ML20307A445

Attachment 3 - Proposed Revision to Site Emergency Plan

ML20307A445
Person / Time
Site:	Dresden
Issue date:	11/02/2020
From:	Exelon Generation Co
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML20307A433	List: ML20307A434 ML20307A436 ML20307A445 ML20307A455 RS-20-131, Part II: Planning Standards and Criteria
References
RS-20-131
Download: ML20307A445 (64)

Text

Attachment 3 Dresden Station PROPOSED REVISION TO SITE EMERGENCY PLAN

Attachment 3 Dresden Station PROPOSED REVISION TO SITE EMERGENCY PLAN Exhibit A Dresden Station Radiological Emergency Plan (Procedure EP-DR-1000)

(Marked-Up Pages)

EP-DR-1000 Exelon Generation Revision X EXELON NUCLEAR DRESDEN STATION RADIOLOGICAL EMERGENCY PLAN November 2021 EP-DR-1000 (Revision X)

PART II: Planning Standards And Criteria Exelon Nuclear

2) State Agencies a) The State of Illinois: The State of Illinois has the statutory responsibility and authority for protecting the health and safety of the public in Illinois. The State of Illinois has developed an "Illinois Plan for Radiological Accidents" (IPRA).

This plan was developed in accordance with the guidance suggested by NUREG-0396 and NUREG 0654/FEMA-REP-1, Rev. 1. The IPRA has received 44 CFR 350 unconditional approvals from FEMA for all Exelon Nuclear's generating stations in the state of Illinois. Basic descriptions for the Illinois state agencies responsible for actions in the event of a nuclear power station are as follows:

• Governor of the State of Illinois: The Governor of the State of Illinois has overall command authority for both the radiological and non-radiological aspects of a nuclear incident. The Governor shall make the final recommendation for protective actions and shall serve as the state's primary spokesperson .

• Illinois Emergency Management Agency (IEMA): IEMA coordinates the operational response and recovery functions of all State agencies. IEMA proposes Protective Action Recommendations (PARs) to the Governor.

IEMA also coordinates the implementation of the Governor's PARs.

IEMA has the responsibility to inform the State of Wisconsin Department of Emergency Government (WDEG) with respect to an emergency event at Dresden Nuclear Power Station that impacts the 50-mile Ingestion Pathway Zone.

IEMA Teehnieal has both the command authority for radiological aspects of a nuclear incident and the responsibility for performing various radiological functions . These functions include milk, water and food control , radiation exposure control for state emergency workers, and confirmatory accident assessment. During an emergency situation, IEMA Technical shall make protective action recommendations to the Governor.

For events that impact the 50-mile ingestion pathway for Dresden Nuclear Power Station, IEMA Technical will coordinate technical information with the State of Wisconsin.

The IEMA Technical response to a nuclear incident utilizes two functional subgroups. They are the Radiological Emergency Assessment Center (REAC) and the Radiological Assessment Field Team (RAFT).

- Radiological Emergency Assessment Center (REAC): IEMA has established REAC in Springfield Illinois. REAC will serve as the command location for all (State related) radiological aspects of a nuclear incident. The Manager of the Office of Nuclear Facility Safety, or his/her designated alternate, is in command of REAC.

November 2021 A-5 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Figure A-2: Agency Response Organization Interrelationships Governor's

- FEMA ~ - Office US NRC . Emergency Mgt.

Headquarters Agency I

US NRC State IJept of Safelj :

Exelon ~

Region Agencies RaEI PrntestieR

' *~

- DOE ' - State Police Field Monitoring Teams Agriculture I Fish

- FBI -

& W ild Life

- USCG -

Other Agencies U.S. Army

- Corp of Engrs

- Hospitals

- NWS Fire Department County Medical Agencies Support

- Municipal Local Law Enforcement November 2021 A-10 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Section B: Exelon Dresden Nuclear Emergency Response Organization This section describes the Dresden Nuclear Emergency Response Organization (ERO),

its key positions and associated responsibilities. It outlines the staffing requirements which provide initial emergency response actions and provisions for timely augmentation of on-shift personnel when required. It also describes interfaces among Exelon Nuclear emergency response personnel and specifies the offsite support available to respond to Dresden Station.

1. On-Shift Emergency Response Organization Assignments The normal plant personnel complement is established with the Station Vise PresidentPlant Manager having overall authority for station operations. The Station Vise PresidentPlant Manager directs the site organization in the management of the various departments while the Shift Manager retains the responsibility for actual operation of plant systems. Emergency Preparedness must consider the capabilities of the normal plant organization, the Station and Corporate Emergency Response Organizations of Exelon Nuclear, and the non-Exelon Nuclear Emergency Response agencies. The initial phases of an emergency situation at a nuclear station will most likely involve a relatively small number of individuals. These individuals must be capable of (1) determining that an emergency exists; (2) providing initial classification and assessment; and (3) promptly notifying other groups and individuals in the emergency organization. The subsequent phases of the emergency situation may require an increasing augmentation of the emergency organization .

Dresden Station has personnel on shift at all times that can provide an initial response to an emergency event. ERO staffing tables, contained within this Emergency Plan outline the plant on-shift emergency organization and its relation to the normal staff complement. Members of the on-shift organization are trained on their responsibilities and duties in the event of an emergency and are capable of performing all response actions in an Unusual Event or the initial actions of higher classifications.

On Shift Personnel Dresden station has the capability at all times to perform detection, mitigation, classification, and notification functions required in the early phases of an emergency.

Shift augmentation and further ERO involvement will be determined by the extent and magnitude of the event.

Shift Manager: While acting as Shift Emergency Director, will take immediate action during an emergency and will activate the Station ERO, as appropriate. In the Shift Manager's absence or incapacitation , the line of succession is defined by Dresden procedures.

November 2021 B-1 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Shift Technical Advisor <STA): During normal plant operations, the Senior Reactor Operators report to the Shift Manager and directly supervise the licensed Reactor Operators and all activities in the Control Room. During an abnormal condition, the Shift Manager assumes direct supervision of personnel and all activities in the Control Room while a qualified individual steps bacl< and assumes an overview role as an STA with the specific responsibility of monitoring the maintenance of core cooling and containment integrity. An individual assigned the duty as the STA shall be available to the Control Room at all times.

Radiation Protection: The Station Radiation Protection personnel are responsible for the handling and monitoring of radioactive materials. Included in this organization are Health Physicists, Radiation Protection Supervisors and Technicians.

Security: The Station Security personnel are responsible for the physical security of the site. Included in this organization are Security Supervisors and Security Guards.

2. Authority Over the Emergency Response Organization The Emergency Director in Command and Control is the designated Exelon Nuclear individual who has overall authority and responsibility, management ability, and technical knowledge for coordinating all emergency response activities at the nuclear power station.

• Control Room: Shift Emergency Director (Shift Manager)

• TSC: Station Emergency Director

• EOF: Corporate Emergency Director

3. Criteria for Assuming Command and Control (Succession)

Emergency personnel assume responsibility for their positions upon receiving notification to activate. The responsibility for initial assessment of and response to an emergency rests with the Shift Manager. The Shift Manager is the Shift Emergency Director and has the Station and Corporate Emergency Director's responsibilities and authority until relieved. The Corporate Emergency Director, once having relieved the Shift Manager of the Emergency Director responsibilities, is responsible for continued assessment of the severity of the emergency and for the necessary functions as described in the E-Plan, the Station Annex, and the emergency implementing procedures.

November 2021 B-2 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

• Rescue operations and First Aid

• Decontamination

• Security of plant and access control

• Repair and damage control

• Personnel protection including Assembly, Accountability and Evacuation

• Communications All Station ERO personnel shall have the authority to perform assigned duties in a manner consistent with the objectives of this plan .

'Nhen plant conditions warrant entry into the Severe Accident Management Guidelines (S/\MGs), On shift staff or TSC Minimum staff ERO may assume the roles of Decision Mak~er and Evaluators as directed by station procedures.

1) Shift Manager (Shift Emergency Director) Control Room A Shift Manager is on duty 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day and is the Shift Emergency Director in a declared emergency until relieved of this function. While serving in this capacity the Shift Manager is responsible for:

• Activating the ERO (as deemed appropriate or as procedurally required).

• Performing those duties outlined in Section B.5.a.2 for the Station Emergency Director.

The on-duty Shift Manager directs the activities of the operating crew and is responsible for the safe operation of the plant in compliance with the station NRC operating license and the station operating procedures. The Shift Manager, after relinquishing Command and Control, functionally reports to the Operations Manager in the TSC.

The Shift Manager's responsibilities, when not in Command and Control, are described below:

• The authority and responsibility to shutdown the reactor when determined that the safety of the reactor is in jeopardy or when operating parameters exceed any of the reactor protection circuit set points and automatic shutdown does not occur;

• To ensure a review has been completed to determine the circumstance, cause, and limits under which operations can safely proceed before the roaster is returned to power following a trip or an unseheduled or unexplained power reduetion;

• The responsibility to be present at the plant and to provide direction for returning the reactor to power following a trip or an unscheduled or unexplained power reduction; November 2021 B-6 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

• Coordinate TSC efforts in determining the nature and extent of emergencies pertaining to equipment and plant facilities in support of Control Room actions.

• Initiate immediate corrective actions to limit or contain the emergency invoking the provisions of 10 CFR 50.54(x) if appropriate.

• Recommend equipment operations checks and miscellaneous actions to the Control Room in support of restoration and accident mitigation.

• Approve emergency special procedures, and implement as required under the provisions of 10 CFR 50.54(x) .

• Assist in determining the priority assigned to OSC activities.

• Organize and direct medical response efforts for injured personnel.

• Ensure adequate staffing of the Control Room and TSC subordinates.

• Ensure the Shift Manager is informed of OSC staffing utilization and activities.

• Identify steps or procedures that the Operations staff should be utilizing to properly respond to the emergency condition.

• Assist the Station Emergency Director in evaluating changes in event classification.

• Supervise the activities of the ENS Communicator in the TSC.

• Act as the TSC liaison with the appropriate NRC Site Team Representative.

5) Technical Support Staff TSC The TSC Technical Support Staff consists of the following minimum staff engineering positions :

-TSC EngineerElectrical Engineer Mechanical Engineer Core/Thermal Hydraulic Engineer serves as Core Damage Assessment Methodology (CDAM) Evaluator, as applicable.

In addition, station Engineering support will be augmented on an as needed basis to support accident assessment and mitigation activities.

November 2021 B-9 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

• Maintain plant security and account for all personnel within the protected area.

• Assist the Station Emergency Director in evaluating changes in security related threats and event classifications.

• Identify any non-routine security procedures and/or contingencies that are in effect or that require a response.

• Expedite ingress and egress of emergency response personnel.

• Coordinate with the Radiation Protection Manager in controlling ingress and egress to and from the Protected Area if radiological concerns are present.

• Provide for access control to the Control Room, TSC and OSC, as appropriate.

• Expedite entry into the Protected Area, as necessary, for the NRG Site Team.

• Act as the TSC liaison with the appropriate NRC Site Team representative.

• Assist the Radiation Protection Manager in determining personnel evacuation routes as necessary.

• Coordinate the evacuation of station non-essential personnel with the appropriate Local Law Enforcement Agencies (LLEAs).

8) Operations Support Center Director osc The OSC Director reports to the Emergency Director and supervises the activities of OSC personnel. Responsibilities include:

• Assign tasks to designated Leads as available:

l&C Maintenance

- Mechanical Maintenance

- Electrical Maintenance

- Radiation Protection

• Coordinate with Operations in the dispatch of Operations personnel to support Control Room and OSC Team activities.

• Notify the Control Room and TSC prior to dispatch of any OSC teams into the plant.

November 2021 B-11 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

• Maintain OSC resources including personnel, material, and equipment.

• Maintain accountability for all individuals dispatched from the OSC.

• Conduct periodic briefings on the overall plant status, emergency response activities, and station priorities.

• Assemble and dispatch the Field Monitoring Teams as required.

9) OSC RP Leads osc OSC Leads report to the OSC Director and are assigned from the following station departments:

Mechanical Maintenance Electrical Maintenance Instrument and Control Radiation Protection The OSC RP Lead assigned to an OSC team is responsi ble at all times for the safety of team personnel and to keep the OSC Director apprised of team status. Specifically, the OSC RP Leads isara responsible for the managing and supervising OSC team RP personnel, including:

Conduct of adequate pre-dispatch briefings.

Ensuring adequate protective equipment and measures have been identified.

Tracking of OSC team activities while dispatched.

Debriefing of team personnel upon return to the OSC.

November 2021 B-12 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

7. Exelon Corporate Emergency Response Organization The Corporate ERO consists of the EOF Organization and the Emergency Public Information Organization. Personnel staffing these corporate organizations are covered in detail in Section B.5 of this plan.

The Corporate Emergency Response Organization is staffed by Exelon personnel, and operates out of the Emergency Operations Facility (EOF) and the Joint Information Center (JIC). The Corporate ERO is supported by News Media Spokespersons, environmental assessment staff and monitoring teams that provide long-term support to the affected station. Additionally, the Corporate ERO has long term liaison responsibilities with federal, state, and local authorities. These positions are further described in the EPIPs.

The Emergency News Center (ENC) function is responsible for the collection and analysis of event information and status, and development of Company news statements. This information is then communicated to the JIC Corporate Spokesperson. The ENC function may be located at either the EOF or the JIC.

The EOF is activated at an Alert. The EOF Organization is responsible for evaluating, coordinating and directing the overall company activities involved in the emergency response. Within the EOF, the Corporate Emergency Director shall assume Command and Control from the Shift Emergency Director when classification escalates to an Alert or higher, unless the EOF capabilities are limited such that the overall control and responsibility for PARs and offsite notifications cannot be assumed .

The JIC is activated within 90 minutes of an Alert or higher. Some JIC functions may continue to be performed by the Exelon Communications organization until transferred to the JIC.

8. Industry/Private Support Organizations Exelon Nuclear retains contractors to provide supporting services to nuclear generating stations. A contract/purchase order with a private contractor is acceptable in lieu of an agreement letter for the specified duration of the contract. Among services currently provided are the following:

a. Deletedlnstitute of ~Juclear Power Operations (INPO): Experience has shown that a utility may need resources beyond in house capabilities for the recovery from a nuclear plant emergency. One of the roles of the Institute of Nuclear Power Operations (l~JPO) is to assist affected utilities by quickly applying the resources of the nuclear industry to meet the needs of an emergency. INPO has an emergency response plan that enables it to provide the following emergency support functions:

Assistance to the affected utility in locating sources of emergency personnel, equipment and operational analysis.

l~JPO , Electric Power Research Institute (EPRI) and ~Juclear Energy Institute (~JEI) maintain a coordination agreement on emergency information with their member utilities.

November 2021 B-18 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear l~JPO provides the "Nuclear ~Jetwork", or its replacement, electronic communications system to its members, participants, ~JEI, and EPRI to coordinate the flow of media and technical information about the emergency.

Exelon ~Juclear may obtain utility industry information and assistance from any party to this agreement through the coordination of l~JPO.

To support these functions , l~JPO maintains the following emergency support capabilities:

A dedicated emergency call number.

Designated l~JPO representative(s) who can be quickly dispatched to the utility emergency response organization to coordinate l~JPO support activities and information flow.

The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day operation of an Emergency Response Center at INPO headquarters.

Exelon Nuclear will notify l~JPO (via the designated emergency call number) for all situations involving an Alert, Site Area Emergency, or General Emergency declaration per the Exelon ~Juclear Reportability Manual.

INPO has coordinated the preparation of a Voluntary Assistance Agreement for Transportation Accidents. Exelon ~Juclear has signed this agreement which establishes the rights and responsibilities of electric utilities in requesting or providing assistance for response to a nuclear materials Transportation Accident.

b. American Nuclear Insurers CANI): In early 1982, ANI issued Bulletin #58 (1981)

"Accident Notification Procedures for Liability Insurers" which provides revised criteria for the notification of the Pools in the event of a nuclear emergency at one of the liability insured nuclear power reactor sites. This revision brings the ANl/MAELU (Mutual Atomic Energy Liability Underwriters) notification criteria into alignment with the standard emergency classification system adopted by the nuclear industry. This document also identifies a suitable channel for follow-up communication by ANI after initial notification.

• ANl/MAELU Emergency Assistance: In the event of an extraordinary nuclear occu rrence (as defined in the Price-Anderson Law) ANI and MAELU (the insurance pools) have plans prepared to provide prompt emergency funding to affected members of the public.

• ANl/MAELU Emergency Assistance (Claims Handling Procedures): The pools' emergency assistance arrangements contemplate the mobilization and dispatch of emergency claims teams to directly dispense emergency assistance funds to affected members of the public.

November 2021 B-19 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Figure B-1 a: Exelon Dresden Overall ERO Command Structure Corporate Emergency Director Station Corporate Emergency Spokesperson Director November 2021 B-23 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Figure B-1 b: Emergency Onsite Organization Station Emergency Director I

Security Coordinator I I I Rad Protection osc Operations Manager Director Manager ENS Communicator -

I I I Cern/TheFFnal t&G ElestFisal Meshanisal Control Room ERgiReeF Rad Protection beal: beal: beal: Shift Manager Lead 1 l&C Electrical Rad Protection Mechanical L Control Room Shift Staff MeshaRisal ERgiReeF Pool Pool Pool Pool

......_ ElestFisal TSC Engineer ERO response pool personnel do not include the on-shift complement.

1 Rad Protection Lead responsibilities will be performed by a Rad Protection Pool responder as a collateral function November 2021 8-24 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

• When the event is terminated, close-out is performed over communication links to offsite authorities participating in the response (i.e., NRC, state, county), followed by formal transmission of a state/local notification form within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. Alert - Events are in process or have occurred which indicate 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 EPA Protective Action Guideline exposure levels.

The purpose of this classification is to ensure that emergency response personnel are readily available and to provide offsite authorities with current status information. An Alert will be classified as the initiating event or as escalation from an Unusual Event. In either case, the classification will most likely made by the Shift Manager (Shift Emergency Director) prior to the transfer of Command and Control.

Required actions at this classification include:

• Notifications to station management and the NDO.

• Notification , within 15 minutes, of the state and local communities. The EOF will assume state update responsibilities.

• Activation of the TSC, OSC, EOF, and the JIC organizations.

• Transfer of Command and Control.

• Notification of the NRC immediately after notification of the appropriate State and local agencies and not later than 60 minutes of classification.

• Notification of INPO and ANI.

• Assessment of the situation and response as necessary, which may include escalating to a higher classification if conditions warrant.

• On-site and off-site Field Monitoring Teams are sent to staging areas or dispatched to monitor for releases of radiation to the environment.

• Keeping offsite authorities informed of plant status by providing periodic updates to include meteorological and radiological data.

• When the event is terminated, notification is performed over communication links followed by an Initial Incident Report to offsite authorities participating in the response (i.e., NRC, state, county) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

November 2021 D-2 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

c. Site Area Emergency - Events are in process or have occurred which involve actual or likely major failures 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.

The purpose of this classification, in addition to those of the Alert level, is to ensure that all emergency response centers are staffed and provisions are made for information updates to the public through offsite authorities and the news media.

The classification will most likely be made by the Station Emergency Director following activation of the TSC.

Required actions at this classification, in addition to those listed under the Alert level, include:

• If not previously performed, Assembly/Accountability shall be performed and Site Evacuation of non-essential personnel shall be initiated.

• Keeping offsite authorities informed of plant status by providing periodic updates to include meteorological data and projected or actual doses for any releases that have occurred.

d. General Emergency - Event(s) are in process or have occurred which involve actual or imminent substantial oore--fuel degradation or melting with potential for loss of eontainment 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 offsite for more than the immediate site area.

The purpose of this classification, in addition to those of the Site Area Emergency level, is to initiate predetermined protective actions for the public and provide continuous assessment of information from monitoring groups. The classification will most likely be made by the Station Emergency Director following activation of the TSC.

Required actions at this classification , in addition to those listed under the Alert and Site Area Emergency, include:

• A Protective Action Recommendation will be determined.

• Assessment of the situation and response as necessary.

November 2021 D-3 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

e. Recovery: That period when the emergency phase is over and activities are being taken to return the situation to a normal state (acceptable condition). The plant is under control and no potential for further degradation to the plant or the environment is believed to exist.

Recovery will be classified by the Station Emergency Director after obtaining authorization from the Corporate Emergency Director.

Required actions at this classification include:

• The affected state(s) and the NRC should be consulted prior to entry into Recovery.

• Notifications will be made to station management, the NDO, state(s) and NRC.

• A Recovery organization will be established to manage repairs to return the Unit to an acceptable condition, and support environmental monitoring activities as requested in coordination with Federal and state efforts.

• l~JPO and ANI arais notified of Recovery classification.

f. Classification Downgrading: Exelon Nuclear policy is that emergency classifications shall not be downgraded to a lower classification. Once declared, the event shall remain in effect until no Classification is warranted or until such time as conditions warrant classification to Recovery.

g. Guidance for Termination of an Emergency: The purpose of terminating an emergency is to provide an orderly turnover of plant control from the Emergency Response Organizations to the normal Exelon Nuclear plant organization .

Termination of the emergency is authorized by the Emergency Director in Command and Control. The considerations provided in the Recovery/Termination Checklist in the emergency implementing procedures must be performed prior to exiting the emergency event. Consultation with governmental agencies and other parties should be conducted prior to termination of an event classified as Site Area or General Emergency. Notifications shall be transmitted to appropriate agencies to terminate an event.

h. Station Nuclear Security Plan: Dresden has a Security Plan that complies with the requirements of 10 CFR 73. The interface between the E-Plan and the Security Plan is one of parallel operation. The plans are compatible. The E-Plan response measures, once initiated, are executed in parallel with measures taken in accordance with the Security Plan.

November 2021 D-4 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear An emergency is classified after assessing abnormal plant conditions and comparing them to EAL Threshold Values for the appropriate Initiating Conditions. Classifications are based on the evaluation of each unit for multi-reactor sites. Matrix tables organized by recognition categories are used to facilitate the comparison. The matrix tables are used when the unit is in the Teohnisal Speoifioation defined modes of Power Operations, Hot Standby, Hot Shutdown (for slassifioations purposes, startup evolutions are insluded in the Power Operations mode) and Cold Shutdown or Refueling (for olassifioation purposes a defueled plant will be oonsidered in the Refueling mode).

All recognition categories should be reviewed for applicability prior to classification.

The initiating conditions are coded with a letter and/or number designator. All initiating conditions, which describe the severity of a common condition (series), have the same initial designator.

3. Timely Classification of Events Classification of an emergency condition occurs within 15 minutes after the availability of indications from plant instrumentation, plant alarms, computer displays, or incoming verbal reports that an EAL has been exceeded and, is then promptly made upon identification of the appropriate EAL. The 15-minute period encompasses all assessment, classification, and declaration actions associated with making an emergency declaration from the first availability of a plant indication or receipt of a report up to and including the declaration of the emergency.

Validation or confirmation of plant indications or reports of the condition are to be accomplished within the 15-minute period as part of the assessment. Since this validation or confirmation is being performed to determine the validity of an alarm, indication, or report, the 15-minute period starts with the availability of the alarm, indication, or report to any qualified EAL assessor, and not the completion of the validation or confirmation, because the former is the time that the information was first available.

A qualified EAL assessor means any member of the plant staff who, by training and experience, is qualified to assess the indications or reports for validity and to compare the same to the EALs. A qualified EAL assessor may be, but need not be, a lioensed operatorCertified Fuel Handler, Non Certified Operator, or member of the ERO.

Qualified EAL assessors may be in the MCR or in another facility where emergency declarations are performed. A qualified EAL assessor does not include personnel such as chemists, radiation protection technicians, craft personnel, security personnel, and others whose positions require they report, rather than assess, abnormal conditions to the MCR.

November 2021 0-6 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

b. Offsite: Notifications are promptly made to offsite emergency response organizations as follows:

1) State/Local Agencies: A notification shall be made within fifteen (15) minutes of:

• The initial emergency classification.

• Classification escalation.

• The issuance of or change to a Protective Action Recommendation (PAR) for the general public.

• Changes in radiological release status, occurring outside of an event classification or PAR notification, based on an agreement with the state(s).

The emergency warning points are simultaneously notified using the Nuclear Accident Reporting System (NARS), or a commercial telephone line as backup.

A notification will also be initiated to cognizant state/local government agencies as soon as possible but within one hour of the termination of an event classification, or entry into Recovery Phase.

2) Nuclear Regulatory Commission (NRC): An event will be reported to the NRC Operations Center immediately after notification of the appropriate state or local agencies but not later than one (1) hour after the time of initial classification, escalation, termination or entry into the Recovery Phase. The NRC is notified by a dedicated telephone system called the Emergency Notification System (ENS). If the ENS is inoperative, the required notification is made via commercial telephone service, other dedicated telephone service, or any other method that shall ensure that a report is made as soon as practical. An NRC Event Notification Worksheet should be utilized to transmit initial information to the NRC. If a continuous communication is requested and established, a log is used in lieu of the ENS Worksheet.

Specific requirements for the notifications to the NRC for classified emergency events are detailed in 10 CFR 50.72 with guidance provided in the Exelon Reportability Manual.

The computerized data link to the NRG, referred to as the Emergency Response Data gystem (EROg), continuously supplies specified plant data to the ~JRC.

Mobilization of federal, state, and county response organizations is performed in accordance with their applicable emergency plan and procedures. At a minimum, mobilization of federal response organizations and activation of state and county EOCs is expected to occur at the declaration of a Site Area Emergency.

November 2021 E-2 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear The state and county authorities are responsible for the process of notification of the general public.

c. Support Organizations: When an emergency is initially classified , escalated or terminated, notifications are promptly made to the following support organizations:

• Medical, rescue, and fire fighting support services are notified for assistance as the situation dictates.

• The Institute of ~Juclear Power Operations (l~JPO) is notified at an Alert or higher classification with requests for assistance as necessary.

• The American Nuclear Insurers (ANI) are notified at an Alert or higher classification with requests for assistance as necessary.

• Vendor and contractor support services are notified for assistance as the situation dictates.

3. Initial Notification Messages Exelon Nuclear, in conjunction with state and county authorities, has established the contents of the initial notification message form transmitted during a classified emergency. The contents of the form include, as a minimum:

• Designation ("This is a Drill" or "Actual Event").

• Identity of site.

• Event classification.

• EAL number (as agreed upon with state authorities).

• Non-technical event description (as agreed upon with state authorities).

• Date and time of declaration (or entry into Recovery or Termination).

• Whether a release is taking place (Note: "Release" means a radiological release attributable to the emergency event.)

• Wind direction and speed.

• Whether offsite protective measures may be necessary.

• Potentially affected Subareas (or Sectors as applicable) when a General Emergency is declared.

Notification approval, transmittal date and time, and offsite agencies contacted are recorded either on the notification form or in an event logbook.

November 2021 E-3 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear The ANS is operated by local governmental agencies and maintained by Exelon Nuclear. To assure the ANS is maintained in an operational readiness posture, the local agencies have agreed to test the system (by sounding the sirens) on a periodic basis that meets or exceeds FEMA guidance and to report inoperable equipment to EP-designated maintenance personnel. The goal of the testing and maintenance program is to identify inoperable equipment in a timely manner and to restore equipment to a functional status commensurate with FEMA operability requirements as referenced in FEMA-REP-10, "Gu ide for the Evaluation of Alert and Notification Systems for Nuclear Power Plants" Section E.6.2.1 . In addition to this routine test and repair program, preventive maintenance of the ANS will be performed on an annual basis.

A more site-specific description of the various prompt public notification systems is presented in the Station Annex to the E-Plan. The activation of the ANS sirens, deployment of emergency service vehicles and operation of the Emergency Alerting System is discussed in detail in the state specific response plans.

7. Messages to the Public The respective States have developed EAS messages for the public consistent with the classification scheme. These draft messages are included as part of the States' Emergency Plan and contain instructions with regard to specific protective actions to be taken by occupants and visitors of affected areas. Messages may include instructions such as: take shelter and go indoors, close windows and doors, turn off ventilation systems; directions given for evacuation ; directions to stay tuned to specific stations for further information, ad-hoc respiratory protection, (e.g. handkerchief over mouth, etc.). Exelon will provide support for the content of these messages when requested . The States control the distribution of radioprotective drugs to the general public.

November 2021 E-5 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

1) Nuclear Accident Reporting System (NARS): The NARS is a dedicated communications system that has been installed for the purpose of notifying state and local authorities of declared nuclear emergencies. This system links together the station Control Rooms, the EOF, TSCs and state and local authorities as appropriate. The specific design, operation, and responsibility for maintenance of the ~JARS systems vary between Exelon ~Juclear regions.

~Joto that some stations refer to ~JARS as Radiological Emergency Communications System (RECS).

2) Operations Status Line: An independent interfacility telephone link called the Operations Status Line that enables communication between the Control Room , the TSC, the OSC, and the EOF to monitor the activities throughout the Emergency Response Facilities (see Figure F-2). The Operations Status line consists of a dedicated Private Branch Exchange (PBX) Telephone System or a Voice Over Internet Protocol (VoIP) system.

3) Director's Hotline: A dedicated telephone link called the Director's Hotline that enables direct Emergency Director communication between the Control Room ,

TSC, and the EOF (see Figure F-2). The Directors Hotline consists of a dedicated PBX or a VoIP system.

4) Local Commercial Telephone System : This system provides standard commercial telephone service through the public infrastructure, consisting of central offices and the wire line . The commercial vendor provides primary and secondary power for their lines at their central office.

5) Emergencv Response Data System (ERDS): ERDS will continuously supply the NRG with selected plant data points on a near real time basis. The selected data points are transmitted automatically to the NRG at approximately 1 minute intervals.

e5 )Field Monitoring Team (FMT) Communications: A separate communications system has been installed to allow coordinated environmental monitoring and assessment during an emergency. This system consists of the necessary hardware to allow communication via Satellite Phones between TSC, EOF, and mobile units in Exelon Nuclear vehicles. Commercial cell phones are available as back up to the primary field team communications system.

In addition, station communication links exist to ensure appropriate information transfer capabilities during an emergency. The station may also utilize its Public Address System, station radios and notification devices to augment its emergency communications.

November 2021 F-2 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Figure F-1: Exelon Notification Scheme (For Full Augmentation)

Control Room (Shift Manager)

TSC NRC Headquarters ~ NRC Region (ENS Comm) 1-------~~

1 (Duty Officer) i-----.i (Duty Officer)

(Emergency Director) 1r EOF (State/Local Comm)

I Commercial I VoIP ----.i~

• Nuclear Duty Officer I

As appropriate I :: I~~~ i (NARS) State Warning Local Warning Points/EOCs -+ Points/EOCs

' - - - - - - - - - - - * (Dispatcher/comm) (Dispatcher/comm)

Updates (Commerc1al/VolP)

November 2021 F-4 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Section H: Emergency Facilities and Equipment Onsite and offsite facilities are available for emergency assessment, communications, first aid and medical care, and damage control. Of particular importance are the Emergency Response Facilities (ERFs); the Control Room (CR), the Technical Support Center (TSC), the Operations Support Center (OSC), the Emergency Operations Facility (EOF), and the Joint Information Center (JIC).

This section describes the emergency facilities and equipment used by the Emergency Response Organization and outlines the requirements which aid in timely and accurate response actions. It also describes the surveillance programs used to monitor and ensure that these facilities and equipment are maintained in a high degree of constant readiness.

1. Control Room, Technical Support Center, and Operations Support Center Dresden has established a TSC and an on-site OSC, which are activated upon declaration of an Alert or higher classification. Until they become operational, required functions of these facilities are performed in the Control Room.

Under certain adverse conditions for Security-Based Events, personnel may be assembled in an "ERO Alternative Facility" prior to being dispatched to one of the facility ERFs.

a. Station Control Room: The Control Room is the centralized onsite location from which the Nuclear Station's reactors and major plant systems necessary to support the spent fuel pool are operatedmonitored . The Control Room is equipped with instrumentation to supply detailed information on the reactors and major plant systems. The Control Room is continuously staffed with qualified licensed operators. The Control Room is the first onsite facility to become involved with the response to emergency events. Control Room personnel must evaluate and effect control over the emergency and initiate activities necessary for coping with the emergency until such time that support centers can be activated. These activities shall include:

• Reactor and pPlant control.

• Initial direction of all plant related operations.

• Accident recognition, classification, mitigation and initial corrective actions.

• Alerting of onsite personnel.

• Notification of appropriate individuals.

• Activation of emergency response facilities and ERO notification.

• Notification of offsite agencies.

• Continuous evaluation of the magnitude and potential consequences of an incident.

November 2021 H-1 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Personnel in the TSC shall be protected from radiological hazards, including direct radiation and airborne contaminants under accident conditions with similar radiological habitability as Control Room personnel. To ensure adequate radiological protection, permanent radiation monitoring systems have been installed in the TSC and/or periodic radiation surveys are conducted. These systems indicate radiation dose rates and airborne radioactivity inside the TSC while in use. In addition, protective breathing apparatus (full-face air purifying respirators) and Kl are available for use as required.

The TSC has access to a complete set of as-built drawings and other records, including general arrangement diagrams, P&IDs, and the electrical schematics.

The TSC has the capability to record and display vital plant data, in real time, to be used by knowledgeable individuals responsible for engineering and management support of reaotor operations, and for implementation of emergency procedures.

c. Operations Support Center (OSC): Dresden has established an OSC. The OSC is the onsite location to where station support personnel report during an emergency and from which they will be dispatched for assignments or duties in support of emergency operations. The OSC shall be activated whenever the TSC is activated, but need not remain activated at the Alert level if its use is judged unnecessary by the Station Emergency Director. At the Site Area and General Emergency levels, the OSC or an alternate OSC shall be activated at all times. The OSC is not activated for a HOSTILE ACTION when the Alternative Facility is implemented.

Activation for other events is optional. Station disciplines reporting to the OSC include, but are not limited to:

• Operating personnel not assigned to the Control Room,

• Radiation Protection Personnel,

• Maintenance Personnel (mechanical, electrical and l&C).

Figure B-1 b illustrates the staffing and organization for the OSC.

The OSC is equipped with communication links to the Control Room, the TSC and the EOF (see Section F). A limited inventory of supplies will be kept for the OSC.

This inventory will include respirators, protective clothing, flashlights and portable survey instruments.

2. Emergency Operations Facility (EOF)

The EOF is the location where the Corporate Emergency Director will direct a staff in evaluating and coordinating the overall company activities involved with an emergency. Activation of the EOF is mandatory upon declaration of an Alert or higher classification. The EOF provides for:

• Management of overall emergency response.

• Coordination of radiological and environmental assessments.

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PART II: Planning Standards And Criteria Exelon Nuclear

a. Geophysical Monitors

1) Meteorological Instrumentation: A permanent meteorological monitoring station is located near each station for display and recording of wind speed, wind direction, and ambient and differential temperature for use in making offsite dose projections. Meteorological information is presented in the CR, TSC, and EOF by means of the plant computer system. This information is remotely interrogated using a computer or other data access terminal.

With regard to Exelon Nuclear's meteorological monitoring program, there has been a quality assurance program adopted from 10 CFR 50, Appendix B.

However, since the meteorological facilities are not composed of structures, systems, and components that prevent or mitigate the consequences of postulated accidents and are not "safety related," not all aspects of 10 CFR 50, Appendix B, apply. Those aspects of quality assurance germane to supplying good meteorological information for a nuclear power station were adopted into the meteorological quality assurance program. The meteorological program is also subject to the requirements of the Decommissioning Quality Assurance ProgramQATR, ~eetion 19, Augmented Quality.

The National Weather Service (NWS), or regional weather forecast providers, may be contacted during severe weather periods. These providers analyze national and local weather in order to provide localized weather forecasts for the system or for the station area as appropriate.

2) Seismic Monitoring: The seismic monitoring system measures and records the acceleration (earthquake ground motion) of the structure. Earthquakes produce low frequency accelerations which, when detected by the remote sensing devices, are permanently recorded as information which defines the response spectrum. The system remains in a standby condition until an earthquake causes the remote unit(s) to activate the recording circuits and tape transports.

It also provides signals for immediate remote indication that specific preset response accelerations have been exceeded.

3) Hydrological Monitors: The design basis flood, probable maximum precipitation, and other improbable, conceivable extremes in hydrologic natural phenomena are well below any design limits for the station as detailed in the UFSAR.

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b. Radiological Monitors and Sampling

1) The Radiation Monitoring System (RMS): In-plant radiological measurements provide information that may help determine the nature, extent and source of emergency conditions. The RMS is available to give early warning of a possible emergency and provides for a continuing evaluation of the situation in the Control Room. Radiation monitoring instruments are located at selected areas within the facility to detect, measure, and record radiation levels. In the event the radiation level should increase above a preset level, an alarm is initiated in the Control Room. Certain radiation monitoring instruments also alarm locally in selected areas of the facility. The RMS is divided into 3 subsystems:

a) Area Radiation Monitors (ARMs) are used for the direct measurement of in-plant exposure rates. The ARM readings allow in-plant exposure rate determinations to be made remotely without requiring local hand-held meter surveys. This information may be used, initially, to aid in the determination of plant area accessibility. In addition to permanent monitors, portable Continuous Air Monitors (CAMs) measure airborne particulate and airborne iodine activities at various locations within the operating areas.

b) Process Radiation Monitors (PRMs) are used for the measurement of radioactive noble gas, iodine, and particulate concentrations in plant effluent and other gaseous and fluid streams.

c) The accident, or high range, radiation monitoring system monitors radiation levels at various locations within the operating area. These are high range instruments used to track radiation levels under accident or post accident conditions. These instruments include the Containment/Drywell Radiation Monitors.

The RMS provides the necessary activity or radiation levels required for determining source terms in dose projection procedures. Key RMS data is linked to the plant computer, which allows information to be passed to the TSC and EOF. The isotopic mix, including isotopes such as those in Table 3 of NUREG-0654, is based upon a default accident mix. Refer to the Dresden UFSAR for further detail on the RMS capabilities and design.

2) Liquid and Gaseous Sampling Systems: The process sampling system consists of the normal sampling system and additional sampling panels located throughout the plant. Sampling systems are installed or can be modified to permit reaetor eoolant and eontainment atmosphere sampling even under severe accident conditions.

The sampling systems use a number of manual sampling techniques to enable reaetor eoolant and eontainment sampling operations over a wide range of plant conditions. It is capable of providing information relative to post-accident plant conditions to allow operator actions to be taken to mitigate and control the course of an accident. Refer to the Dresden UFSAR for further detail on sampling capabilities.

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3) Portable Radiation Monitoring Equipment: Portable radiation survey instruments are available for a wide variety uses such as area, sample, and personnel surveys and continued accident assessment. Instruments are stored throughout the plant and in the emergency facilities.

c. Process Monitors: The Control Room and applicable redundant backup locations are equipped with extensive plant process monitors for use in both normal and emergency conditions. These indications include but are not limited to reactor sealant systen:i pressure ans ten:iperature, sontainn:ient pressure ans ten:iperature, liquid levels, flow rates, status or lineup of equipment components. This instrumentation provides the basis for initiation of corrective actions.

1) Plant Monitoring/Information System: A plant monitoring/information system provides the data acquisition and database capability for performing plant monitoring and functions. The system is designed to scan, convert to engineering units, make reasonability and alarm limit checks, apply required transformations, store for recall and analysis, and display the reading of transformed data from plant instrumentation. The system scans flows, pressures, temperatures, fluid levels, radiation levels, equipment, and valve status at required frequencies. Scanned variables are quality tagged. The system provides for short and mid term storage of data for on-line retrieval and fast recall, and long term storage to appropriate media.

2) Safety Parameter Display (SPDS) & Plant Parameter Display (PPDS) Systems:

SPDS and PPDS provide a display of plant parameters from which the safety status of operation may be assessed in the Control Room, TSC and EOF. The primary function of the SPDS and PPDS is to help operating personnel in the Control Room make quick assessments of plant safety status. SPDS and/or PPDS displays in the TSC and EOF promote the exchange of information between these facilities and the Control Room and assists the emergency organization in the decision making process.

d. Fire Detection System: The Fire Detection System is designed to quickly detect visible or invisible smoke (or other products of combustion) and/or heat in designated areas of the plant. The fire alarm communication systems and subsystems are located at strategic points throughout the plant to warn personnel of a nuclear incident or other emergency conditions. Existing plant alarm systems are sufficiently audible to alert personnel in the event of a fire or need for assembly.

These alarm communication systems consist of warning sirens and lights (in high noise areas) and the PA system. Refer to the Dresden UFSAR for further description of the station's fire protection system.

November 2021 H-8 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Section I: Accident Assessment To effectively coordinate and direct all facets of the response to an emergency situation, diligent accident assessment efforts are required throughout the emergency. All four emergency classifications have similar assessment methods, however, each classification requires a greater magnitude of assessment effort dependent upon the plant symptoms and/or initiating event(s) .

1. Plant Parameters and Corresponding Emergency Classification Plant system and effluent parameter values are utilized in the determination of accident severity and subsequent emergency classification . Environmental and meteorological events are also determining factors in emergency classification. An emergency condition can be the result of just one parameter or condition change, or the combination of several. The specific symptoms, parameter values or events for each level of emergency classification are detailed in the emergency implementing procedures. Specific plant system and effluent parameters that characterize a classifiable event (EALs) are presented in Addendum 3 to each Station Annex.

In order to adequately assess the emergency condition, each emergency facility has the necessary equipment and instrumentation installed to make available essential plant information on a continuous basis. Evaluation of plant conditions is accomplished through the monitoring of plant parameters both from indication in the Control Room and within the plant. Some of the more important plant parameters to be monitored in the Control Room are assembled into a single display location, which is entitled the "Safety Parameter Display System" (SPDS). The SPDS monitors such parameters as: reactor coolant system pressure, reactor or pressurizer water level, containment pressure, suppression pool water level and temperature, reactor power, safety system status, containment radiation level and effluent monitor readings. The instrumentation and equipment capabilities available for each emergency facility are described in Section H.

2. Onsite Accident Assessment Capabilities The resources available to provide initial and continuing information for accident assessment throughout the course of an event include plant parameter display systems, liquid and gaseous sampling system, Area and Process Radiation Monitoring Systems, and Accident Radiation Monitoring Systems ('.vhich includes the high range containment radiation monitors). Descriptions of these systems are given in Section H.5.b.

3. Source Term Determination Source term (or OOFe-fuel damage) estimations serve several roles within the Exelon Emergency Preparedness Program . For planning purposes, fuelOOfe damage considerations are used as the bases for several of the Emergency Action Level (EAL)

Initiating Conditions and as the threshold for the declaration of a General Emergency (the definition of a General Emergency specifies conditions which involve 'substantial' OOfe-fuel degradation or melting as one of the bases for classification).

November 2021 1-1 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear From an implementation perspective, OOFefuel damage estimations provide a means of realistically differentiating between the fuelfour core states (no damage, clad failure, and fuel melt, and vessel melt through ) to:

• Evaluate the status of the fuel barriers clad and how their status relates to the risks and possible consequences of the accident.

• Provide input on OOfe-fuel configuration (coolable or uncoolable) for prioritization of mitigating activities .

• Determine the potential quality (type) and/or quantity(%) of source term available for release in support of projected offsite doses and protective action recommendations.

• Provide information that quantifies the severity of an accident in terms that can be readi ly understood and visualized .

• Support the determination of radiological protective actions that should be considered for long term recovery activities.

The assessment methodologies utilized by DresdenExelon are intended to provide a rapid best estimate of OOfe-fuel damage which, when evaluated together, help to develop an overall picture of the extent of OOfe-fuel damage. The methods used to estimate the amount or type of core damage occurring under accident conditions includes the following:

Containment Radiation Monitors: /\n indirect method used to determine the amount of sore damage. /\pplisable to Loss of Coolant /\ssident (LOG/\) ssenarios. Based upon an end of life souree term and statis nuslide ratio assumptions yielding a limited assurasy. Valid any time following an ascident.

Core Temperatures: Methods sush as Core Exit Thermosouple (GET), Peal< Core Temperatures and l=lot Leg Temperatures provide indirest methods used to indisate the type and/or amount of sore damage. /\pplisable for all types of assidents. Valid any time following an assident.

Core Unsoverv: Methods sush as Core Unsovery Time, RVLIS Level and Souree Range Monitor count rate provide indirect methods used to indicate the type of core damage (slad failure or fuel melt). /\pplisable for all types of assidents. Provides a relatively assurate estimate of the state of the sore early in the event. Valid any time following an assident.

Containment l=lydrogen Consentration : An indirest method used to establish the type of sore damage. /\pplisable to LOG/\ type assidents where all the hydrogen generated by the metal water reaction is released into containment. Valid any time following an assident.

Sample /\nalysis lsotopis Ratio Comparison: A direst method used to establish the type of sore damage. Compares expected isotopis ratios *.vith a sample to determine a general core state . Applisable under all types of ascidents. Valid any time following an assident.

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PART II: Planning Standards And Criteria Exelon Nuclear Sample Analvsis Presence of Abnormal Isotopes: A direct method used to provide a go/no go indication of fuel melt by the presence of unusually high concentrations of the less volatile fission products. Applicable under all types of accidents. Valid any time following an accident.

Sample Analysis Concentration Evaluation: A direct method that yields the most accurate numerical estimations of the amount of core damage. Applicable for all types of acsidents. Requires the sampled system(s) be in a steady state that usually prevents its use until the plant is in a stable sondition.

4. Effluent Monitor Data and Dose Projection Dose assessment or projection represents the calculation of an accumulated dose at some time in the future if current or projected conditions continue. During an accident, the Plant Parameter Display System and personal computers will provide the ERO with the timely information required to make decisions. Radiological and meteorological instrumentation readings are used to project dose rates at predetermined distances from the station, and to determine the integrated dose received . Dose assessment methods used by Exelon personnel to project offsite doses include:

A. Monitored Release Points - This method utilizes the plant's effluent radiation monitors and system flow rates. Effluent release points are used to directly calculate a release rate. The point of the release determines the way the source term is affected and is adjusted by the dose assessment process.

B. Containment Leakage/F"ailure This method uses a variety of containment failures or leak rates in sonjunction with available sourse term estimations to develop a release rate to the environment. A direct vent of containment can be modeled as a failure to isolate.

G:-B. Release Point Samples - This method uses a sample at the release point and an estimated flow rate to develop a release rate at the point of release.

G:-C. Field Monitoring Team Data - This method uses a field survey or sample and the atmospheric model to back calculate a release rate and ratio concentrations of radioactive material at various points up and downwind of plume centerline.

The computer applications used to provide dose calculations are evaluated against the EPA-400 plume exposure Protective Action Guides (PAGs) applicable for the early phase of an accident. These evaluations place an emphasis on determining the necessity for offsite protective action recommendations. Dose assessment actions will be performed in the following sequence:

First: Onset of a release to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> post-accident: Shift personnel will rely on a simplified computerized dose model to assist them in developing offsite dose projections using real time data from effluent monitors and site meteorology.

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m. At a General Emergency classification, Exelon Nuclear will provide the state with recommendations for protective actions for the public. For incidents involving actual, potential, or imminent releases of radioactive material to the atmosphere, EPA 400-R-92-001, the NRC Response Technical Manual (RTM-96) and NUREG-0654, Supp. 3, Revision 1 are used as the basis for the general public PARs.

1) Plant Based PARs Station specific PAR Flowcharts have been developed to aid Exelon Nuclear personnel providing PARs based on the above. Station specific PAR Flowcharts with Subarea or Sector tables are documented in the Exelon EP Implementing Procedures, including station-specific requirements regarding PAR determination. These flowcharts and tables provide technically based Protective Action Recommendations based on plant conditions and sore damage indicators as applicable to the Exelon site and described within the implementing procedures. Possible plant based PARs issued by Exelon Nuclear, in support of NUREG-0654 Supp. 3, at a General Emergency could include as appropriate for the Station:

• Response to a Rapidly Progressing Severe Accident.

• Utilization of the staged evacuation concept as determined by station ETE's.

• Shelter of the general public in response to but not limited to; a oontrolled eontainment vent lasting less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in duration less than PAGs, impediments to evacuation, or Hostile Action event.

• Evacuation of the general public.

In addition to the above actions to minimize or prevent potential exposure to radiation, a recommendation of "monitor and prepare" will be issued for the remainder of the EPZ.

2) Dose Based PARs Evacuation is recommended if projected doses reach the minimum EPA PAGs (2 1 Rem EPA TEDE 1 or 2 5 Rem COE Thyroid).

Many assumptions exist in dose assessment calculations, involving both source term and meteorological factors, which make computer predictions over long distances highly questionable. However, in the event dose assessment results indicate the need to recommend actions beyond the outer EPZ boundaries, which is past 10 miles, Field Monitoring Teams are dispatched to downwind areas to verify the calculated exposure rates prior to issuing PARs outside the EPZ. In the event dose assessment results indicate the need to recommend actions beyond the outer EPZ boundaries (past 10 miles):

1 EPA TEDE is defined as the sum of the doses from external exposure and inhalation from the plume, and from 4 days of external exposure to deposited materials.

November 2021 J-6 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Establishment of Recovery can be conducted from any emergency classification level. However, it is possible that the lower classifications of Unusual Event and Alert will conclude with the event being terminated. There may be cases where certain EAL initiating conditions remain exceeded, but the station is under control and no further danger of degradation exists. In such a case, it may be appropriate to enter Recovery. Site Area and General Emergencies will require a Recovery Phase to be established prior to event termination. Exelon Nuclear may consult with/notify cognizant governmental agencies prior to declaring Recovery or event termination.

Termination/Recovery considerations are contained in the implementing procedures to provide guidance for evaluating the risk of entering Recovery without alleviating the intent of the Initiating Condition. The purpose of Recovery is to provide the necessary personnel to handle the long-term activities and to return the plant to an acceptable condition.

The following conditions are guidelines for the determination of establishing Recovery (this is not intended to be a complete list and additional criteria may apply, depending on the specifics of the event):

• The risk to the health and safety of the public has been mitigated.

• Plant parameters and equipment status have been established and controlled.

• In-plant radiation levels are stable or decreasing, and acceptable, given the plant conditions.

• The potential for uncontrolled releases of radioactive material to the environment has been eliminated.

• Environmental monitoring has been established.

• The radioactive plume has dissipated and plume tracking is no longer required (the only environmental assessment activities in progress are those necessary to assess the extent of deposition resulting from passage of the plume).

• Exelon Nuclear workers have been protected.

• Any security threat has been neutralized, and/or plant security is under the direction of Exelon Nuclear personnel.

• Adequate plant safety systems are operable.

• The reactor is in a stable shutdown condition and long term core cooling is available November 2021 M-3 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

• The fuel pool damage has been mitigated, or spent fuel damage has been contained and controlled.

Primary and/or secondary containment integrity has been established.

• Plant systems and equipment are restored and/or replaced such that plant conditions are stable highly unlikely to degrade further.

• Conditions that initiated the emergency have been contained, controlled, eliminated or stabilized such that the classification is no longer applicable.

• The operability and integrity of radioactive waste systems, decontamination facilities, power supplies, electrical equipment and of plant instrumentation including radiation monitoring equipment.

• Any fire, flood, earthquake or similar emergency condition or threat to security no longer exists.

• All required notifications have been made.

• Discussions have been held with federal, state and county agencies and agreement has been reached to terminate the emergency.

• At an Alert or higher classification , the ERO is in place and emergency facilities are activated.

• Any contaminated injured person has been treated and/or transported to a medical care facility.

• Offsite conditions do not unreasonably limit access of outside support to the station and qualified personnel and support services are available.

It is not necessary that all conditions listed above be met; however, all items must be considered prior to entering the recovery phase. For example, it is possible after a severe accident that some conditions remain that exceed an Emergency Action Level, but entry into the Recovery Phase is appropriate.

2. Recovery Organization Once plant conditions have been stabilized and the Recovery Phase has been initiated, the Emergency Director may form a Recovery Organization for long-term operations. These types of alterations will be discussed with the NRG prior to implementation.

• For events of a minor nature, (i.e. for Unusual Event classifications) the normal on shift organization is normally adequate to perform necessary recovery actions.

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• For events where damage to the plant has been significant, but no offsite releases have occurred and/or protective actions were not performed, (i.e. for Alert classifications) the station Emergency Response Organization, or portions thereof, should be adequate to perform the recovery tasks prior to returning to the normal station organization.

• For events involving major damage to systems required to maintain safe shutdown of the plant andwhere offsite radioactive releases have occurred, (i.e. for Site Area Emergency or General Emergency classifications) the station recovery organization is put in place.

The specific members of the station recovery organization are selected based on the sequence of events that preceded the recovery activities as well as the requirements of the recovery phase. The basic framework of the station recovery organization is as follows:

a. The Recoverv Director: The Corporate Emergency Director is initially designated as the Recovery Director. The Recovery Director is charged with the responsibility for directing the activities of the station recovery organization. These responsibilities include:

• Ensuring that sufficient personnel, equipment, or other resources from Exelon and other organizations are available to support recovery.

• Directing the development of a recovery plan and procedures.

• Deactivating any of the plant Emergency Response Organization which was retained to aid in recovery, in the appropriate manner. Depending upon the type of accident and the onsite and offsite affects of the accident, portions of the ERO may remain in place after initiation of the recovery phase.

• Coordinating the integration of available federal and state assistance into onsite recovery activities.

• Coordinating the integration of Exelon support with federal, state and county authorities into required offsite recovery activities.

• Approving information released by the public information organization which pertains to the emergency or the recovery phase of the accident.

• Determining when the recovery phase is terminated.

b. The Recovery Plant Manager: The Station Manager or a designated alternate will become the Recovery Plant Manager. The Recovery Plant Manager reports to the Recovery Director and is responsible for:

• Coordinating the development and implementation of the recovery plan and procedures.

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c. Medical Emergency Drills: A medical emergency drill, involving a simulated contaminated individual, and containing provisions for participation by local support services organizations (i.e., ambulance and support hospital) are conducted annually . Local support service organizations, which support more than one station, shall only be required to participate once each calendar year. The offsite portions of the medical drill may be performed as part of the required biennial exercise.

d. Radiological Monitoring Drills: Plant environs and radiological monitoring drills (onsite and offsite) are conducted annually. These drills include collection and analysis of all sample media (such as, water, vegetation, soil , and air), and provisions for communications and record keeping.

e. Health Physics Drills: Health Physics Drills involving a response to, and analysis of, simulated airborne and liquid samples and direct radiation measurements within the plant are conducted semi-annually. At least annually, these drills shall include a demonstration of the sampling system capabilities , or the Core Damage Assessment Methodology (CD/\M) osjestives as a1313lisasle .

f. Augmentation Drills: Augmentation drills serve to demonstrate the capability of the process to augment the on-shift staff with a TSC, OSC and EOF in a short period after declaration of an emergency. These drills are conducted using the following methods:

• Quarterly, each station will initiate an unannounced off-hours ERO augmentation drill where no actual travel is required. Each region's Corporate ERO shall also perform an unannounced off-hours ERO augmentation drill that may be conducted independent of, or in conjunction with, a station drill.

• At least once per exercise cycle, an off-hours unannounced activation of the ERO Notification System with actual response to the emergency facilities is conducted by each station. Each region's Corporate ERO need only participate once per cycle.

g. Accountability Drills: Accountability drills are conducted annually. The drill includes identifying the locations of all individuals within the protected area.

3. Conduct of Drills and Exercises Advance knowledge of the scenario will be kept to a minimum to allow "free-play" decision making and to ensure a realistic participation by those involved. Prior to the drill or exercise, a package will be distributed to the controllers and evaluators that will include the scenario, a list of performance objectives, and a description of the expected responses.

For each emergency preparedness exercise or drill conducted, a scenario package is developed that includes at least the following:

a. The basic objective(s) of the drill or exercise and the appropriate evaluation criteria.

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PART II: Planning Standards And Criteria Exelon Nuclear Emergency response personnel in the following categories receive knowledge and/or performance based training initially and retraining thereafter once per calendar year not to exceed 18 months between training sessions.

a. Directors. Managers and Coordinators within the station and corporate ERO:

Personnel identified by the Emergency Response Organization Telephone Directory as Directors, Managers and Coordinators for the station and corporate EROs receive training appropriate to their position in accordance with the approved ERO Training Program . These personnel receive specialized training in the areas of:

• Notifications

• Emergency Classifications

• Protective Action Recommendations

• Emergency Action Levels

• Emergency Exposure Control Selected Directors, Managers, Coordinators and Shift Emergency Directors receive training in accordance with the approved ERO Training Program. Training in accident assessment sufficient to classify an event and to mitigate the consequences of an event are also covered.

b. Personnel Responsible for Accident Assessment:

The skills and knowledge required to perform plant stabilization and mitigation are a normal function of operations specific positions, as identified in Section B of this plan. Power changes and planned and unplanned reactor shutdowns are handled on a normal operation basis. Subsequent plant stabilization and restoration is pursued utilizing normal operating procedures. Licensed Qualified Operators receive routine classroom and simulator training to ensure proficiency in this area.

1) Active Senior Licensed Control Room PersonnelCertified Fuel Handlers shall have training conducted in accordance with the approved ERO Training Program such that proficiency is maintained on the topics listed below. These subjects shall be covered as a minimum on an annual basis.

• Event Classification.

• Protective Action Recommendations.

• Radioactive Release Rate Determination.

• Notification form completion and use of the Nuclear Accident Reporting System (NARS).

• Federal, state and local notification procedures as appropriate.

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PART II: Planning Standards And Criteria Exelon Nuclear

• Site specific procedures for activating the onsite and offsite ERO.

To remove peripheral duties from the Operations shift, the following group of positions responsible for aeeident assessment, eorreetive aetions, proteetive aetions, and related aetivities reeeive the training listed below:

2) Core Damage Assessment Personnel: During an emergeney when eore/eladding damage is suspeeted, a speeialized group of trained individuals perform sore damage assessment. At a minimum, personnel responsible for sore damage assessment reseive slassroom and hands on training in the following areas:

• Available Instrumentation and Equipment

• lsotopie Assessment and Interpretation

• Computerized Core Damage Assessment Methodology (CDAM) and/or proseduralized assessment methods.

c. Radiological Monitoring Teams and Radiological Analysis Personnel

1) Offsite Radiological Monitoring: Offsite radiological monitoring is performed by trained individuals who provide samples and direct readings for dose assessment calculations and dose projection comparisons.

Personnel identified as members of Field Monitoring Teams receive training in accordance with the approved training program. Field Monitoring Team members receive classroom and hands-on training in the following areas:

• Equipment and Equipment Checks

• Communications

• Plume Tracking Techniques

2) Personnel Monitoring: Personnel monitoring is performed by trained individuals who monitor station personnel and their vehicles for contamination during an emergency. Personnel Monitoring Team members receive classroom and hands-on training in the following areas:

• Personnel Monitoring Equipment and Techniques

• Decontamination Techniques for Personnel

• Decontamination Techniques for Vehicles November 2021 0-4 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Section P: Responsibility for the Maintenance of the Planning Effort This section describes the responsibilities for development, review and distribution of the E-Plan and actions that must be performed to maintain the emergency preparedness program. It also outlines the criteria for insuring that personnel who perform the planning are properly trained.

1. Emergency Preparedness Staff Training The Emergency Preparedness staff is involved in maintaining an adequate knowledge of state of the art planning techniques and the latest applications of emergency equipment and supplies . At least once each calendar year each member of the Emergency Preparedness staff is involved in one of the following activities:

• Training courses specific or related to emergency preparedness.

• Observation of or participation in drills and/or exercises at other stations.

• Participation in industry review and evaluation programs.

• Participation in regional or national emergency preparedness seminars, committees, workshops or forums.

• Specific training courses in related areas, such as systems, equipment, operations, radiological protection, or Problem Identification & Resolution (Pl&R).

2. Authority for the Emergency Preparedness Effort The ~ite Vice PresidentPlant Manager is responsible for the safe and reliable operation of the generating station. The issuance and control of this plan and the activities associated with emergency preparedness at Dresden shall be the overall responsibility of the Vice President, Fleet Support. This individual is assigned the responsibility for overall implementation of the E-Plan and station Annex.

3. Responsibility for Development and Maintenance of the Plan Each regional Emergency Preparedness Manager is responsible for the overall radiological emergency preparedness program associated with the operation of the nuclear power stations within their respective region and to administer the program to ensure availability of resources in the event of an emergency. The regional Emergency Preparedness Managers report to an EP Director who in turn reports to the Vice President, Fleet Support.

November 2021 P-1 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear The Emergency Preparedness Managers are assisted by regional corporate and Station Emergency Preparedness staff. Specific responsibilities include the following:

Program Administration

• Develop and maintain the E-Plan, Station Annex, implementing procedures and administrative documents.

• Develop and maintain 50.54(q) evaluations for changes to EP documents.

• Coordinate and maintain the EP Activities Schedule.

• Develop and maintain working relationships and coordinate meetings with Federal, state and local agencies.

• Ensure integration of plans between Exelon and offsite agencies.

• Provide an opportunity to discuss Emergency Action Levels and the availability of Nuclear Oversight audit results relating to interface with governmental agencies.

• Coordinate, negotiate and maintain agreements and contracts with offsite agencies and support organizations.

• Obtain Letters of Agreement with medical facilities, and medical consultants specifically skilled in the medical aspects of radiation accidents and other medical consultants as might be necessary for the case of a person involved in a radiation incident.

• Coordinate the development and annual distribution of the station's public information publication.

• Coordinate and administer the Self Evaluation Program to monitor and evaluate the adequacy of the Emergency Preparedness Program.

• Coordinate and support EP Self-Assessments, Audits and Inspections.

• Ensure the documentation and resolution of adverse conditions in the emergency preparedness program discovered through drills, audits, etc. in accordance with the Exelon Nuclear Corrective Action Program.

• Coordinate and develop Operational Experience responses.

• Coordinate, document and review Performance Indicator data and reports.

• Provide oversight of Drill and Exercise Performance (DEP) evaluations during Lisense Operator Requalifisation (LOR) Training.

• Coordinate and conduct EP Event reviews and reports.

November 2021 P-2 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear The E-Plan and its Annex shall be revised as needed and the most current approved revisions shall remain in effect so long as they are certified as current. Revisions to the E-Plan are reviewed by the Station!..s Plant Operational Review Committee (SPGRC) prior to approval. Changes to the plan are made without NRC approval only if such changes do not result in a reduction in effectiveness of the plan per 10 CFR 50.54(q), and the plan as changed continues to meet the standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E. Proposed changes that reduce or have a potential to reduce the effectiveness of the approved plan are not implemented without prior approval by the NRC.

• Proposed revisions to the E-Plan and Station Annex shall be completed in accordance with the Exelon Nuclear review and approval processes.

• E-Plan and Station Annex changes shall be categorized as (1) minor/

administrative or (2) significant programmatic changes. Minor/administrative changes shall be implemented within 30 days of approval. Significant programmatic changes shall be implemented as soon as practical and within 60 days of final approval .

• After review and approval, the E-Plan and Station Annex shall be:

a) Reviewed by the applicable Emergency Preparedness Manager(s) and EP Director, or designee(s), and b) Approved for use by the Vice President, Fleet Support or designee.

• The Implementing Procedures shall be developed and revised concurrent with the E-Plan and Annex, and reviewed every two years.

Annually, each Letter of Agreement is reviewed and certified current in order to assure the availability of assistance from each supporting organization not already a party to the individual State Plan for Radiological Accidents.

5. E-Plan Distribution E-Plan manuals, Station Annex and implementing procedures are distributed on a controlled basis to the Emergency Response Facilities. All controlled documents holders are issued revision changes upon approval. Selected Federal, state, and local agencies, and other appropriate locations requiring them are also issued copies.

Procedures are in place that control the revision of the E-Plan and require the use of revision bars and individual page identifications (i.e. section of plan, revision number, etc.).

6. Supporting Emergency Response Plans Other plans that support this E-Plan are:

• NUREG-1471, US Nuclear Regulatory Commission, "Concept of Operations:

NRG Incident Response" November 2021 P-5 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear

• National Response Framework (NRF), Nuclear/Radiological Incident Annex.

• Illinois Plan for Radiological Accidents (IPRA).

• Department of Energy, Region 5, "Radiological Assistance Plan"

• l~JPO Emergency Resources Manual.

• Nuclear Station Security Plans - Note: The Station Security Plan contains industrial security information that must be withheld from public disclosure under provisions of 10 CFR 2.790(d).

7. Implementing and Supporting Procedures Appendix 2 of this plan contains a listing, by number and title, of those procedures that implement this plan during an emergency. Additionally, administrative procedures that outline the steps taken to maintain the Exelon Emergency Preparedness Program have been developed and are listed in Appendix 2.

8. Cross Reference to Planning Criteria The Plan is formatted in the same manner as NUREG-0654, FEMA-REP-1, Revision 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in support of Nuclear Power Plants." The use of this format lends itself to uncomplicated comparison of the criteria set forth in NUREG-0654, FEMA-REP-1.

9. Audit/Assessment of the Emergency Preparedness Program To meet the requirements of 10 CFR 50.54(t), Exelon Nuclear Oversight shall coordinate an independent review the Emergency Preparedness Program to examine conformance with 10 CFR 50.47, 10 CFR 50.54, and 10 CFR 50 Appendix E.

Included in the audit/assessment are the following:

• The E-Plan and associated implementing procedures.

• The Emergency Preparedness Training Program including drills and exercises.

• The readiness of the station Emergency Response Organization to perform its function .

• The readiness of facilities and equipment to perform as outlined in the plan and procedures.

• The interfaces between Exelon, the state, and county governmental agencies pertaining to the overall Emergency Preparedness Program.

November 2021 P-6 EP-DR-1000 (Revision x)

PART II: Planning Standards And Criteria Exelon Nuclear Results of this audit are submitted for review to Corporate Management and the

~tation Vice PresidentPlant Manager. The Emergency Preparedness Manager ensures that any findings that deal with offsite interfaces are reviewed with the appropriate agencies. Written notification will be provided to the state and counties of the performance of the audit and the availability of the audit records for review at Exelon facilities. Records of the audit are maintained for at least five years.

10.Maintenance of Emergency Organization Telephone Directory Names and phone numbers of the Emergency Response Organization and support personnel shall be reviewed and updated at least quarterly.

November 2021 P-7 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear

18. NUREG-0737, Clarification of TMI Action Plan Requirements, dated October 1980.

19. NUREG-0737, Supplement 1, Requirements for Emergency Response Capability, December 1982.

20. NUREG 0728 - "Report to Congress: NRC Incident Response Plan."

21. US NRC Regulatory Guide 1.101, "Emergency Planning and Preparedness for Nuclear Power Reactors," revision 4, July, 2003.

22. U.S. NRC Response Technical Manual (RTM-96)

23. NEI 99-01, Methodology for Development of Emergency Action Levels.

24. EPA 400-R-92-001, October 1991, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents."

25. FEMA-REP-10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants

26. FEMA-REP-14, Exercise Evaluation Methodology

27. FEMA-Guidance Memorandum, MS-1 "Medical Services"

28. Exelon t-Juelear Decommissioning Quality Assurance Topieal ReportProgram (QATRDQAP}, NO-AADC-10

29. Deleted lt-JPO Emergency Resources Manual

30. Deleted "Maintaining Emergency Preparedness Manual," dated December, 1996 lt-JPO 96 009.

31. "Federal Bureau of Investigation and Nuclear Regulatory Commission Memorandum of Understanding for Cooperation Regarding Threat, Theft, or Sabotage in U.S. Nuclear Industry," Federal Register, Vol. 44, p. 75535, December 20, 1979.

32. Illinois Department of Nuclear Safety, Title 32, Chapter II, Subchapter b, Part 340, "Standards for Protection Against Radiation."

33. ComEd April 1983 response to NUREG 0737 Supplement #1 or latest submitted schedule of planned operational dates.

34. "Voluntary Assistance Agreement By and Among Electric Utilities involved in Transportation of Nuclear Materials," dated November 1, 1980.

35. Comprehensive Environmental Response, Compensation and Liability Act of 1980.

November 2021 Appendix 1 Page 2 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear

36. Accidental Radioactive Contamination of Human Food and Animal Feeds; Recommendation for State and Local Agencies, Volume 47, No. 205, October 22, 1982.

37. American Nuclear Insurers Bulletin #58 (1981 }, "Accident Notification Procedures for Liability Insureds".

38. "Potassium Iodide as a Thyroid Blocking Agent in a Radiation Emergency: Final Recommendations on Use," Federal Register Vol. 47, No. 125, June 29, 1982.

39. Letter from William J. Dircks, Executive Director for Operations, NRC, to Dr.

Donald F. Knuth, President KMC, Inc. dated October 26, 1981.

40. Deleted INPO Coordination agreement on emergency information among USCE/\, EPRI, INPO, NUM/\RC and their member utilities, dated April (19BB).

41. Babcock and Wilcox Company, Post Accident Sample Offsite Analysis Program (1982).

42. ANl/MAELU Engineering Inspection Criteria For Nuclear Liability Insurance, Section 6.0, Rev. 1, "Emergency Planning."

43. NRC RIS 2006-12, Endorsement of Nuclear Energy Institute Guidance "Enhancement to Emergency Preparedness Programs for Hostile Action."

44. NRC Bulletin 2005-02, "Emergency Preparedness and Response Actions for Security-Based Events."

42. NRC Information Notice 2009-01, National Response Framework November 2021 Appendix 1 Page 3 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Appendix 3: List of Corporate Letters of Agreements Oraanization/Aqreement Type Department Of Energy (DOE) Radiation Emergency Assistance Center/Training Site, REAC/TS (Letter on File)

Medical Consultant Environmental, Inc. (P.O.)

Radiological Environmental Monitoring Landauer, Inc. (P.O .)

Emergency Dosimetry l~JPO (Letter on file)

Emergency Event Support Murray & Trettel, Inc. (P.O.)

Meteorological Support Arnita Health St. Joseph Hospital (Letter on File)

Back-up Emergency Medical Facility Teledyne Brown Engineering (P.O.)

Bioassay Analysis/Radiochemical Analysis Westinghouse Electric Company, PWRs (Letter on File)

PWR Emergency Support J.D Ingenuities (P.O.)

Emergency Met Tower National Foam, Inc.

Fire Foam Supply November 2021 Appendix 3 Page 1 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Appendix 4: Glossary of Terms and Acronyms Accident Assessment Accident assessment consists of a variety of actions taken to determine the nature, effects and severity of an accident and includes evaluation of reactor operator status reports, damage assessment reports, meteorological observations, seismic observations, fire reports, radiological dose projections, in plant radiological monitoring, and environmental monitoring.

Activation (1) "ERO Activation" is the process of initiating actions to notify and mobilize Emergency Response Organization (ERO) personnel following an event classification under the emergency plan .

(2) "Facility Activation" refers to the decision to consider a facility fully operational based on the minimum staffing required in ERO staffing tables contained within the station specific Annex and the ability of facility staffing and equipment to perform its designed function(s).

Annual Frequency of occurrence equal to once per calendar year, January 1 to December 31.

Assembly/Accountability A procedural or discretionary protective action taken for all persons within the security "Protected Area", which involves the gathering of personnel into pre-designated areas, and the subsequent verification that the location of these personnel is known.

Assessment Actions Those actions taken during or after an emergency to obtain and process information that is necessary to make decisions to implement specific emergency measures.

November 2021 Appendix 4 Page 1 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Drill A supervised instruction period aimed at testing, developing and maintaining skills in a particular operation.

Early Phase The period at the beginning of a nuclear incident when immediate decisions for effective use of protective actions are required and must be based primarily on predictions of radiological conditions in the environment. This phase may last from hours to days. For the purposes of dose projections it is assumed to last four days.

Emergency Action A pre-determined, site-specific, observable threshold for a Levels (EALs) plant Initiating Condition that places the plant in a given emergency class. An EAL can be an instrument reading; an equipment status indicator; a measurable parameter (onsite or offsite ); a discrete, observable event; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.

Emergency Alert A network of broadcast stations and interconnecting facilities System (EAS) which have been authorized by the Federal Communications Commission to operate in a controlled manner during a war, state of public peril or disaster, or other national or local emergency. In the event of a nuclear reactor accident, instructions/notifications to the public on conditions or protective actions would be broadcast by state or local government authorities on the EAS.

Emergency Director Individual in Command and Control. One of the following: the Shift Emergency Director (Control Room), Station Emergency Director (TSC) or the Corporate Emergency Director (EOF).

Emergency Notification The NRC Emergency Notification System hot line is a System (ENS) dedicated telephone system that connects the plant with NRC headquarters in White Flint, Maryland. It is directly used for reporting emergency conditions to NRC personnel.

Emergency Operations Designated location from which the Licensee Emergency Facility (EOF) Response Organization conducts the company's overall emergency response in coordination with Federal, State and designated emergency response organizations.

Emergency Operating EOPs are step-by-step procedures for direct actions taken by Procedures (EOPs) lieensed reaetorqua lified operators to mitigate and/or correct an off normal plant condition through the control of plant systems.

November 2021 Appendix 4 Page 4 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Emergency Operations A facility designed and equipped for effective coordination Center (EOG) and control of emergency operations carried out within an organization's jurisdiction . The site from which civil government officials (municipal, county, state, and Federal) exercise direction and control in a civil defense emergency.

Emergency Personnel Those organizational groups that perform a functional role during an emergency condition. Within Exelon Nuclear, emergency personnel include the Managers and Directors of the Emergency Response Organization, accident assessment personnel, radiological monitoring teams, fire brigades, first aid teams and security personnel.

Emergency Planning That area surrounding a nuclear station in which emergency Zones (EPZ) planning is conducted for the protection of the public. With respect to protecting the public from the plume exposure resulting from an incident, the EPZ is usually an area with a radius of about 10 miles surrounding the facility. With respect to the ingestion exposure pathway, the EPZ is usually an area with a radius of about 50 miles.

Emergency A state of readiness that provides reasonable assurance that Preparedness adequate protective measures can and will be taken upon implementation of the E-Plan in the event of a radiological emergency.

Emergeney Response EROS is a continuous direct near real time electronic data Data System (EROS) link between the licensee's onsite computer system and the NRG Operations Center that provides f-or the automated transmission of a limited data set of selected parameters.

Environmental The use of radiological instruments or sample collecting Monitoring devices to measure and assess background radiation levels and/or the extent and magnitude of radiological contamination in the environment around the plant. This may be done in various stages such as pre-operational, operational, emergency, and post operational.

Essential Personnel Essential personnel are those needed to achieve the goals and tasks as deemed necessary by the Station Emergency Director.

Evacuation The urgent removal of people from an area to avoid or reduce high level, short-term exposure usually from the plume or from deposited activity.

November 2021 Appendix 4 Page 5 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Exclusion Area An Exclusion Area is an area specified for the purpose of reactor site evaluation in accordance with 10 CFR 100. It is an area of such size that an individual located at any point on its boundary for two hours immediately following onset of the postulated release would not receive a total radiation dose to the whole body in excess of 25 rem or a total radiation dose of 300 rem to the thyroid from iodine exposure.

Exercise An event that tests the integrated capability of a major portion of the basic elements existing within emergency preparedness plans and organizations.

Exercise Cycle An eight-year period.

F='ission Produet Barrier The fuel cladding, reactor coolant system boundary, or the containment boundary.

Hazardous Material A substance or material which has been determined by the United States Secretary of Transportation to be capable of posing an unreasonable risk to health, safety, and property when transported in commerce, and which has been so designated in 49 CFR 172.

Health Physics Network In the event of a Site Area Emergency, the NRG HPN line will (HPN) Line be activated by the NRG Operations center in White Flint, Maryland . This phone is part of a network that includes the NRG Regional Office and the NRG Operations Headquarters in White Flint, Maryland. This system is dedicated to the transmittal of radiological information by plant personnel to NRG Operations Center and the Regional office. HPN phones are located in the TSC and EOF.

l=ligh Radiation Post ascident sampling sapability to obtain and perform Sampling System radioisotopic and ohemioal analyses of reactor coolant and containment atmosphere samples.

Imminent Mitigation actions have been ineffective and trended information indicates that the event or condition will occur within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Ingestion Exposure The potential pathway of radioactive materials to the public Pathway through consumption of radiologically contaminated water and foods such as milk or fresh vegetables. Around a nuclear power plant this is usually described in connection with the 50-mile radius Emergency Planning Zone (50 mile EPZ).

November 2021 Appendix 4 Page 6 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Protective Action Guide Projected radiological dose values to individuals in the (PAG) general population that warrant protective action. Protective Action Guides are criteria used to determine if the general population needs protective action regarding projected radiological doses, or from actual committed (measured) dose values.

Protective Action Recommended actions to the States for the protection of the Recommendations offsite public from whole body external gamma radiation, and (PARs) inhalation and ingestion of radioactive materials. Access control and other recommendations concerning the safeguards of affected food chain processes may be issued by the States as PARs.

Public Alerting/Warning The process of signaling the public, as with sirens, to turn on their TV's or radios and listen for information or instructions broadcast by state or local government authorities on the Emergency Alert System (EAS).

Puff Release A controlled containment vent that will be terminated prior to exceeding 60 minutes in duration and is less than the limit as defined in the Station Annex.

Quarterly Frequency of occurrence equal to once in each of the following four periods: January 1 through March 31; April 1 through June 30; July 1 through September 30; October 1 through December 31 .

Recovery The process of reducing radiation exposure rates and concentrations of radioactive material in the environment to levels acceptable for unconditional occupancy or use.

Release A 'Release in Progress' is defined as ANY radioactive release that is a result of, or caused by, the emergency event.

Restricted Area Any area, access to which is controlled by Exelon for purposes of protection of individuals from exposure to radiation and radioactive materials.

Restricted Area For classification and dose projection purposes, the boundary Boundary is a 400-meter (1/4-mile) radius around the plant. The actual boundary is specified in the ODCM.

November 2021 Appendix 4 Page 10 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Safety Analysis Report, The UFSAR is a comprehensive report that a utility is Updated Final (UFSAR) required to submit to the NRC as a prerequisite and as part of the application for an operating license for a nuclear power plant. The multi-volume report contains detailed information on the plant's design and operation, with emphasis on safety-related matters.

Semi-Annual Frequency of occurrence equal to once in each of the following periods: January 1 through June 30; July 1 through December 31.

Shall, Should, and May The word "shall" is used to denote a requirement, the word "should" to denote a recommendation and the word "may" to denote permission, neither a requirement nor a recommendation.

Shielding Any material or barrier that attenuates (stops or reduces the intensity of) radiation.

Site Boundary Dresden's Site Boundary is described in detail in the ODCM.

Site Evacuation The evacuation of non-essential personnel from the plant site.

Source Term Radioisotope inventory of the reactor core, or amount of radioisotope released to the environment, often as a function of time.

Technical Support A center outside of the Control Room in which information is Center (TSC) supplied on the status of the plant to those individuals who are knowledgeable or responsible for engineering and management support of sitereaetor operations in the event of an emergency, and to those persons who are responsible for management of the on-site emergency response.

Threshold Value Measurable, observable detailed conditions which must be satisfied to determine an EAL applicability.

Thyroid Blocking Agent An agent which when properly administered to an individual will result in sufficient accumulation of stable iodine in the thyroid to prevent significant uptake of radioiodine. Potassium Iodide is such an agent.

Total Effective Dose The sum of the deep dose equivalent (for external exposure)

Equivalent (TEDE) and the committed effective dose equivalent (for internal exposure) and 4 days of deposition exposure.

November 2021 Appendix 4 Page 11 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Unrestricted Area Any area to which access is not controlled by the licensee for protecting individuals from exposure to radiation and radioactive materials, and any area used for residential quarters.

Vital Areas Areas within the station security fence which contain vital equipment. Examples include Control Rooms, Containment/Reactor Buildings, Turbine Buildings and Electrical Equipment Rooms.

Vital Equipment Any equipment, system, device or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation . Equipment or systems which would be required to function to protect public health and safety following such failure, destruction, or release are also considered to be vital.

Weekly Frequency occurrence equal to once per calendar week:

Monday through Sunday.

Any abbreviation followed by a lower case 's' denotes the plural form of the term.

November 2021 Appendix 4 Page 12 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear ACRONYMS ac ........................... .... ... .... .... .. ....... ... ...... ............................................. alternating current ALARA ..................... .... ...... ... .. .. ........ .... ................ ......... as low as reasonably achievable ANI ... .... .... .... .... .... ...... .... .... ... .. .. ........ .... ...... .... .... ...... .... .... .... .. American Nuclear Insurers ANS .......... .... .... .......... ........ ... .. .. ........ .... .............. .... ............ Alert and Notification System ANSI ................. .......... ........ ... .. .. ..... ... .... ........ .... .... American National Standards Institute ARM ... .......... .... .... ... .. .. .. .. .. .... .. .. .. .. .. .. .. .. .. .. .... .. .. .. .. .. .. ... ... .. ... .... ... .. Area Radiation Monitor ASLB .. ... .. ... .... .... .......... ..... .. .. .. .. ........ .. .. .. ........ ...... ......... ... Atomic Safety Licensing Board CB .......................... .... ........... .. .......... .... ......................................................... citizen band cc .... .... .... .... .... ........ .... ........ ....... .... .... .... .............. .... .... .... ...... .... .... .... .... .. cubic centimeter COE ....................................................................................... Committed Dose Equivalent CEOC ... .... .... .... ...... .... ........ ... .. .. .... .... .... ............ .... . County Emergency Operation Center CFR .................. ...... .... ........ ... .. .. ........ .... .............. ................. Code of Federal Regulations CHRMS ....................................................... Containment High Range Monitoring System CHRRMS ................................... Containment High Range Radiation Monitoring System cm2 .... ... .. ... .... .... .... .... .... .... ... .. .. .. .. .. .. .. .. .. .... .... .... .... .... .... ...... .... .... .... .... square centimeter CNO ......... .... .... .... .... ...... .... ... .. .. ........ .... .... ...... .... .... ......................... Chief Nuclear Officer cpm .... ... .. ... .... ....... .. ... ... ..... ... .. .. ..... ... .... ....... ....... .. .. .. .. .... .... ............ .... .. .. count per minute CR .............................. ........... .. .......... .... ...................................................... Control Room CRO ..... .... .... .... ........ .......... ....... .... .... .... .............. .... .... .... ...... .... ... Control Room Operator CRT .......................... ............. .. .. ........ .... .............................................. Cathode Ray Tube Cs .......... ...... .... .... .......... .... ......... .... ........ ...... .. .. ... .... .... .... ........ ......... .... .... .... .... ..... Cesium de ... .... .... .... .... ........ .... ........ ....... .... .... .... .............. .... .... .... .... .... .... .... .... .... ..... direct current DEP ............................ ........... .. .......... .... ........................... Drill and Exercise Performance DEQ ..... .... .... .... ...... .... ........ ... .. .. ........ .... ............ .... .. Department of Environmental Quality DFO .. .... .... .... .... .... ...... .... .... ... .. .. .. .. .. .. .. .. .. .. ...... .... .... .... .... .... .... .... .... .. Disaster Field Office November 2021 Appendix 4 Page 13 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear DGI ............... .... .......... ... .... .. ... ... ..... .... ... ... ............. .... ........ .. Digital Graphics Incorporated DHFS ......................... ........... .. .......... ............. Department of Health and Family Services DLR ..... .... .... .... ........ .......... ... .. .. ........ .... .............. ...... .... .... .... .. Dosimeter of Legal Record DOE ......... .... .... ........ .......... ....... ........ .... .............. ...... ............ U.S. Department of Energy DOT. ......... .... .... .... .... ...... .... ... .. .. .. .. .. .. .. .. .. .. .. .... ...... .... . U. S. Department of Transportation DPH ...... .... .... .... .......... ........ ....... .... .... .... .............. .... .... .... .... ..Department of Public Health dpm ............................ ........... ............ ......................................... disintegration per minute DQAP ............... .......... ....................... ....... Decommissioning Quality Assurance Program EAL .................. .......... ........ ... .. .. .... ........ .............. ...................... .. Emergency Action Level EAS ....................................................................................... Emergency Alerting System EMA ............................................................................. Emergency Management Agency ENC .. .... .... .... .... .......... ........ .... ... .... .... .... .............. .... .... .... .... ...... .Emergency News Center ENS .................. .......... ........... .. .. ........ ................ ... Emergency Notification System (NRG)

EOC ......... .... .... .......... ........ ....... ........ .... ..... Emergency Operations (or Operating) Center EOF .. ...... .... .... ........ .... ........ ... .. .. ........ .... .............. .... .... .... .. Emergency Operations Facility EOP ........................................... .................................... Emergency Operating Procedure EPA .......... .... .... .... ...... .... .... ... .. .. ........ .... ...... ...... .. U. S. Environmental Protection Agency EPDS ... .... .... .... ........ ..... ..... ... .. .. ..... ... .... ..... ....... ..Emergency Preparedness Data System EPZ ............................ ........... .. .......... ...................................... Emergency Planning Zone ERF .. .... .... .... .... ........ .......... ....... .... .... .... .............. ...... .... .... . Emergency Response Facility ESF ............................ ........... .. .. ........ ...................................... Engineered Safety Feature FEMA .... .... .... .... ............ .... ......... ... .. ....... .... ..... Federal Emergency Management Agency FR MAC ...... .... ........ .... ........ ...... Federal Radiological Monitoring and Assessment Center FRMAP ......................... ........ ... .... Federal Radiological Monitoring and Assessment Plan FRPCC ... .... .... ........ .... ........ Federal Radiological Preparedness Coordinating Committee FSAR .... .... .... .... .... .... ...... .... ... .. .. .. .. .. .. .. .. .. .. .... ...... ...... .... .... ... Final Safety Analysis Report November 2021 Appendix 4 Page 14 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Ge .. ............ .... ............ ... .... .. ... ... ..... .... ... ... ........... .... .... .... ...... .................... ...... Germanium GET ............................ ............. ............ .... ............................... General Employee Training GM ... .... .... .... .......... .... ........ ... .. .. ........ .... ........ .... Geiger Mueller (radiation detection tube)

HEPA ....... .... .... ........ .......... ....... ........ .... .............. .... ............. high efficiency particulate air HPN .......... .... .... .... ...... .... .... ... .. .. .. .. .. .. .. .. .. .. .. .... .... ...... .... .. . Health Physics Network (NRC) hr ........ .... .... .... ........ .... ........ ....... .... .... .... .............. .... .... .............. ........ .... .... ........ ...... ... hour 1 .................................. . .......... . ........... . ..................................................................... Iodine IEMA ................ ........ .... ...... ... .. .. ........ .... ........ .... Illinois Emergency Management Agency IRAP ................. ...... .... ........ ... .. .. .... ........ ........ ... lnteragency Radiological Assistance Plan l~JPO ...................................................................... Institute of Nuclear Power Operations JIC .............. .... ........... .. .. .... .. ... ... ..... .... ... .... .......... .... .... .... .......... .. Joint Information Center LGEOC ..... .... .... ........ .... ....... .. ... ... ........ Local Government Emergency Operations Center Li ................................ ........... .. .. ........ ..................................................................... Lithium LOCA ......................................................................................... Loss of Coolant Aeeident LPZ ............................. ........... .. .. ........ ............................................... Low Population Zone MAE LU ...................................... ................... Mutual Atomic Energy Liability Underwriters MCP ......... .... .... .... .... .... .... ..... .. .. ........ .... .... ...... .... .... .................. Municipal Command Post mR .... .. .. .... .... .... .......... ... ..... ... .. .. ..... ... .... ..... ......... .. ... ... .... .... .......... .... .... .... .... milliroentgen NARS ......................... ........... .. .......... ........................ Nuclear Accident Reporting System NCRP ... .... .... .... ........ .......... ....... .... .... .... ............ National Council on Radiation Protection NOP ........................... ........... .. .. ........ ............................. Nuclear Organization Procedure NRC ...... ...... .... .... .......... .... ......... ... .. ....... ...... .. .... .. . U. S. Nuclear Regulatory Commission NRF .. .... ........ .... .......... ........ ....... .... .... .... ................ .... .... ... National Response Framework NRR ........................................ .......... .... ..................... Nuclear Reactor Regulation (NRC)

NWS ..... .... .... .... .......... ........ ... .. .. ........ .... .............. .... .... ...... .... .... National Weather Service NSRAC ..... .... .... .... .... .... .... ... .. .. .. .. .. .. .. .. .... .. .. Nuclear Safety Review and Audit Committee November 2021 Appendix 4 Page 15 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear OSC ............. .... .......... ... .... .. ... ... ..... .... ... .............. .... .... .... .... .... Operations Support Center PAG ............................ ........... .. .......... ........................................... Protective Action Guide PANS ... .... .... .... ........ .......... ... .. .. ........ .... ............ .... .. Prompt Alert and Notification System PAR .......... .... .... .......... ........ ....... ........ .... ............ .... .... Protective Action Recommendation PASS ............................................................................... Post Assident Sampling System QATR ................................... .. ...................................... Quality Assuranse Topisal Report R ............................................ ............ .................................................................. roentgen RAA .... ... .. ... .... .... .......... ..... .. .. .. .. ........ .. .. .. ........ .... ...... ..... Remote Assembly Area (off-site)

RAC ............................ ........... .. .......... ................ .... Regional Advisory Committee (FEMA)

RAFT .... ...... .... ........ .... ........ ....... .... .... .... ..Radiological Assistance Field Team (ILLINOIS)

RAP ................................................................... Radiological Assistance Plan (ILLINOIS)

REAC ... .... .... .... ........ ...... ........ .. Radiological Emergency Assessment Center (ILLINOIS)

REP .................. .......... ........... .. .. ........ ................ .. Radiological Emergency Preparedness RERP ....... .... .... .......... ........ ....... ........ .... ............ Radiological Emergency Response Plan RMS ..... .... .... .... ........ .......... ... .. .. ........ .... .............. .... .... .... .... . Radiation Monitoring System SCBA ........................................ ............................... Self Contained Breathing Apparatus SEOC ....... .... .... .... ...... .... .... ... .. .. ........ .... .... ...... ...... ... State Emergency Operations Center SFCP .. .. .... .... .... ........ ..... ..... ... .. .. ..... ... .... ..... ......... .. .. .... .. .... State Forward Command Post SPCC ......................... ........... .. .......... .... .... Spill Prevention Control and Countermeasure SPDS ... .... .... .... .......... ........ ....... .... .... .... ............ .... .... ... Safety Parameter Display System Sr ........................................... .. .. ........ .... ............................................................. Strontium SRC ....... ...... .... .... .......... .... ......... ... .. ....... .... .. .... ... .... ...... .... State Radiological Coordinator SSC .. .... ........ .... ...... .... ........ ....... .... .... .... .............. ........ .... .......... .... ... State Staging Center STA ............................................................................................... Shift Teehnieal Advisor TDD ................ ............ ........... .. .. ........ .... ............ Telecommunications Device for the Deaf TEDE .... .... .... .... .... .... ...... .... ... .. .. .. .. .. .. .. .. .. .. .... ...... .... .... .... .Total Effective Dose Equivalent November 2021 Appendix 4 Page 16 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear TSC .. .......... .... ............ ... .... .. ... ... ..... .... ... .............. ...... ................ Technical Support Center

µCi .............................. ........... .. .......... ...... .......................................................... microcurie UFSAR ..... .... .... ........ .......... ... .. .. ........ .... ............ .... . Updated Final Safety Analysis Report VVEM ..................................... .. ................................. \IVisconsin Emergency Management November 2021 Appendix 4 Page 17 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Appendix 5 Table 5-1: Emergency Response Organization (ERO} Staffing and Augmentation Plan TSC I OSC EOF - Alert or Emergency Greater Preparedness {EP) On-Shift Alert or Greater Alert or Greater Functions Augment Augment Augment w/in 60 min. w/in 90 min. w/in 60 min.

Command and Control

. Provide overall ERO command and control, until relieved .

• Approve emergency action level (EAL) (1)Shift (1) Station (1) Corporate Emergency Emergency Not applicable Emergency and/ or protective action Director Director Director recommendation (PAR) classifications ,

until relieved .

• Authorize personnel dose extensions, until relieved.

Communications 3

. Communicate EAL and PAR (1) ENS classifications to Shift ( 1) State I Local Communicator Not applicable offsite response Communicator 1 Communicator (TSC) organizations (OROs),

including the NRC, until relieved .

Radiation Protection

. Provide qualified radiation protection coverage for responders accessing potentially (~2 ) Additional As needed Radiation I'">\ A unknown radiological (;! 1) ,.:: I environments during Protection emergency Radiation Protection Personnel [In Not applicable addition to *-

11 ~ L'h conditions . Personnel Provide in-plant personnel on-shift]

. surveys. (OSC) witf:1iF1 9Q l'AiFI.} (OaG)

Control dosimetry and radiologically controlled area access.

November 2021 Appendix 5 Page 1 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Appendix 5 Table 5-1: Emergency Response Organization (ERO} Staffing and Augmentation Plan TSC I OSC EOF - Alert or Emergency Greater Preparedness {EP) On-Shift Alert or Greater Alert or Greater Functions Augment Augment Augment w/in 60 min. w/in 90 min. w/in 60 min.

Emergency Classifications

. Evaluate plant ~FAeF§eAey ClassifieatioA conditions and (1) Operations Not applicable Not applicable recommend Atl-vise1=~Not Manager (TSC) emergency applicable classifications, until relieved .

(1) TSC Engineer:

Provide engineering coverage for the ERO Additional staff as needed+&b

,_ c rr

,_. ~

• o 11 \ r1 II

., \ Not applicable 'I Engineering

. Provide engineering II --.J

,.._ ..... _1/1or1 *

~-

coverage rnlateEI to U:ie s13eeifie Elisei13liAe

~

As needed Not applicable

~

r - - ... i..._

of the assi§AeEI s+A.t Icon u

eA§iAeeF, until 1~ ,- - - - -- -

relieved . .. 10,..

,., I * *

~ ~

r

• u

u. 1..._ rnn 111 r

-1 111.

,- .1*

-

• r- -*

November 2021 Appendix 5 Page 3 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Appendix 5 Table 5-1: Emergency Response Organization (ERO} Staffing and Augmentation Plan TSC I OSC EOF - Alert or Emergency Greater Preparedness {EP) On-Shift Alert or Greater Alert or Greater Functions Augment Augment Augment w/in 60 min. w/in 90 min. w/in 60 min.

(1) Security Coordinator

{TSC)

Security staffing per the site-

• Coordinate Security security- related Not applicable Not applicable specific security plan . activities and information with the Emergency Coordinator.

Maintenance Personnel

{OSC)

Maintenance

. (1) l&C Technician :

Personnel Provide

{OSC) assistance with

• (1) Electrical logic Maintenance manipulation, Technician: support for event Provide mitigation and electrical equipment repair, support for and support

~ of digital l&C e~t1ipment , if applicable.

Not applicable event Additional l&C Repair Team Activities Not applicable mitigation , and staff may be equipment called out if repair. needed.

• (1) Mechanical Maintenance

. Electrical Maintenance Technician : Provide Technicians - As mechanical support needed .

for ~

e~t1ipment , event Mechanical mitigation , and Maintenance equipment repair. Technicians - As needed.

November 2021 Appendix 5 Page 4 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Appendix 5 Table 5-1: Emergency Response Organization (ERO} Staffing and Augmentation Plan TSC I osc EOF - Alert or Emergency Greater Preparedness {EP) On-Shift Alert or Greater Alert or Greater Functions Augment Augment Augment w/in 60 min. w/in 90 min. w/in 60 min.

OSC Supervisor(s)

As needed

(~) E:leetFieal MaiAteAaAee S1:113eFviseF tbea4 S1:113eF>rise OSC aetivities rnlateEI te eleetFieal eei1:1i13R'leAt.

(~) Meel:iaAieal MaiAteAaAee S1:113eF>riseF t bea4 (1) osc Director S1:113eFvise Supervision of . Supervise OSC OSC aeti><ities rnlateEI te Repair Team Not applicable activities as R'leeRaAieal Not applicable Activities directed by eei1:1i13R'leAt.

Emergency Coordinator. (~) l&C S1:113eF>riseF t LeaEI: S1:113eF>rise OSC aeti~*ities FelateEI te l&C eei1:1i13R'leAt. May 13e 69R'lSiAeEI witA E:leetFieal S1:113eF>riseF.

. (1) Radiation Protection Supervisor I Lead 1 : Supervise OSC activities related to radiation protection.

November 2021 Appendix 5 Page 5 EP-DR-1000 (Revision x)

PART Ill: Appendices Exelon Nuclear Appendix 5 Table 5-1: Emergency Response Organization (ERO} Staffing and Augmentation Plan TSC I OSC EOF - Alert or Emergency Greater Preparedness {EP) On-Shift Alert or Greater Alert or Greater Functions Augment Augment Augment w/in 60 min. w/in 90 min. w/in 60 min.

Onsite FM Individual

• (1) QllalifieEI iREli"iElllalRP Personnel to assess the protected area for radiation and contamination and Offsite FMT B provide input to the TSC RPM. * (1) Qualified Responsible for individual to radiation protection assess the area(s) coverage for the outside the FMT as directed protected area for by TSC RPM or radiation and EOF RPM. contamination ,

7 and for radioactive plume tracking, as Offsite FMT A directed by, and Field Monitoring Not applicable under the control Not applicable Teams {FMTs) * (1) Qualified of, the EOF DAC individual to assess or RPM.

the area(s) outside Responsible for the protected area the radiation for radiation and protection contamination, and coverage of the for radioactive FMT as directed plume tracking, as by EOF RPM .

directed by, and * (1) Driver to under the control of, provide the EOF DAC or transportation.

RPM. Responsible for the radiation protection coverage of the FMT as directed by EOF RPM.

• (1) Driver to provide transportation.

November 2021 Appendix 5 Page 6 EP-DR-1000 (Revision x)