decreasing with time, and
  • The reactor is stable with adequate core cooling capability, and
  • Releases of radioactive materials to the environment are controlled and within radioactive effluent controls limits, and
  • Fire, natural events, security threats, or similar emergency conditions are under control and Plant effects assessed.
The Recovery Manager evaluates the Emergency Coordinator's recommendation that transition into recovery operations begin. When the Recovery Manager concurs that recovery operations are to commence, the Recovery Manager ensures that the Emergency Coordinator notifies the On-Site Emergency Response Organization that recovery has been declared. The Recovery Manager also ensures that the EOF Emergency Response Organization and off-site authorities are informed of recovery declaration. The Emergency Coordinator and Recovery Manager determine the staffing requirements necessary to support recovery operations at the Plant. Once the requirements have been determined, the emergency organizations are modified appropriately to meet the need. The duties and responsibilities of the individuals who transferred into the Recovery Organization remain similar to those they had in the Emergency Response Organization. Some modifications may have to be made as required by recovery operations. The Recovery Manager determines the availability of any additional resources requested by off-site authorities to support off-site recovery activities. The Emergency Coordinator and Recovery Manager will ensure that on-site and off-site organizations are informed of recovery activities. Page 113 of 139 RERP Rev. 045 Emergency Plan Implementing Procedures, provide guidance for establishing and directing the Recovery Organization. These procedures may be used as issued or modified to meet the recovery needs. Additional procedures may also be developed as necessary to cover a particular recovery need. Once the Recovery Organization is established, "key members" of the organization direct the recovery efforts necessary to restore the Plant to its pre-emergency condition. If the Normal Plant Organization is capable of handling minor recovery activities, the Director, Nuclear Operations or his designee, may assume the responsibilities of the Recovery Manager for recovery operations. 9.2. Recovery Organization When emergency and post-accident conditions indicate that recovery efforts are complicated or long term, Callaway Plant will shift from Emergency Response Organization response to a long term Recovery Organization. A suggested basic structure for a long term Recovery Organization is shown in Figure 9-1; however, the specific make-up of the Recovery Organization is dependent on the nature, scope, and magnitude of recovery efforts necessitated by the emergency. Key recovery management responsibilities that may be considered are discussed in the following subsections. 9.2.1. Recovery Manager (RM) The Recovery Manager has overall control of recovery activities and directs recovery operations and would be vested with the authority to commit resources as necessary to support recovery efforts. The RM would coordinate the recovery with the Director, Nuclear Operations and off-site organizations and utilize input from these entities. 9.2.2. Operations Coordinator The Operations Coordinator would report to the Recovery Manager and be responsible for day-to-day Plant operations. The Operations Coordinator would coordinate recovery operations within the Plant to ensure that modifications and repairs are performed in a safe and competent manner. Requirements for reentry into affected and evacuated areas of the Plant during recovery would be established by the Operations Coordinator and evaluated and approved by the Recovery Manager. 9.2.3. Engineering Coordinator The Engineering Coordinator would report to the Recovery Manager and be responsible for providing and coordinating technical support to operations and recovery activities. This support includes core physics, thermal hydraulics, design activities, procedure development and also ensuring that specifications for procurement of materials and equipment are met. Page 114 of 139 RERP Rev. 045 9.2.4. Work Control Coordinator The Work Control Coordinator would report to the Recovery Manager and be responsible for normal and outage planning and scheduling activities to support recovery. 9.2.5. Licensing and Fuels Coordinator The Licensing and Fuels Coordinator would report to the Recovery Manager and be responsible for providing licensing and technical support to the recovery effort in areas of reactor systems and fuel related concerns. The Licensing & Fuels Coordinator would also be the liaison between Callaway Plant and the NSSS supplier, A/E, and other contractors. 9.2.6. Radiological Assessment Coordinator The Radiological Assessment Coordinator would report to the Recovery Manager and be responsible for coordinating activities involving Plant personnel or equipment, assisting the State Department of Health (DOH) in estimating and assessing total population exposure calculations, and coordinating off-site sampling and analysis. 9.2.7. Administrative Services Coordinator The Administrative Services Coordinator would report to the Recovery Manager and be responsible for ensuring that administrative, logistical, and personnel support is available to support recovery operations. 9.2.8. Public Information A Public Information Coordinator will be appointed by Corporate Communications to assist the Recovery Manager and the recovery effort. The position need not be physically located at the plant site. 9.2.9. Additional Support Additional support would include assistance from organizations external to Callaway Plant as well as other functions. Additional support would be available to the Recovery Manager from firms such as the Wolf Creek Nuclear Operations Corporation, the Institute of Nuclear Power Operations, and others as deemed necessary. Prearranged agreements with various organizations are on file as Letters of Agreement. Additional support can be provided by various Company organizations as necessary. This would be provided in a manner similar to normal operations, with the exception that other company management would be advised of the potential need for support during the early phase of a serious emergency. This gives these organizations additional preparatory time to support the recovery effort. Page 115 of 139 RERP Rev. 045 9.3. Objectives of the Recovery Organization During the initial stages of recovery, the organization would be prepared for 24-hour per day operations. As recovery activities progress, recovery operations may be geared to long term concerns and 24-hour per day operations may not be required. 9.3.1. Short-Term Objectives Initially, the Recovery Organization would focus on the following short term objectives:
  • Maintaining the Plant in a safe and stable condition;
  • Maintaining control of the release of radioactive material to the environment;
  • Maintaining control of personnel exposures;
  • Maintaining adequate communication with federal, State and local agencies;
  • Maintaining adequate capability to provide timely and factual information to the general public.
9.3.2. Long-Term Objectives After the short term objectives are addressed by the Recovery Organization, the long term objectives would focus on:
  • Restoring the Plant to its pre-emergency condition;
  • Providing for the storage and/or disposal of waste material generated during the emergency and recovery phases;
  • Evaluating the cause of the emergency, response to the emergency, and potential effects on future Plant operations.
9.4. Concept of Operations Administrative controls imposed on normal operations would be maintained during the recovery phase as conditions allow. Procedures would be generated for each specific operation and maintenance evolution and would be reviewed for nuclear safety concerns, personnel safety, and environmental impact by the Onsite Review Committee. 9.5. Reentry If an evacuation of personnel from any portion of the Plant is ordered during an emergency, reentry to the affected area(s) will be controlled utilizing pre-established guidance. In the event radiological conditions prevent normal access to areas, personnel will be informed of necessary equipment and pertinent information to ensure personnel safety and limit personnel exposure. If extensive training is required prior to reentry, personnel will receive formal training. This training could include: respiratory protection, ALARA, posting of areas, dosimetry, industrial safety, etc. Page 116 of 139 RERP Rev. 045 In the event that the general public was evacuated during the emergency, the Recovery Organization would assist the Department of Health (DOH) in the decisions to expand or relax Protective Action Recommendations. The Director, Nuclear Operations or Emergency Coordinator establishes requirements for reentry into affected and evacuated areas of the Plant prior to allowing personnel access. The Recovery Manager evaluates and approves the requirements prior to allowing reentry of personnel to those Plant areas. 9.6. Exposure Control During recovery, available information will be used to pre-plan work activities to ensure that the ALARA concept is achieved. Exposure to personnel will be documented in accordance with Radiation Protection procedures. During recovery operations, the Plant will assist the State Department of Health in estimating and assessing total population exposure when releases of radioactive materials have occurred. 9.7. Restoration The last element of a recovery program is restorative operations. The overall purpose of restoration is to prepare for resumption of full power operations. This facet of recovery would include a detailed investigation of the accident causes and consequences both to the Plant and the environment. Determinations would be made of the repair work required to perform necessary modifications to Plant equipment and/or procedures. Repair work and approved modifications would be carried out under appropriate authorizations. Tests would be performed to confirm that affected Plant systems are operable and acceptable for return to service. Page 117 of 139 RERP Rev. 045 Figure 9-1 Suggested Recovery Organization Sheet 1 of 1 Operations Coordinator On-Site Engineering (TSC) Coordinator Work Control Coordinator Recovery Q_ Manager Public Information Coordinator Radiological Assessment Coordinator Off-Site (EOF) Licensing & Fuels Coordinator Administrative Services Coordinator Page 118 of 139 RERP Rev. 045 Appendix A NUREG-0654/ Callaway Plant Radiological Emergency Response Plant (RERP) Cross-Reference Sheet 1 of 9 A. Assignment of Responsibility (Organization Control) NUREG-0654 Reference RERP Reference 1.a ............................................................................................................... 5.3 1.b............................................................................................................... 5.0 - 5.3 1.c ............................................................................................................... Figure 5-3 1.d............................................................................................................... 5.1, 5.1.1, 5.2.1, 5.3.1 1.e ............................................................................................................... 6.3 - 6.3.3.3 2.a ............................................................................................................... N/A 2.b............................................................................................................... N/A 3 ................................................................................................................... 5.3, Appendix C 4 ................................................................................................................... 5.0 - 5.2 B. On-Site Emergency Response Organization NUREG-0654 Reference RERP Reference 1 ................................................................................................................... 5.1 - 5.1.11.4, 5.2 - 5.2.8.2, Table 5-1, Figures 5-1 and 5-2 2 ................................................................................................................... 5.1, 5.2.1 3 ................................................................................................................... 5.1, 5.1.1, 5.2.1, 5.2.2.1 4 ................................................................................................................... 5.2.1 5 ................................................................................................................... 5.1, 5.2, 5.3, Tables 5-1, 5-2, and 5-3 6 ................................................................................................................... Figure 5-3 7.a ............................................................................................................... 5.2.8, 5.2.11 7.b............................................................................................................... 5.2.4, 5.2.10, 9.2.3 7.c ............................................................................................................... 5.2.9, 5.2.10.1, 5.2.12.1 7.d............................................................................................................... 5.2.13 8 ................................................................................................................... 5.3.1, Appendix C 9 ................................................................................................................... 5.3.2.3, Appendix C Page 119 of 139 Appendix A RERP Rev. 045 C. Emergency Response Support and Resources NUREG-0654 Reference RERP Reference 1.a ............................................................................................................... Appendix B 1.b............................................................................................................... 5.3.2.1 1.c ............................................................................................................... 5.3.2.1 2.a ............................................................................................................... N/A 2.b............................................................................................................... 5.3.2.3 3 ................................................................................................................... 5.3.2.1.2, 5.3.2.1.7, 5.3.2.2.2, 7.3.1.7, 7.3.1.8, 7.3.1.9.2, 7.3.2, Appendix C 4 ................................................................................................................... 5.0 - 5.3, Appendix C D. Emergency Classification System NUREG-0654 Reference RERP Reference 1 ................................................................................................................... Tables 4-1 and 4-2 2 ................................................................................................................... 4.1, 4.2, Table 4-1 3 ................................................................................................................... N/A 4 ................................................................................................................... N/A E. Notification Methods and Procedures NUREG-0654 Reference RERP Reference 1 ................................................................................................................... 6.3 2 ................................................................................................................... 6.3, 6.4 3 ................................................................................................................... 6.3 4 ................................................................................................................... Section 6.3, Figures 6-2 and 6-3 4.a - 4.n .................................................................................................. 6.3 5 ................................................................................................................... N/A 6 ................................................................................................................... 6.3.3, 6.7.2.1, Appendix H 7 ................................................................................................................... 6.7.2.2 Page 120 of 139 Appendix A RERP Rev. 045 F. Emergency Communications NUREG-0654 Reference RERP Reference 1.a ............................................................................................................... 6.3.3.1, 6.3.3.2, 6.3.3.3, 7.2.4, 7.2.5, 7.2.7 1.b............................................................................................................... 6.3.3.1, 6.3.3.2, 6.3.3.3, 7.2.4, 7.2.5, 7.2.7 1.c ............................................................................................................... 6.3.2, 7.2.8 1.d............................................................................................................... 7.2.2 - 7.2.7 1.e ............................................................................................................... 5.2, 5.3, 5.4, 6.4, 6.7.1.1 1.f................................................................................................................ 5.1.10, 5.2.6, 7.2.8 2 ................................................................................................................... 5.5.2.3, 7.2.5 3 ................................................................................................................... 8.2.1 G. Public Education and Information NUREG-0654 Reference RERP Reference 1 ................................................................................................................... 8.1.4 2 ................................................................................................................... 8.1.4 3.a ............................................................................................................... 6.9, 7.1.5, 7.1.8 3.b............................................................................................................... 7.1.3 4.a ............................................................................................................... 5.4.1 4.b............................................................................................................... 5.4, 6.9 4.c ............................................................................................................... 6.9.2 5 ................................................................................................................... 8.1.3 Page 121 of 139 Appendix A RERP Rev. 045 H. Emergency Facilities and Equipment NUREG-0654 Reference RERP Reference 1 ................................................................................................................... 7.1.2 2 ................................................................................................................... 7.1.3 3 ................................................................................................................... N/A 4 ................................................................................................................... 5.2, 5.3, 5.4, 6.4 5 ................................................................................................................... Tables 4-1 and 4-2 5.a ............................................................................................................... 7.3.1.1.1, 7.3.1.1.2 5.b............................................................................................................... 7.3.1.2, 7.3.1.3, 7.3.1.4, 7.3.1.5 5.c ............................................................................................................... Table 4-2, 7.3.1.6, 7.3.1.10, 7.3.1.11 5.d............................................................................................................... 7.3.1.13 6.a ............................................................................................................... 7.3.1.1.1, 7.3.1.1.2 6.b............................................................................................................... 6.5.2, 7.3.1.3, 7.3.1.4, 7.3.1.5, 7.3.2 6.c ............................................................................................................... 7.3.1.7 7 ................................................................................................................... 6.5.2.1, 7.3.2 8 ................................................................................................................... 7.3.1.1.1 9 ................................................................................................................... 7.1.2 10 ................................................................................................................ 8.5 11 ................................................................................................................ 6.7.3 12 ................................................................................................................ 6.5.2.1 Page 122 of 139 Appendix A RERP Rev. 045 I. Accident Assessment NUREG-0654 Reference RERP Reference 1 ................................................................................................................... Tables 4-1 and 4-2, 7.3 2 ................................................................................................................... 6.5.1, 6.5.2, 7.3.1.2, 7.3.1.8, 7.3.1.9, 7.3.1.10, 7.3.1.11 3.a ............................................................................................................... 6.5.2.1, 7.3.1.9.2 3.b............................................................................................................... 6.5.2.1, 7.3.1.2.1, 7.3.1.9.2 4 ................................................................................................................... Table 4-1, 6.5.2.1, 7.3.1.9.2 5 ................................................................................................................... 7.3.1.1.1, 7.3.1.9.2 6 ................................................................................................................... 6.5.2.1 7 ................................................................................................................... 5.3.2.5, 5.3.2.6, 6.5.2.1, 7.3.1.3.1, 7.3.1.3.2, 7.3.2 8 ................................................................................................................... 5.2.3.5, 5.3.2.6, 6.5.2.1, Table 5-2 9 ................................................................................................................... 6.5.2.1, 6.7.3 10 ................................................................................................................ 6.5.2.1, Tables 6-2, 6-3, and 6-4 11 ................................................................................................................ N/A Page 123 of 139 Appendix A RERP Rev. 045 J. Protective Response NUREG-0654 Reference RERP Reference 1.a ............................................................................................................... 6.7.1.1, 6.7.1.2, 6.7.1.5, 7.2.1, 7.2.1.1 1.b............................................................................................................... 6.7.1.1, 6.7.1.2, 6.7.1.5, 7.2.1, 7.2.1.1 1.c ............................................................................................................... 6.7.1.1, 6.7.1.2, 6.7.1.5, 7.2.1, 7.2.1.1 1.d............................................................................................................... 6.7.1.1, 6.7.1.5, 6.7.2.1, 7.2.1, 7.2.1.1 2 ................................................................................................................... 6.7.1.4 3 ................................................................................................................... 6.7.1.4, 6.7.1.6 4 ................................................................................................................... 6.7.1.4, 6.7.1.6 5 ................................................................................................................... 6.7.1.2 - 6.7.1.5 6.a ............................................................................................................... 6.7.3, 6.7.3.1 6.b............................................................................................................... 6.7.3.2 6.c ............................................................................................................... 6.7.3.4 7 ................................................................................................................... 6.5.2.1, 6.7.2.2 8 ................................................................................................................... Appendix G 9 ................................................................................................................... N/A 10.a ............................................................................................................ 6.7.2.2, Figure 6-1, Appendix G 10.b............................................................................................................ Appendix G and H 10.c ............................................................................................................ 6.7.2.1, Appendix H 10.d............................................................................................................ N/A 10.e ............................................................................................................ N/A 10.f............................................................................................................. N/A 10.g............................................................................................................ N/A 10.h............................................................................................................ N/A 10.i ............................................................................................................. N/A 10.j ............................................................................................................. N/A 10.k............................................................................................................ N/A 10.l ............................................................................................................. N/A 10.m .......................................................................................................... 6.7.2.2, Appendix G 11 ................................................................................................................ N/A 12 ................................................................................................................ N/A Page 124 of 139 Appendix A RERP Rev. 045 K. Radiological Exposure Control NUREG-0654 Reference RERP Reference 1.a ............................................................................................................... 6.8.1, 6.8.2 1.b............................................................................................................... 6.8.1 1.c ............................................................................................................... 6.8.1 1.d............................................................................................................... 6.8.1, 6.8.2 1.e ............................................................................................................... 6.7.4.1, 6.8.1, 6.8.2 1.f................................................................................................................ 5.4.3.1, 6.8.1, 6.8.2 1.g............................................................................................................... 6.8.2, 6.8.4 2 ................................................................................................................... 5.2.1, 5.3.1, 6.8.1 3.a ............................................................................................................... 6.7.3.3, 6.8.1, 7.3.1.4 3.b............................................................................................................... 6.8.1 4 ................................................................................................................... N/A 5.a ............................................................................................................... 6.7.4.1 5.b............................................................................................................... 6.7.1.6, 6.7.3, 6.7.4.1, 6.8.2 6.a ............................................................................................................... 6.7.4.1 6.b............................................................................................................... 6.7.4.1 6.c ............................................................................................................... 6.5.3, 6.7.4.1, 9.5 7 ................................................................................................................... 6.7.1.6, 6.7.3.2, 6.7.4.1, 6.8.2, 7.5 L. Medical and Public Health Support NUREG-0654 Reference RERP Reference 1 ................................................................................................................... 5.5.2.3, 6.8.2 - 6.8.4, Appendix C 2 ................................................................................................................... 6.8.2, 7.6 3 ................................................................................................................... N/A 4 ................................................................................................................... 5.5.2.3, Appendix C M. Recovery and Reentry Planning and Post Accident Operations NUREG-0654 Reference RERP Reference 1 ................................................................................................................... 9.1, 9.5 2 ................................................................................................................... 9.2 3 ................................................................................................................... 9.1 4 ................................................................................................................... 9.6 Page 125 of 139 Appendix A RERP Rev. 045 N. Exercises and Drills NUREG-0654 Reference RERP Reference 1.a ............................................................................................................... 8.2 1.b............................................................................................................... 8.2 2.a ............................................................................................................... 8.2.1 2.b............................................................................................................... 8.2.5 2.c ............................................................................................................... 8.2.2 2.d............................................................................................................... 8.2.3 2.e(1)........................................................................................................ 8.2.4 2.e(2)........................................................................................................ 8.2.4 3.a ............................................................................................................... 8.2 3.b............................................................................................................... 8.2 3.c ............................................................................................................... 8.2 3.d............................................................................................................... 8.2 3.e ............................................................................................................... 8.2 3.f................................................................................................................ 8.2 4 ................................................................................................................... 8.2 5 ................................................................................................................... 8.2 Page 126 of 139 Appendix A RERP Rev. 045 O. Radiological Emergency Response Training NUREG-0654 Reference RERP Reference 1 ................................................................................................................... 8.1 - 8.1.4 1.a ............................................................................................................... 8.1.2 1.b............................................................................................................... N/A 2 ................................................................................................................... 8.1.1, 8.2 3 ................................................................................................................... 8.1.1, 8.1.1.2 4.a ............................................................................................................... 8.1, 8.1.1.2 4.b............................................................................................................... 8.1.1.2 4.c ............................................................................................................... 8.1.1.2 4.d............................................................................................................... 8.1.1.2, 8.1.2 4.e ............................................................................................................... 8.1.1.2 4.f................................................................................................................ 8.1.1.2 4.g............................................................................................................... 8.1.2 4.h............................................................................................................... 8.1.2 4.i ................................................................................................................ 8.1.1.1, 8.1.1.2 4.j ................................................................................................................ 8.1.1.2 5 ................................................................................................................... 8.1.1 P. Responsibility for the Planning Effort: Development, Periodic Review and Distribution of Emergency PlansNUREG-0654 Reference RERP Reference 1 ................................................................................................................... 8.1.1.3 2 ................................................................................................................... 8.0, 8.3, 8.6.1.1 3 ................................................................................................................... 8.6, 8.6.1.2 4 ................................................................................................................... 8.3, 8.4 5 ................................................................................................................... 8.3 6 ................................................................................................................... 2.3, Appendix I 7 ................................................................................................................... Appendix F 8 ................................................................................................................... Table of Contents, Appendix A 9 ................................................................................................................... 8.4 10 ................................................................................................................ 8.3 Page 127 of 139 Appendix A RERP Rev. 045 Appendix B Policy Statement Scope of Authority and Responsibility of Emergency Coordinator and the Recovery Manager Sheet 1 of 1 In the event of an emergency which requires the implementation of the Callaway Plant Radiological Emergency Response Plan (RERP), the Emergency Coordinator and Recovery Manager are authorized and have the responsibility to:
a. Evaluate, classify, and declare emergencies;
b. Activate and direct the Emergency Response Organization;
c. Direct that off-site authorities be notified;
d. Make protective action recommendations for the protection of the general public and site personnel; and
e. Request off-site assistance.
Additionally, until such time that the emergency is terminated or control is assumed by a superior corporate officer, the Emergency Coordinator and Recovery Manager are vested with the authority to commit AmerenUE resources which may be necessitated by an emergency situation. These resources include personnel, equipment and funds. r ~~q9}1. Authorization: 1J/~~ I'~ Date Fadi M. Diya Senior Vice-President and Chief Nuclear Officer Page 128 of 139 AppendixB RERP Rev. 045 Appendix C Letters of Agreement Sheet 1 of 1 NOTE These documents are reviewed annually and updated as necessary. The QA Records of these documents are kept on file at the Callaway Plant in the Electronic Document Management System (File Code K190.0011).
1. Callaway County Sheriff's Office (includes response to hostile action based events).
2. Missouri State Highway Patrol (includes response to hostile action based events).
3. Institute of Nuclear Power Operations.
4. Callaway Community Hospital.
5. Callaway County Ambulance District.
6. Emergency Mutual Assistance Agreement, Wolf Creek Nuclear Operating Corporation
7. Westinghouse Electric Corporation.
8. Environmental, Inc. Midwest Laboratory.
9. South Callaway Fire Protection District.
10. The Curators of the University of Missouri.
11. Radio Station KTXY.
Page 129 of 139 Appendix C RERP Rev. 045 Appendix D DELETED, Rev. 017, 01/94 (See 6.7.2.1, Alerting the General Public) Sheet 1 of 1 This Page Intentionally Left Blank. Page 130 of 139 Appendix D RERP Rev. 045 Appendix E DELETED, Rev. 017, 01/94 (See 6.7.3, Use of On-Site Protective Equipment and Supplies) Sheet 1 of 1 This Page Intentionally Left Blank. Page 131 of 139 Appendix E RERP Rev. 045 Appendix F List of Emergency Plan Implementing Procedures (EIPs) Sheet 1 of 1 NOTE This is a sample list of procedures. Procedure numbers, titles of any listed procedure, or the numbers of EIPs, may be modified or revised based on revisions made to these procedures. Such modifications or revisions are reflected in the periodic updates to the RERP. Procedure No. Procedure Title RERP Sections Implemented EIP-ZZ-A0001 Emergency Response Organization ................................... Chapter 5, 8.1.1 EIP-ZZ-A0020 Maintaining Emergency Preparedness ............................... Chapter 8 EIP-ZZ-A0066 RERP Training Program.................................................... 8.1, 8.1.1, 8.1.1.2 EIP-ZZ-C0010 Emergency Operations Facility Operations ........................ 5.2.9 - 5.2.12, 7.1.3 EIP-ZZ-PR020 Activation and Operation of the Joint Public Information Center ............................................................ 5.2.13, 6.9, 7.1.5 EIP-ZZ-SK001 Response to Security Events .............................................. Table 4-1 EIP-ZZ-00101 Classification of Emergencies ........................................... Chapter 4, Table 4-1, 6.1, 6.2 EIP-ZZ-00102 Emergency Implementing Actions..................................... 5.1, 5.2, 6.2, 6.3, 6.4, 6.5, 6.6, 6.7, 6.8 EIP-ZZ-00200 Augmentation of the Emergency Organization .................. Chapter 5, 6.4, Tables 5-2 EIP-ZZ-00201 Notifications ..................................................................... 5.1.10, 5.2.6, 5.3.2.3, 6.3, 6.7.2, 7.2.4, 7.2.5 EIP-ZZ-00211 Field Monitoring ............................................................... 5.2.5.2, 5.3.2.2.2, 6.5.2.1 EIP-ZZ-00212 Protective Action Recommendations ................................. 6.7.2, Tables 6-2, 6-3, 6-4 EIP-ZZ-00213 Technical Assessment ....................................................... 5.1.1,5.1.2, 5.2.4, 6.5, 6.6 EIP-ZZ-00217 Emergency Response Data System Activation................... 7.2.8.6 EIP-ZZ-00220 Emergency Team Formation ............................................. 5.1.11 EIP-ZZ-00225 Reentry ............................................................................. 9.5 EIP-ZZ-00226 Fire Response Procedure for Callaway Plant ..................... 5.1.11.1, 7.2.1.1, 7.3.1.13 EIP-ZZ-00230 Accountability ................................................................... 6.7.1.2 EIP-ZZ-00240 Technical Support Center Operations ................................ 5.2.3-5.2.8,, 7.1.2 EIP-ZZ-00260 Event Closeout/Plant Recovery ......................................... Chapter 9 EIP-ZZ-01211 Accident Dose Assessment ................................................ 6.5.2 EIP-ZZ-03010 Hazardous Chemical/Oil Spill Response/Spill Cleanup Implementing Procedure EIP-ZZ-03010, Appendix A: Hazmat Locator EIP-ZZ-03010, Appendix B: Above Ground Oil Storage and Use Facilities Page 132 of 139 Appendix F RERP Rev. 045 Appendix G Evacuation Time Estimate for the Callaway Nuclear Plant Emergency Planning Zone Sheet 1 of 1 This document is being controlled as a separate License Document in the Callaway Document Room. Page 133 of 139 Appendix G RERP Rev. 045 Appendix H Public Alert System Sheet 1 of 4 The public alert system consists of fixed sirens and tone alert receivers and provides notification to approximately 100 percent of the population within the Callaway Plant Plume Exposure Pathway Emergency Planning Zone (EPZ). The fixed sirens are located in various populated areas (see Figure H-1) and tone alert receivers are utilized for coverage of sparsely populated areas. Tone alert receivers are also used to augment coverage of special facilities located within the EPZ. The sirens have a rated output power of approximately 125DB at 100 ft. and each siren has a coverage radius of 7000 feet. The fixed sirens within each risk county are activated from the Callaway County 911 Center. The tone alert receivers will be activated by one of two methods depending on receiver type. Earlier issued models will be activated from EAS Common Program Control Station KTXY in Columbia, Missouri when the EAS tone is transmitted. The All Hazards Weather Radio type will be activated by the National Weather Service when the EAS alert is sent. The alerting processes are performed in parallel to ensure that all tone alert receivers are activated. An automated calling service is available as a backup to the sirens and tone alert receivers. This service can call all listed telephone numbers in the EPZ. Unlisted telephone numbers provided by the owners are also included. This system is activated by a call from Callaway County to the vendor. Population at Schools and Other Institutions Due to expected mobilization time requirements to institutional populations and the resources needed for their evacuation, all special facilities are notified by their county's Emergency Operations Center (EOC) at an emergency classification of SITE AREA EMERGENCY or greater. These facilities are notified of a protective action situation via the public alert system and by telephone from the county EOC. Although some schools, located in the EPZ, are within the range of the fixed outdoor warning system, notification of each school administration that protective action is called for is made via both the tone alert receiver system and direct telephone call. The schools can then effect the alerting of students and staff through their existing internal communications systems. Populations located in selected institutions, such as medical, convalescent, or geriatric facilities are also notified both through the tone alert receiver system and by telephone from the EOC. Population In Transit During an emergency condition, it can be expected that a number of persons would be traveling on the road system within the EPZ. These travelers may be local residents or persons from other areas traveling through or to areas within the EPZ. Local trips within the EPZ are, of course, short trips with an average travel time of approximately 10 minutes. These local travelers can, therefore, be expected to be advised of the emergency condition at their trip destination if they are not in an area covered by a fixed outdoor warning siren at the time the warning is issued. They should, therefore, be notified within or near the required 15-minute notification period. Page 134 of 139 Appendix H RERP Rev. 045 Non local travelers will need to be diverted from entering the EPZ at the earliest possible time, not only for their own protection but also to provide maximum available road capacity in event of the evacuation of area residents. Major roadway access control points are identified for the Callaway Plant EPZ (See Figure H-2). These access points are to be controlled by local law enforcement personnel within each risk county. These access control points may be manned to preclude entry to any subarea of the EPZ or to preclude entry to the EPZ as a whole. Non local travelers are notified of an emergency condition at these control points prior to their entry into a controlled access area. There is a possibility that transients may be located in the Reform Wildlife Area surrounding the Plant, on the Katy Trail State Park, or on the Missouri River. Transients in these locations are alerted by the public alert sirens, and instructional material has been posted at Wildlife Area parking areas and Public Access Points along the river to explain what to do if the fixed sirens are activated. Table H-1 summarizes the public alert systems that are employed for different population segments in the EPZ. Table H-1 Alert Systems for Specific Population Segments Population Segment Alert System Population Segment Alert System Population at Home Sirens or Tone Alert Receivers Population at Work At Business Centers Sirens or Tone Alert Receivers At Industrial Centers Sirens or Tone Alert Receivers At Places Outside the EPZ On Farms Sirens or Tone Alert Receivers Population in Transit On the Road System Sirens/Authorities at EPZ access control points. On the River Sirens Population at Business Centers Sirens or Tone Alert Receivers Population at Schools Sirens or Tone Alert Receivers / Supplemental Notification Methods Population in Other Institutions Sirens or Tone Alert Receivers / Supplemental Notification Methods Population at Recreational Areas Hunting, Fishing, Camping,Hiking, Biking, Jogging, Sirens / Possible Supplemental Etc. Notification Methods At Sporting Events Sirens or Tone Alert Receivers Page 135 of 139 Appendix H RERP Rev. 045 Figure H-1 Public Alert System Siren Coverage Page 136 of 139 Appendix H RERP Rev. 045 Figure H-2 Access Control Points Page 137 of 139 Appendix H RERP Rev. 045 Appendix I List Of Supporting Radiological Emergency Response Plans Sheet 1 of 1 I. CALLAWAY PLANT A. Fire Protection Program B. Security Plan II. COUNTY A. Callaway County/Fulton Radiological Emergency Response Plan B. Osage County Radiological Emergency Response Plan C. Montgomery County Radiological Emergency Response Plan D. Gasconade County Radiological Emergency Response Plan III. STATE A. Missouri Nuclear Accident Plan - Callaway IV. FEDERAL A. NRC Incident Response Plan - NUREG-0728
1. Agency Procedures for the NRC Incident Response Plan - NUREG-0845
2. Region IV Incident Response Supplement to NUREG-0845 B. Federal Emergency Management Agency, National Radiological Emergency Response Plan
1. Federal Emergency Management Agency Region VII Kansas City, Missouri Emergency Response Team Plan Page 138 of 139 Appendix I
RERP Rev. 045 Appendix J Callaway Plant - On-Shift Staffing Analysis Report Sheet 1 of 1 This document is being controlled as a separate License Document in the Callaway Document Room. Page 139 of 139 Appendix J
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