ML040710474

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Emergency Preparedness Plan
ML040710474
Person / Time
Site: Beaver Valley
Issue date: 03/02/2004
From: Pearce L
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2015-0005
Download: ML040710474 (110)
v • d • e


Text

Emergency Preparedness Plan TABLE OF CONTENTS PAGE

1. DEFINITIONS 1-1
2. SCOPE AND APPLICABILITY 2-1
3.

SUMMARY

OF EMERGENCY PREPAREDNESS PLAN 3-1 3.1 ONSITE EMERGENCY ORGANIZATION 3-1 3.2 OFFSITE EMERGENCY ORGANIZATION 3-2 3.3 EMERGENCY MEASURES 3-4 3.4 EMERGENCY FACILITIES 3-7 3.5 MAINTAINING EMERGENCY PREPAREDNESS 3-7

4. EMERGENCY CONDITIONS 4.0 EMERGENCY ACTION LEVEL BASES 4-1 4.1 CLASSIFICATION OF EMERGENCIES 4-1 4.2 EAL BASES 4-7 4.3 EAL MATRIX 4-10 4.4 INDIVIDUAL EAL BASIS DESCRIPTIONS 4-15 4.5 SPECTRUM OF POSTULATED ACCIDENTS 4-17
5. EMERGENCY ORGANIZATION 5-1 5.1 NORMAL OPERATING ORGANIZATION 5-1 5.2 BVPS EMERGENCY ORGANIZATION 5-1 5.3 NUCLEAR COMMUNICATIONS 5-18 CONTROLLED BVPSiUNIT 3 REVISION 26

Emergency Preparedness Plan TABLE OF CONTENTS PAGE 5.4 EMERGENCY ORGANIZATION STAFFING 5-23 5.5 AUGMENTATION OF THE ONSITE EMERGENCY ORGANIZATION 5-25 5.6 COORDINATION WITH PARTICIPATING GOVERNMENT AGENCIES 5-27

6. EMERGENCY MEASURES 6-1 6.1 EMERGENCY INITIATION 6-1 6.2 ACTIVATION OF THE ONSITE EMERGENCY ORGANIZATION 6-1 6.3 ACTIVATION OF THE EMERGENCY SUPPORT GROUPS 6-7 6.4 ACTIVATION OF OFFSITE EMERGENCY RESPONSE ORGANIZATIONS 6-9 6.5 ASSESSMENT ACTIONS 6-12 6.6 CORRECTIVE ACTIONS 6-23 6.7 PROTECTIVE ACTIONS 6-24 6.8 AID TO AFFECTED PERSONNEL 6-40 6.9 EMERGENCY PUBLIC INFORMATION 6-43
7. EMERGENCY FACILITIES AND EQUIPMENT 7-1 7.1 ONSITE EMERGENCY CENTERS 7-1 7.2 EMERGENCY SUPPLIES 7-6 7.3 COUNTY AND STATE EMERGENCY CENTERS 7-7 CONTROLLED BVPS UNIT 3 REVISION 26

Emergency Preparedness Plan TABLE OF CONTENTS PAGE 7.4 ASSESSMENT FACILITIES 7-8 7.5 PROTECTIVE FACILITIES 7-15 7.6 COMMUNICATIONS SYSTEMS 7-17 7.7 ONSITE FIRST AID AND MEDICAL FACILITIES 7-22 7.8 DAMAGE CONTROL EQUIPMENT 7-23

8. MAINTAINING EMERGENCY PREPAREDNESS 8-1 8.1 ORGANIZATIONAL PREPAREDNESS 8-1 8.2 MANAGER, EMERGENCY PREPAREDNESS 8-10 8.3 REVIEW AND UPDATING 8-11 8.4 MAINTENANCE AND INVENTORY OF EMERGENCY EQUIPMENT AND SUPPLIES 8-13 8.5 NUCLEAR COMMUNICATIONS 8-14 8.6 NRC/FEMA 8-15
9. RE-ENTRY AND RECOVERY 9-1 9.1 TRANSITION FROM RESPONSE TO TERMINATION AND/OR RECOVERY 9-1 9.2 TERMINATION CRITERIA 9-2 9.3 RE-ENTRY 9-2 9.4 RECOVERY 9-3 9.5 RECOVERY OPERATIONS 9-3 9.6 POST-ACCIDEGO{\JROLUED BVPS iUNIT 3 REVISION 26

Emergency Preparedness Plan TABLE OF CONTENTS

10. APPENDICES A. Letters of Agreement B. Demography and Evacuation Evaluation C. Emergency Implementing Procedures D. Equipment Listings E. Corporate Policy Statement F. Warning Sirens G. References CONTROLLED BVPSv UNIT 3 REVISION 26

Emergency Preparedness Plan A5.735A SECTION 6 EMERGENCY MEASURES CONTROLLED Rev. 19 BVPS UNIT 3

Emergency Preparedness Plan Section 6 EMERGENCY MEASURES Table of Contents Pare No.

6.0 EMERGENCY MEASURES .................................................. 1 6.1 EMERGENCY INITIATION .................................................. 1 6.2 ACTIVATION OF THE ONSITE EMERGENCY ORGANIZATION ............. 1 6.2.1 Activation for Unusual Events ........................... ....................... 2 6.2.2 Activation for Alert Emergencies .................................................. 2 6.2.3 Activation for Site Area Emergency and General Emergency ................ 4 6.2.4 Activation of the Emergency Facilities ................................................... 5 6.3 ACTIVATION OF THE EMERGENCY SUPPORT GROUPS .............. .......... 7 6.3.1 Offsite Emergency Response Groups .................................................. 7 6.3.2 FENOC Corporate Organization .................................. 8...............8 6.3.3 Other Organizations Providing Onsite Support ....................................... 8 6.4 ACTIVATION OF OFFSITE EMERGENCY RESPONSE ORGANIZATIONS.............................................................................................9 6.4.1 Initial Notifications .................................................. 9 6.4.2 Follow-up Notifications ................................................. 10 6.4.3 Subsequent Notifications ................................................. 12 6.5 ASSESSMENT ACTIONS .................................................. 12 6.5.1 General Assessment Actions . ................................................. 12 6.5.2 Plant Systems Status ................................................. 14 6.5.3 Dose Projection ................................................. 14 64i Rev. 19

Emergency Preparedness Plan Section 6 EMERGENCY MEASURES Table of Contents Pame No.

6.5.4 Field Radiological Monitoring ......................... 21

.1 In-plant Radiological Surveys .22

.2 Onsite Radiological Monitoring .22

.3 Offsite Radiological Monitoring--Gaseous Release .22

.4 Offsite Radiological Monitoring--Liquid Release .23

.5 Emergency Environmental Monitoring .23 6.6 CORRECTIVE ACTIONS .. 23 6.7 PROTECTIVE ACTIONS .. 24 6.7.1 Onsite Protective Actions .24

.1 Evacuation .24

.2 Local Evacuation .25

.3 Site Assembly .26

.4 Site Evacuation .27

.5 Personnel Accountability .27

.6 Contamination Control .28

.7 Exposure Control .30

.8 Respiratory Protection .31 6.7.2 Offsite Protective Actions ...................... 32

.1 Protective Actions Within Beaver County, PA .33

.2 Protective Actions Within Columbiana County, OH .36

.3 Protective Actions Within Hancock County, WVA 36

.4 Public Warning System .37

.5 Protective Action Guides and Recommendation of Protective Actions .38 6-ii Rev. 19

Emergency Preparedness Plan Section 6 EMERGENCY MEASURES Table of Contents Paae No.

6.8 AID TO AFFECTED PERSONNEL ......................... 40 6.8.1 Personnel Decontamination ............................. 40 6.8.2 First Aid............................. 41 6.8.3 Medical Transportation ............................. 41 6.8.4 Medical Treatment ............................. 42 6.9 EMERGENCY PUBLIC INFORMATION ........ ..................... 43 6-fli Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES 6.0 EMERGENCY MEASURES Emergency Measures are actions taken to ensure that an emergency situation is assessed and that proper corrective and/or protective actions are taken. These actions include activation of the appropriate components of the emergency organizations, both onsite and offsite; assessment of plant systems status and radiological conditions; corrective actions to ameliorate or terminate an emergency situation; protective actions to minimize the consequences of the emergency to Site personnel and to the general public in the Site environs; decontamination and medical treatment for Site personnel; and other supporting actions such as timely and accurate emergency news releases to the public.

6.1 EMERGENCY INITIATION Emergency actions are initiated primarily in response to alarmed instrumentation, but may be initiated through notification to the Control Room by the first individual at the Beaver Valley Power Station to become aware of an apparent emergency situation. The Reactor Operator (RO) performs the necessary immediate actions to contend with the off-normal situation in accordance with Abnormal Operating Procedures, instrument alarm response procedures and/or Operating Procedures (BVPS Op Manual). The RO promptly notifies Shift Supervision of the potential emergency situation. The Shift Manager assesses the situation and, if necessary, declares the emergency. The Shift Manager assumes the role of Beaver Valley Power Station Emergency Director until he is relieved of that responsibility by the On-call Emergency Director. The Emergency Director continues to assess and classify the condition and initiates the appropriate corrective and protective actions and ensures activation of the necessary segments of the total emergency organization.

The Emergency Operating Procedures contain appropriate action statements, which refer the operator to this Emergency Preparedness Plan when specified plant parameter values are exceeded or equipment status warrants such response.

6.2 ACTIVATION OF THE ONSITE EMERGENCY ORGANIZATION This section describes the provisions for notifying or activating personnel in the onsite Emergency Response Organization for response to emergency events at the Beaver Valley Power Station. Action levels and recognition criteria, which dictate the appropriate emergency classifications, are described in Section 4. The composition of the onsite emergency organization and the assigned responsibilities and authorities of each member of the organization is described in Section 5. The activation process for each emergency classification is described in more detail in the Emergency Implementing Procedures.

6-1 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Table 6.1 summarizes the notification/activation of both the onsite and the offsite emergency response organizations and designates immediate action requirements for each emergency classification. Table 6.2 tabulates the organizations notified, the point of notification, provision for 24-hour coverage, and the communications equipment used, for each notification made.

6.2.1 Activation for Unusual Events Upon being informed of an emergency event, which corresponds to an Unusual Event, as defined in Section 4, the Shift Manager will immediately begin to assess and evaluate the situation. He will ensure that appropriate actions have been initiated to maintain the safe and proper operation of the Site. As Emergency Director, the Shift Manager, will concern himself with the emergency response activities, delegating responsibility for corrective actions to return the plant to a safe mode and other plant operations to the Unit Supervisor.

For most Unusual Event emergencies, the emergency response functions can be performed by the on-shift emergency response organization without augmentation by called-in personnel. In these cases, the Shift Manager will ensure that the appropriate emergency functions are performed in a timely manner consistent with the nature of the emergency. The Shift Manager may designate one or more individuals from the on-duty shift to assist in this effort.

6.2.2 Activation for Alert Emergencies Once an off-normal condition has been classified as an Alert, either initially or as an escalation from Unusual Event, the entire onsite Emergency Response Organization (as illustrated in Figure 5.3), will begin activation. The Shift Manager will:

.1 Classify the condition as an Alert.

.2 Implement immediate actions in accordance with this Plan and the applicable Emergency Implementing Procedures.

6.2 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

.3 Ensure the following key Emergency Coordinators are notified, as needed, using the Beeper paging system or telephone communications:

  • Emergency Director
  • Assistant to the Emergency Director
  • TSC and EOF Operations Coordinator
  • Operations Communicator
  • Communication and Records Coordinator
  • Radiological Controls Coordinator
  • Technical Support Coordinator
  • Maintenance Coordinator
  • Engineering Coordinator
  • Operations Support Center Coordinator
  • Operations Support Center Health Physics Coordinator
  • Environmental Assessment and Dose Projection Coordinator
  • Security Coordinator
  • Chemistry Coordinator
  • Computer Coordinator
  • Environmental Coordinator NOTE These Emergency Coordinators will initiate additional call-out of personnel, as needed.

.4 Once the designated Emergency Director, or alternate, arrives and assumes the position, the Shift Manager will re-assume control of the operation of the plant from the Unit Supervisor.

6-3 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES NOTE The Emergency Director will ensure that the designated Emergency Recovery Manager, or alternate, is notified and placed on standby.

6.2.3 Activation for Site Area Emergency or General Emergenca Once an off-normal condition has been classified as a Site Area Emergency or General Emergency, either initially or as an escalation from a lower classification, the entire offsite emergency response organization (as illustrated in Figure 5.4),

will be activated. The Emergency Director (Shift Manager, until relieved) will:

.1 Classify the condition as a Site Area or General Emergency, as appropriate.

.2 Implement immediate actions in accordance with this Plan and the applicable Emergency Implementing Procedures.

NOTE The Shift Manager retains the authority and responsibility of the Emergency Director until properly relieved.

.3 Ensure the following key Emergency Managers are notified, as needed, using the Beeper Paging System or telephone communications, if not already completed.

  • Assistant to the Emergency Recovery Manager
  • Offsite Agency Liaison
  • Support Services Manager
  • Senior, Nuclear Communications Representative
  • Joint Public Information Center Manager
  • Chief Company Spokesperson 6-4 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES NOTE These Emergency Managers will initiate additional call-out of personnel, as needed.

.4 When the Emergency Operations Facility is operational, transfer Environmental Assessment and Dose Projection activities to the EOF.

6.2.4 Activation of the Emergency Facilities In the event of any off-normal event requiring implementation of the Emergency Preparedness Plan, the emergency response commences within the Control Room and emergency response functions are transferred to the designated emergency facilities as the incident escalates in severity and/or as the emergency response organization is activated. Beaver Valley Power Station will maintain an emergency organization and notification system, which will have the objective of meeting the response times in Table B-1 of NUREG-0654. It is recognized that 100% staff augmentation, within 30 minutes, may not be achievable under all circumstances. The onsite staff shall be augmented as soon as reasonably achievable. Section 7 describes the function, responsibilities, equipment, and communications of these emergency facilities. Emergency facilities are not usually activated for Unusual Events, but the Technical Support Center is activated for Alert and higher emergency conditions, and the Emergency Operations Facility is activated for Site Area Emergency or General Emergency.

This section describes the activation of these facilities. Emergency Implementing Procedures provide other detailed information on the activation of these facilities.

.1 Control Room The Control Room is initially the primary location of plant management control of emergencies and would under most circumstances provide sufficient capabilities to contend with emergencies classified as Unusual Events.

If an Alert or higher emergency occurs, the plant management functions would be transferred from the Control Room to the Technical Support Center. Upon arrival of the designated Emergency Director, Emergency Coordinators, and satisfactory energization of instrumentation and communications equipment activation will occur.

65 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

.2 Technical Support Center (TSC)

The Technical Support Center serves two functions, the first being plant management control of the emergency, and second, engineering and technical support of the emergency response. The first function is satisfied by the BVPS Emergency Response Organization illustrated in Figure 5.3.

These personnel are activated by a call out initiated by the Shift Manager.

The second function is served in the Technical Support position of the TSC and is manned by qualified technical and engineering personnel. The TSC staff calls upon other BVPS engineering personnel, as necessary, to contend with then-existing conditions.

.3 Operations Support Center (OSC)

The Operations Support Center (OSC) is primarily an assembly area for emergency response personnel and shift personnel needed for supplemental emergency maintenance team responses. An OSC Coordinator maintains accountability and interfaces with the TSC and the Control Room.

The Radiological Controls Coordinator is stationed at the Technical Support Center, and would direct Health Physics activities through the OSC-Health Physics Coordinator in the OSC. The OSC H.P. Coordinator, would call-in Radcon Technicians, as necessary. If the nature of the emergency renders the OSC unusable due to radiological conditions, OSC operations are transferred to the Alternate OSC. No other formal assignments are made to the OSC.C 15

.4 Emergency Operations Facility (EOF)

The Emergency Operations Facility is activated for any emergency classified as Site Area or General. Personnel to staff the EOF are notified simultaneously with the TSC emergency organization. Offsite agencies may supply a liaison to the EOF as part of the activation of their individual emergency response organizations.

6-6 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

.5 Joint Public Information Center (JPIC)

In the event of any emergency condition at the Beaver Valley Power Station, First Energy Communications is notified as part of the initial notification process for offsite agencies and following completion of notifications to local and state emergency response organizations. The Joint Public Information Center (JPIC) is not activated for Unusual Events. For Alert emergencies, the JPIC is placed on standby. For Unusual Events or Alerts, Company news announcements will be distributed from the Corporate Offices or from the JPIC upon its activation. For Alert emergencies, Communications Representatives will report to the Emergency Operations Facility to initiate development of news announcements and to anticipate the activation of the JPIC should the incident escalate.

For Site Area Emergency or General Emergency, the Communications Emergency Response Team will activate the JPIC, located adjacent to the Alternate EOF in Coraopolis, PA.

6.3 ACTIVATION OF THE EMERGENCY SUPPORT GROUPS 6.3.1 Offsite Emergency Response Groups The Emergency Director shall ensure that appropriate offsite emergency response groups are contacted to provide the type and level of emergency assistance which may be required to deal with the existing emergency condition. The organizations listed below may be contacted for assistance. Methods available for contacting these support groups include direct telephone communications with individual organizations and message relay through the Beaver County Emergency Services Center. Each of these agencies can be notified and can respond on a 24-hour-per-day basis.

  • The Medical Center, Beaver
  • University of Pittsburgh Medical Center-Presbyterian University Hospital
  • Offsite fire departments
  • Offsite ambulance services 6-7 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

  • Beaver County Sheriffs Department (security assistance) 6.3.2 First Energy Operating Company (FENOC) Corporate Organization Notifications will be made to FENOC Headquarters as appropriate to the type and severity of conditions at the Beaver Valley Power Station. The method for alerting the corporate organization from BVPS is a graded system of notifications, which, to the extent possible, follows normal organizational lines of communications. Once the emergency has been declared, the Shift Manager shall notify the designated Emergency Director, who in turn will notify the Manager, Operations. Additional notifications to FENOC management will be made, consistent with the nature and severity of the emergency. Communications personnel are activated as part of the Onsite Emergency Response Organization.

6.3.3 Other Organizations Providing Onsite Support The Westinghouse (E) Water Reactors Division provides emergency assistance to the Beaver Valley Power Station under the provisions of the W Emergency Response Plan. In the event of an Alert or higher Emergency, the Communications & Records Coordinator or designee notifies the W Water Reactors Division. Upon receipt of this notification, the W plan is initiated and the W emergency organization is activated. If appropriate, Site Response Personnel will be dispatched to the onsite Technical Support Center. The W plan provides for 24-hour-per-day notification and response capability.

Assistance from contractor groups and other utilities is not considered to be an immediate action. Thus, these groups will be contacted by TSC and/or EOF personnel as necessary to augment onsite personnel.

The FENOC Institute for Nuclear Power Operations (INPO) administrative point of contact coordinates all requests for emergency assistance.

6-8 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES 6.4 ACTIVATION OF OFFSITE EMERGENCY RESPONSE ORGANIZATIONS The Emergency Director shall ensure that offsite authorities are notified and apprised of emergency events at the Beaver Valley Power Station. Notifications are either initial or follow-up. Initial notifications inform offsite agencies that an event has occurred and, as applicable, the emergency response actions necessary. Follow-up notifications provide technical information on the incident on a periodic basis. For Site Area or General Emergencies, the offsite agencies in the Emergency Operations Facility will interface with the BVPS emergency organization through the Offsite Agency Liaison, as necessary.

Detailed notification procedures, call-lists, and notification forms are provided in Emergency Implementing Procedures. Procedures include the use of a code word for authenticating notificationsC2. The communications systems used for notification are described in Section 7 of this Emergency Preparedness Plan.

6.4.1 Initial Notifications Notifications are made to the offsite authorities listed below:

  • Columbiana County Emergency Management Agency (Ohio)
  • Ohio Emergency Management Agency

CCEMA and HCOES both notify their respective state organizations. Each organization notified performs notifications in addition to those specified in accordance with their respective emergency response plans and procedures.

6-9 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Since the initial contact with offsite authorities is generally made to a communications operator or other similarly qualified individual, the initial notification will be simple, brief, and factual. To facilitate notification, Initial Notification message forms are supplied to all appropriate offsite agencies. These forms contain pre-printed text with blanks for incident specific information.

Where feasible, the blanks contain a choice of words and/or phrases which, when circled, complete the message text. The message provides information that an emergency condition exists, the classification of that emergency, whether or not a release of radioactive material is occurring or could occur, and recommendations for offsite protective actions.

Upon receipt of an initial notification the individual contacted at each agency notifies the Director of that agency, or other designated personnel and relays the message provided in the initial notification. The cognizant individual then contacts the facility for additional follow-up technical information. In Pennsylvania, DEP/BRP performs the call-back for PEMA.

The process described above provides necessary notifications in a manner, which facilitates accuracy and provides for verification of the notification.

Notification of an Unusual Event is primarily to ensure that the authorities are cognizant of the details of events, which might arouse public concern and initiate inquiries by the news media, or members of the public.

Primary means of notification is by regular telephone. A Emergency Telephone System (ETS) connection onsite for contacting the USNRC, and "hot-line" exists between the Site and DEP/BRP. Back-up radio communications capability exists between the Control Room and each of the risk county Emergency Operations Ceniers (EOCs). See Table 6.2.

6.4.2 Follow-up Notifications The follow-up notification form serves two purposes: The first is to provide technical information on the emergency directly to those individuals qualified to use the data. The second is to provide a means for offsite authorities to verify the authenticity of any emergency notification.

6-10 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES A Follow-up Notification Form has been developed and supplied to all appropriate offsite agencies. Similar in format to the Initial Notification Form, the Follow-up Notification Form contains data blanks which, when filled in, provide the following information:

  • Location of incident and name and telephone number of caller
  • Date/time of incident
  • Class of emergency
  • Type of actual or projected release and estimated duration/impact times
  • Estimate of quantity of radioactive material released or being released and the points and height of releases
  • Chemical and physical form of released material, including estimates of the relative quantities and concentration of noble gases, iodines and particulates
  • Meteorological conditions and stability
  • Actual or projected dose rates at site boundary; projected integrated dose at site boundary
  • Projected and integrated dose at peak for 2, 5 and 10 miles
  • Estimate of any surface radioactive contamination inplant, onsite and offsite
  • Licensee response actions underway
  • Recommended emergency actions, including protective measures
  • Request for any needed onsite support by offsite organizations
  • Prognosis for worsening or termination of event based on plant information Unlike the Initial Notification Form, the Follow-up Form is not intended to be relayed word-for-word. The objective of the form is to standardize the information provided to offsite agencies by different communications personnel.

Following activation of the Emergency Operations Facility (EOF), technical data will be provided directly to state, local, and Federal liaison personnel at the EOF, providing additional information in conjunction with the Follow-up Notification Form.

6-11 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES 6.4.3 Subsequent Notifications In the event it becomes necessary to escalate an emergency classification, the Initial Notification Form will be used, in the manner described for initial notification, to notify offsite agencies of the escalation of the emergency.

6.5 ASSESSMENT ACTIONS Provisions are made for assessment throughout the course of an emergency to ensure effective coordination, direction, and upgrading of emergency activities in a timely manner. The assessment actions are described, in detail, in Emergency Implementing Procedures. Assessment facilities and equipment are described in Section 7 of this Plan.

The assessment functions, the general methodology, and the techniques utilized are identified in this section.

6.5.1 General Assessment Actions

.1 Unusual Event Continuous assessment of the status of plant systems and radiological conditions is provided by plant instrumentation and is supplemented by routine surveillance functions. The occurrence of an Unusual Event will be recognized by instrument alarms or indications, surveillance results, or other observations of an off-normal condition by an individual at the site.

For events which require dispatching the Emergency Squad (or additional emergency teams), the initial and continuing assessment will be performed by the Emergency Squad Chief. His training and experience enable him to evaluate the condition and implement the proper corrective actions.

Offsite dose projections may be performed if the event involves radiological effluent releases. These dose projections are continually repeated throughout the duration of the release to reflect any significant changes. If warranted, the emergency classification will be upgraded to an Alert or higher. Methods for performing rapid dose projections are described in detail in Emergency Implementing Procedures, and are summarized in Section 6.5.3.

6-12 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

.2 Alert Assessment action for an Alert include upgrading of the functions performed for an Unusual Event as appropriate for the condition.

Examples are:

  • Increased surveillance of in-plant instrumentation
  • Additional assistance obtained from off-duty personnel and/or offsite support groups
  • Extended radiological monitoring
  • Intensified dose projection activities

.3 Site Area Emergency Assessment actions for a Site Area Emergency will be responsive to the increased probability of major failure of plant safety functions and a higher potential for release of significant quantities of radioactive material.

Examples include:

. Increased surveillance of instrumentation, which may provide information on the status of the core and reactor coolant system.

  • Increased offsite monitoring efforts.
  • Coordination of offsite dose assessment activities with DEP/BRP.

.4 General Emergency The emphasis of assessment actions for a General Emergency will be placed on the likelihood of substantial core degradation, potential loss of containment integrity and release of significant quantities of radioactive material. Surveillance of instrumentation relative to the core condition, reactor coolant system activity, containment pressure and radiation level, and radioactive effluents will be increased. Dose projection and offsite monitoring efforts will be further intensified and communications will be maintained with DEPIBRP and corresponding agencies in Ohio and West Virginia to ensure that offsite dose assessments are based on the best available informnation.

6-13 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Recommendations for protective actions will be provided, as applicable, to PEMA, BCEMA, OEMA, CCEMA, WVOES and HCOES.

6.5.2 Plant Systems Status Process and effluent parameter monitoring instrumentation has been installed to provide a capability to identify that an off-normal condition exists, to determine the extent and nature of the off-normal condition, to assess the radioactivity in effluent paths, and to determine the effectiveness of corrective and mitigative measures such as safety injection or containment isolation. This equipment is described in Section 7 of this Plan and in the BVPS Updated Final Safety Analysis Report (FSAR) and Operating Manual.

The Reactor Operator has primary responsibility for monitoring and assessing plant systems status, reporting such status to shift supervision, and taking appropriate corrective action in a timely manner.

The Staff Nuclear Advisor supports the shift operations personnel in assessing off-normal conditions and in recommending appropriate corrective action.

When activated, the Technical Support Center (TSC) will augment the Staff Nuclear Advisor in performing accident assessment activities and in recommending corrective actions to place the plant in a safe configuration and to mitigate the consequences of the event. The TSC staff has access to all plant parameter indications through analog/digital data and voice communication links.

6.5.3 Dose Projection

.1 General Dose projection is the assessment of the radiological consequences of an accidental release of radioactive material from the Site. The primary objective of these consequence assessments is to support decisions regarding the need for protective actions for members of the general public. A multi-component capability for performing dose projections for both gaseous and liquid radioactivity releases from the Site has been established. Necessary radiological, process, and meteorological information to support this assessment activity have been provided in the Control Room and in the TSC/EOF, and are described in Section 7 of this Plan.

6-14 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES There are several principles that are reflected in the dose projection methodology and implementing procedures at the Beaver Valley Power Station. These principles are:

. Dose projections are primarily performed to support decisions on offsite protective action recommendations in slowly developing emergency situations. Protective action decisions for quickly developing situations are based on pre-calculated Emergency Action Levels and plant systems status assessments.

. Time permitting, dose projection results may be considered in conjunction with results from plant systems status assessments in protective action decisions. In the event of a significant discrepancy between a protective action indicated by dose projection results and that indicated by plant systems status assessments, the most conservative (i.e., leading to the lower population dose) recommendation that cannot be readily discounted shall be relayed to appropriate offsite agencies.

  • Compatibility in the dose assessment methodologies used by BVPS and the offsite agencies is largely an unachievable goal. The level of technical sophistication varies greatly from agency to agency.

Technical information regarding the BVPS methodologies is routinely made available to these agencies and periodic comparison exercises are conducted.

. BVPS personnel will make every reasonable effort to resolve differences that may arise between onsite dose projection results and those results generated by the various offsite response agencies.

However, in the absence of a resolution of the differences, the BVPS protective action recommendations shall be based on the onsite dose projection results, and/or plant systems status assessments.

.2 Dose Projection Capabilities The dose projection capabilities and the implementing procedures provide methods for performing dose projections under a wide range of circumstances. There are four major components to the BVPS dose projection capability: (1) Computer-assisted Class A Model, (2) 6-15 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Computer-assisted Class B Model, (3) Class A Model Hand Calculational Methods, and (4) Liquid Release Computer assisted and hand calculational models. These models are described in detail in supporting technical documentation, and procedures for their use are included in the Emergency Implementing Procedures EPP/IP-2.xx series. In brief summary:

Computer-Assisted Class A Model The dose assessment capabilities at BVPS are centered around the Atmospheric Radioactivity Effluent Release, Assessment System (ARERAS). ARERAS is a data collection and analysis system comprised of two (2) computers, associated data storage, display terminals, and communication hardware, configured in two (2) redundant nodes. Each node is independently powered from one of two battery-supplied uninterruptable power distribution systems in the Emergency Response Facility. Meteorological and effluent radiological information is continuously collected and stored by ARERAS.

ARERAS runs the proprietary MIDAS (Meteorological Information and Dose Assessment System, Pickard, Lowe and Garrick, Washington, DC) software. The BVPS implementation of MIDAS contains the generic MIDAS code modules adapted to the BVPS site through extensive site adaptation parameter files.

NAEXEC (Variable Trajectory Plume Segment Model) is the Class A model in the BVPS implementation. This model provides the user with a variable trajectory plume segmented model dose projection capability. Flexible run time option choices provide for varying combinations of data sources, accident source terms, decay periods, report types, and other parameters. Reports available include X/Q, gamma dose, inhalation thyroid, and projected TEDE and CDElthyroid dose.

Computer-Assisted Class B Model In addition to the Class A model, the BVPS implementation of MIDAS incorporates an advanced Class B model. This model employs modified potential field with tracker particle technology

("particle-in-cell"). The wind field is a 25 x 25 rectangular grid matrix covering the 50 mile environs of the site. There can be up to six (6) vertical layers. To enable addressing the wind shear that may 6-16 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES occur in the valley, the model can generate two (2) independent wind fields -- one on top of the other. A three-dimensional digitized grid map of the surrounding terrain supplements the wind field grid, and makes the model specific to BVPS. A new wind field is generated every simulated 15 minute period, as necessary, using actual or forecast meteorological information.

Into this wind field, the model injects tracker particles that carry source term data. Every simulated 15 minutes, the model injects 240 particles into the field. These particles, along with the particles from prior time steps, are allowed to disperse through the wind field. Each time step, the dispersion halts, and the model counts the particles in each cell, transposing the data into a polar coordinate grid of 64 angular sectors and 15 radial sectors. Ground deposition, if applicable to the source term mix, is applied as a vector quantity. This model operates within the same user interface as the Class A model, with many of the same run-time options. The model is operated by qualified Environment Assessment and Dose Projection personnel in the EOF, and is used primarily to verify the results of the initial Class A model runs and in post-accident assessments.

Class A Hand Calculation Methods There are several hand calculational procedures in the emergency preparedness plan implementing procedure series 2.6x. Prior to the implementation of the computer assisted methods identified above, these procedures were the primary means of performing dose projections at BVPS. These procedures are now retained as a backup methodology should the computer-assisted methods become unavailable. Each procedure addresses a particular dose projection calculation. Of these procedures, EPP/IP-2.6.1, "Dose Projection --

Backup Methods," is the most important, providing means to calculate X/Q, calculate doses using actual monitor data and selected accident type, and to calculate doses using default accident releases. Other procedures in this series address:

  • Using Alternate Sources of Meteorological Data.
  • Determining Plume Width, Plume Height, and Transit Time.

. Dose Projection with Known Isotopic Release Rate or Known Isotopic Quantity.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

  • Dose Projection with Source Term Based on Field Measurements.
  • Estimation of Ingestion/Inhalation Dose Commitments.
  • Integrated Dose Assessment.

Liquid Release Hand Calculational Methods Procedure EPPJIP-2.7 and EPPAIP-2.7.1 provides a series of methods of assessing the radiological consequences of liquid releases to the Ohio River. The objective of these methods is to assess whether or not the release has exceeded the Emergency Action Levels listed in TAB 7 of the BVPS Classification Procedure. This method determines the liquid concentration and dose at the entrance of the Ohio River and whether or not the release will result in activity at the Midland Water Treatment Plant intake that exceeds EPA drinking water standards.

The procedure provides methods to address releases via normal monitored pathways and unmonitored releases.

.3 Technical Basis Summary The atmospheric dispersion and dose projection methodologies are based on recognized national and international standards. The primary documentation for each method describes the technical bases for each method in detail. The paragraphs that follow summarize some significant basis.

  • For the Class A models, the value of the atmospheric dispersion factor, X/Q, is based on the guidance of Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants." In the hand methods, all releases are treated as ground level releases. The MIDAS Class A model algorithm addresses ground level and elevated releases, plume rise, virtual source building wake correction, and other similar considerations. Plume direction is based on the 150' wind direction sensors due to terrain interference on the 35' sensors.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

  • The dose projection methodology is based on Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," and TID-21490, "Meteorology and Atomic Energy." The Class A models are based on semi-infinite submergence dose and on ICRP 30 intake models. The MIDAS Class B dose is based on the sum of three (3) components: finite cloud plume shine, whole body inhalation dose, and whole body ground shine dose.
  • Source term processing is performed with default source term mixes associated with the FSAR - analyzed accidents, or with input isotopic sample data. These source term mixes are used to normalize both the monitor efficiency and the dose conversion factors for energy-dependent variations. The MIDAS Class A and Class B model software decays the source term mixes for the period between plant shutdown and start of release, and applies decay corrections in route.

.4 Meteorological Considerations Because of the complex terrain surrounding the Beaver Valley Site, it is not always possible to accurately determine the plume trajectory from the site meteorological instrumentation alone. This situation creates uncertainty in the identification of the affected area. The ARERAS Class B model can more accurately predict plume transport as a digitized three-dimensional terrain map as an input database for the model. The technical sophistication of this model, the resulting complexity, and the required computer run-time makes it unlikely that the model results would be immediately available in a rapidly developing situation. As a result of these terrain impacts, it will be necessary to apply conservative compensatory factors to the observed site meteorological conditions.

A meteorological study performed in 1982 determined that there were three (3) meteorological regimes that characterized the dispersion meteorology at the BVPS site. The paragraphs below identify these three regimes, and the likely affect on plume transport.

A. Night-time conditions (G, F, E stability) with 500' wind speeds lower than 4.0 mph.

Under these conditions, the regional wind flows will create a valley floor flow that is de-coupled from the regional wind flow. Upriver of the site (towards Beaver) the valley wind flow is 6-19 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES towards the site. Downriver from the site, the wind flows are also towards the site. A heat island at the site of the J&L Specialty Steel plant creates a "chimney" effect that circulates these converging flows. If there is an inversion layer (as there is most likely), the upward chimney flow is recirculated back into the valley. This circulation will continue in the site area. If there is no inversion, the outlet flows from this chimney are injected into the regional wind flow.

Releases during these conditions will tend to "puddle" in the site area and will be generally contained within the valley walls.

Releases that break through the inversion layer (if there is one) would follow the 500' winds.

B. Night-time or day-time conditions with 500' wind speeds greater than 4.0 mph.

Under these conditions, the regional wind flow creates eddies as the flow breaks over the leading edge (wind passes this first) of the valley and as it strikes the opposite valley wall. However, due to the regional wind velocity, these eddies and swirls continue to circulate and mix with the regional wind flow. This creates a scrubbing action that flushes the valley. A similar scrubbing effect will occur if the regional wind direction aligns with the valley.

A release under these conditions will follow the 500' wind direction.

C. Day-time with 500' wind speeds lower than 4.0 mph.

Under these conditions, the regional wind flow creates eddies as described above. However, since the wind velocity is low, the scrubbing action is not as strong, and the regional wind flow will create a de-coupled flow in the valley. This valley flow will tend to flow downriver in the absence of any other forces (i.e., regional wind direction aligns with valley).

Releases during these conditions could result in two (2) plumes, depending on wind direction, or a plume that starts in one direction and then changes direction as it leaves the valley area.

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.5 Initiation and Performance of Dose Projection Functions In the event of a known or projected release of radioactive material, immediate and continuous assessment, including dose projection, is performed by on-duty shift personnel. Following activation of the Technical Support Center, dose projection activities are performed by the Environmental Assessment and Dose Projection Coordinator and assigned assistants at the TSC. Upon declaration of a Site Area or General Emergency, this function transfers to the Emergency Operations Facility (EOF). Responsibilities and functions assigned to these personnel are identified in Section 5 of this Plan. Activation of the emergency facilities is described in Section 6.2.3. The training of personnel assigned dose projection functions is identified in Section 8.

6.5.4 Field Radiological Monitoring Radiological monitoring following a release of radioactive materials to the environment is an intrinsic part of the Beaver Valley Power Site Emergency Preparedness Plan. Emergency radiological monitoring includes actions such as dose rate surveys, sampling and analysis of airborne and liquid activity, and collection and analysis of environmental media, both onsite and offsite. The extent and degree of radiological monitoring following a release of radioactive material will depend on the nature, the severity, the physical/chemical form, and the radioisotopic composition of the release.

Emergency Implementing Procedures provide guidance to the EA and DP Coordinator and monitoring team personnel in the performance of this radiological monitoring. These procedures identify criteria and guidelines, instrumentation to be used, monitoring team protective actions, communications protocol, data handling methods, and predesignated survey routes and survey points. Environmental monitoring procedures identify the location of environmental monitors, the use of the monitors, the sampling techniques and analysis methods to be used.

The Beaver Valley Power Station offsite monitoring teams may be supplemented or supplanted by monitoring teams from local, state, and Federal agencies. The Environmental Assessment and Dose Projection Coordinator will interface the activities of the BVPS offsite monitoring teams with the monitoring teams of the governmental agencies.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Initially in radioactive release situations, the Beaver Valley Power Station is in the best position to dispatch qualified monitoring personnel, and therefore has short-term responsibility of all offsite emergency radiological monitoring. However, following activation of the offsite emergency organizations and the deployment of governmental monitoring personnel, primary responsibility for offsite monitoring will revert to the state governments in the affected area. The state governments are assisted in this effort by personnel and equipment from the Federal Radiological Monitoring Assistance Program.

The types of emergency radiological monitoring performed and the methods for performing this monitoring are discussed below.

.1 In-Plant Radiological Surveys Procedures for performing radiological surveys and the use of survey equipment are incorporated in the Beaver Valley Power Station Health Physics Manual. The methods and techniques are essentially the same as those used for emergency surveys.

.2 Onsite Radiological Monitoring In the event of a radioactive release, one or more onsite radiation monitoring teams may be dispatched to assess radiological conditions onsite and at the site boundary in order to verify dose projection results and to determine the need for onsite protective actions.

Monitoring teams are normally comprised of one radcon technician and one other individual. Since there is a radcon technician on shift at all times, at least one monitoring team can be dispatched soon after the release has occurred, with additional teams dispatched using available personnel onsite or called-in personnel as they arrive onsite. Onsite monitoring teams maintain communications with the Control Room/OSC via portable radio transceivers. Survey equipment is provided for air sampling, direct radiation measurements, and for field-checking air sampling media. All sampling media is returned to the Site or to another designated location for laboratory analysis, as appropriate.

.3 Offsite Radiological Monitoring--Gaseous Release In the event that dose projection results or onsite monitoring results indicate the potential for radioactivity release to offsite areas, offsite radiation monitoring teams will be dispatched. Initially, at least one monitoring team will be sent in the direction of the plume movement.

6-22 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES The onsite monitoring team may be diverted from onsite monitoring to perform offsite monitoring. As additional radcon personnel assemble, additional monitoring teams will be deployed at the discretion of the Environmental Assessment and Dose Projection Coordinator.

Offsite monitoring team personnel take direct radiation readings with appropriate survey instruments and take air samples for analysis of airborne radioactivity. Air sample media are field-checked and significant results reported immediately to the EA and DP Coordinator. The field analysis provides for a minimum sensitivity for radioiodine detection of less than 1 x 10-7 uCi/cc, in the presence of radioactive noble gases. All monitoring results are recorded on data sheets by the monitoring teams and reported to the EA and DP Coordinator. Vehicles for monitoring teams are available on BVPS controlled property. Instructions for securing FMT vehicles are provided in the Implementing Procedures.

.4 Offsite Radiological Monitoring--Liquid Release In the event of a release of radioactivity to the Ohio River, a monitoring team is sent to the Midland Water Treatment Plant (closest treatment plant) to collect samples of drinking water. Installed environmental monitoring sample pumps routinely draw samples of drinking water for subsequent laboratory analysis. Upon arrival at the treatment plant, monitoring personnel will take the on-line sample for analysis and will collect additional samples as directed by the EA and DP Coordinator.

Sampling may be extended to downriver treatment plants if preliminary sampling results at Midland indicates the need. Vehicles for monitoring teams are available on BVPS controlled property. Instructions for securing FMT vehicles are provided in the Implementing Procedures.

.5 Emergency Environmental Monitoring The Beaver Valley Power Station has made provisions for required post-accident environmental monitoring. Additional samples may be taken, or samples may be taken ahead of schedule, if deemed warranted by the Environmental Assessment and Dose Projection Coordinator. Qualified personnel perform all environmental sampling and analysis. c3 6.6 CORRECTIVE ACTIONS Detailed Operating Procedures, Abnormal Operating Procedures, and Emergency Operating Procedures are utilized by the site operating personnel to assist them in recognizing emergency events and taking the corrective actions necessary to place the plant in a safe condition. Additionally, Emergency Implementing Procedures, as listed in Appendix C, describe subsequent and supplemental corrective actions for the scope 6-23 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES of potential situations within each of the emergency classifications. These procedures are designed to provide general guidance to personnel for correcting or mitigating the condition as early and as near to the source of the problem as feasible. Actions are specified, for example, which may prevent or significantly reduce a potential release of radioactive material, provide for prompt fire control, and ensure timely damage control and repair. The Emergency Implementing Procedures are also utilized in emergency training and are the basis for periodic emergency drills, and emergency equipment operational checks.

6.7 PROTECTIVE ACTIONS Protective actions are implemented to prevent or mitigate consequences to individuals during or after a radiological incident. Protective actions within the Beaver Valley Power Station site boundary, in response to an emergency originating at BVPS, are the responsibility of the BVPS Emergency Director. However, such protective actions may require coordination with other onsite organizations or the unaffected BVPS Unit, and may include assistance by offsite organizations. Protective actions outside the Beaver Valley Power Station site boundary are primarily the responsibility of state and local emergency organizations, but may require coordination of activities, dissemination of appropriate data, and recommendations by the BVPS Emergency Director.

6.7.1 Onsite Protective Actions

.1 Evacuations The primary protective measure for onsite personnel in an emergency is prompt evacuation from areas, which may be affected by significant radiation, contamination or airborne radioactivity.

Significant aspects of the various classes of evacuations are described in sections 6.7.1.2 through 6.7.1.4. General provisions applicable to all evacuations are:

In addition to the normal site complement, there are often visitors, construction workers, and nonconstruction contractors and vendors onsite. These construction personnel and contractors receive training, which addresses their responsibilities during an evacuation, prior to being issued a site badge. All other persons onsite, other than FENOC personnel assigned to BVPS, will be treated as visitors during evacuations. As such, these visitors will follow all instructions provided with regard to evacuations in site paging system announcements.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Protective Action Guides (PAGs) for evacuations are provided in the Emergency Implementing Procedures. Although the primary reason for evacuation is likely to be a radiological condition, evacuations may be indicated for other conditions, which create habitability problems, such as toxic gases, and/or fire. Appropriate PAGs are provided for these hazards in the Emergency Implementing Procedures.

.2 Local Evacuation This category refers to evacuation of localized areas within the site.

Evacuation of personnel from localized areas is initiated primarily by local area radiation monitors (ARM) and/or continuous air monitors (CAM).

The alarm setpoints are based on normal levels of radiation and airborne radioactivity and expected fluctuations within the specific areas. The immediate response by individuals in the vicinity of such an alarm is evacuation to an unaffected area, possibly within the same building, but away from the localized condition, and reporting the situation to the appropriate Control Room. In the absence of readily available radiological surveillance information or other logical assessment of conditions, those individuals will evacuate at least to a point where other radiological monitors show that the area is unaffected. Applicable instructions to personnel, based on evaluation of Control Room instrumentation or other supporting information, may be transmitted over the site paging system.

Strategic location of the radiological monitors and the requirement for immediate evacuation in response to alarms from these monitors provides reasonable assurance that radiological consequences of a localized incident will be minimized. Frequent radiological surveys throughout the site provide continuing verification of levels and trends indicated by these monitors. These surveys, as well as any other detection methods, can also serve to initiate the evacuation of personnel for conditions, which may not otherwise be identified by these monitors.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

.3 Site Assembly The declaration of a Site Assembly (as ordered by the Emergency Director/Shift Manager until properly relieved) requires all non-emergency response personnel to assemble at Primary or Near-Site Assembly Areas.

Personnel within the protected area shall report to their designated Primary Assembly Area. These Primary Assembly Areas are identified below:

  • BV-1 Service Building - Locker Room
  • SOSB - 3rd Floor - Locker Room C28
  • Nuclear Construction Office and Shops (NCOS) 2nd Floor
  • NCOS - 3rd Floor Personnel located outside the protected area but within the owner controlled property shall report to their designated Near-Site Assembly Area. These areas are listed below: C25 C28 C30
  • Training Building C19
  • Warehouse B The actual decision to implement a Site Assembly is the responsibility of the BVPS Emergency Director. This decision is based largely on his evaluation and judgment of the magnitude and severity of the particular situation. Factors to be considered must include the apparent levels of radiation and/or airborne radioactivity involved, the exposure to personnel that would result from evacuating as well as not evacuating to the Primary Assembly Areas. In the event of a multiple alarms (fire, ARMs, or CAMs) within the Controlled Area, the BVPS Emergency Director may deem it prudent not to evacuate personnel outside of the Controlled Area but within the Site's protected area fence, and allow work to continue if these personnel are not at risk.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

.4 Site Evacuation Site Evacuation requires that all individuals within the BVPS exclusion area, except for Control Room operations personnel and others, with specific emergency assignments, evacuate and proceed to the designated Remote Assembly Area, located upwind of the release or other designated area. This Site Evacuation includes all non-essential persons on site, and any other persons within the exclusion area. The Remote Assembly Areas for BVPS personnel are located at:

  • The Hookstown Grange
  • Western Power Delivery Division, Raccoon Headquarters Implementation of a Site Evacuation is the responsibility of the BVPS Emergency Director. That decision is based on the severity of the incident, the likelihood of escalation, and the radiation and airborne radioactivity levels throughout the site, particularly (but not exclusively) at the Primary Assembly Area. Primary Assembly Area dose rates and airborne radioactivity concentrations are determined by radiation control personnel using portable survey instruments and air sample collection devices and/or readings from fixed radiological monitors.

Notification of a Site Evacuation is made via the site paging system, consisting of evacuation alarm signal and message announcement.

.5 Personnel Accountability To ensure that all Site personnel present in affected areas have been evacuated and to ascertain the whereabouts of all emergency personnel who have not evacuated, measures have been established to provide for personnel accountability in the event of an evacuation. Accountability of evacuated and nonevacuated personnel (emergency workers) will be performed in accordance with the detailed Emergency Implementing Procedures. All individuals within the protected areas of BVPS are issued a security keycard badge. These security badges form the basis of the accountability process.

In the event of a local assembly near-by supervision shall ensure that all personnel have evacuated the affected area.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES In the event Accountability is declared, personnel accountability will be accomplished through the use of the computerized access security system (key-card). This system has provisions for identifying and printing a listing of all personnel in selected areas of the site. Site personnel update their whereabouts in the computer by inserting their security badge/key-card in the readers adjacent to the security doors leading to these areas.

The results from the assembly areas, and from personnel performing emergency response functions who can not report to an assembly area but are listed on a Site Accountability Form are reported to the Security Coordinator (on-duty Security Supervisor, until relieved by designated Security Coordinator), who provides a tabulation of missing individuals to the Emergency Director. If necessary, search and rescue efforts will commence in accordance with Emergency Implementing Procedures. The initial accountability phase shall be completed within thirty (30) minutes.

Unaccounted for personnel are reported to the Emergency Director who shall take the necessary steps to initiate Search and Rescue.

.6 Contamination Control The Beaver Valley Power Station Health Physics Manual (HPM) contains provisions governing the control of contamination including access control, use of protective clothing, contamination monitoring, and the release of potentially contaminated items from controlled areas. Chapter 3 of the HPM contains procedures that implement the 1PM provisions. The requirements and guidelines of these documents shall apply to contamination control during emergency conditions. Emergency Implementing Procedures provide the interface between the HPM and the Emergency Preparedness Plan. These procedures authorize the Radiological Controls Coordinator to waive or modify certain normal contamination control methods, if other conditions, such as delaying necessary evacuations, personnel rescue, or delaying access to necessary plant equipment would create a greater hazard to plant personnel or the general population.

There are no potentially affected agricultural products within the Beaver Valley Power Station exclusion area. The Ohio River, which flows within the exclusion area, however, is a navigable river and is the source of water for several downstream communities and industrial facilities.

6-28 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Domestic water at the Beaver Valley Power Station is provided by the Midland Water System. It's distributed by the domestic water system, which is a closed system. As a result of this configuration, contamination of the drinking water is unlikely. The Midland Water System storage tank has sufficient capacity to meet short-term needs.

With the exception of food brought to the site by Site personnel, all food supplied to the site arrives sealed for vending machine sale. These machines are located in noncontrolled areas. If these areas become contaminated they will be considered as controlled areas, and eating will be prohibited as is normally the case for controlled areas. Normal controlled area access controls will prevent the removal of contaminated food from these controlled areas and possible ingestion by unwary individuals.

Contamination monitoring will be performed as specified in the HPM.

During Site Evacuations, personnel and vehicle contamination surveys are performed at a location on the site exit road. Contaminated personnel will be returned to the Site, for decontamination. In the event that the Site Evacuation must be made immediately, the survey process will result in undue delay in evacuating site personnel, personnel will be directed to proceed, with personal automobiles, to the designated remote assembly area. Personnel monitoring will be performed at the location.

Decontamination of materials and equipment are performed in areas provided for that purpose within the Beaver Valley Power Station. The Liquid Waste System, described in the BVPS Operating Manual, provides the capability to store and process decontamination wastes. The handling of solid radioactive waste is also described in the Operating Manual and Health Physics Manual.

Personnel decontamination is described in Section 6.8.1.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

.7 Exposure Control The exposure of Site personnel during emergency operations shall be maintained as low as reasonably achievable, and should be maintained less than the administrative guides established in the BVPS Health Physics Manual (HPM) and/or less than the Federal Radiation exposure standards established in 10 CFR 20. In order to accomplish this objective, administrative means used during normal operations to minimize personnel exposure (such as radiation work permits and ALARA measures) should remain in effect to the extent consistent with timely implementation of emergency measures.

If necessary operations require personnel exposures in excess of the normal control limits, or if normal access control and radiological work practices will result in unacceptable delays, the Radiological Controls Coordinator may, at his discretion, waive or modify the established exposure control criteria and methods. The Emergency Director is the only individual who may authorize dose extensions in excess of 10CFR20.

Table 6.3 summarizes the emergency exposure criteria for entry or re-entry into areas for the purposes of undertaking protective or corrective actions.

Two classifications of emergency exposure are identified: corrective actions, and lifesaving actions. Lifesaving actions include actions such as rescue, first aid, personnel decontamination, medical transport, and medical treatment services, when such actions are immediately necessary to save a life. Corrective actions include surveillance actions and plant operations necessary to minimize further deterioration of the level of plant safety or to mitigate the consequences of the accident, if failure to perform these actions could result in a significant increase in offsite exposures.

Personnel exposures received performing emergency measures, other than those identified above, shall be limited pursuant to 10 CFR 20.

Dosimetry monitoring equipment is provided at the Site as part of the normal Radiation Control Program, and such dosimetry will continue to be used during emergency situations. Health Physics Procedures provide guidelines and procedures for issuing, using, and reading dosimetry devices and provisions for exposure record keeping.

6-30 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES The Beaver Valley Power Station Health Physics Manual contains provisions for administration of the facility bioassay program. Emergency Implementing Procedures provide guidance for accelerated or additional bioassays in the event there are individuals who are suspected of being exposed to elevated levels of airborne activity as a result of the emergency.

This bioassay consists primarily of lung and thyroid counts. These are supplemented by whole body counts and urinalysis when pre-determined lung and thyroid count screening levels, or pre-determined airborne activity exposure levels, are exceeded or suspect of being exceeded. These procedures provide for follow-up monitoring, medical treatment, and incident reporting.

.8 Respiratory Protection The Beaver Valley Power Station Health Physics Manual (HPM) contains provisions governing the use of respiratory protection equipment and administration of the BVPS Respiratory Protection Program, which is responsive to Regulatory Guide 8.15 and NUREG-0041. The provisions of this document and supporting procedures shall apply to all usage of respiratory protection equipment during emergency conditions.

Three exceptions to normal respiratory protection practices may be authorized by the Emergency Director with the advice of the Radiological Controls Coordinator, in accordance with the provisions of Emergency Implementing Procedures. These exceptions are:

  • Extension of normal uptake limits. Under these provisions, internal exposure is controlled such that the total dose commitment--due to internal and external exposure, does not exceed the emergency exposure limits established in Table 6.3.
  • Use of Thyroid Prophylaxis. Potassium iodide is available for use by BVPS employees and contractors in the event of an emergency. This potassium iodide is only specified for use by emergency workers who must remain in affected areas, and for whom other means of respiratory protection are not available or are not practicable.

Normally, potassium iodide will not be issued unless I-131 airborne activity in occupied areas would result in a thyroid CDE in excess of 25 REM. The use of thyroid prophylaxis by Site personnel is voluntary. Potassium iodide shall not be administered to non-emergency workers or to members of the general public by BVPS personnel, and is issued only at the direction of the Emergency Director.

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. Use of Iodine Sorbent Canisters in Filter Respirators. During emergencies, iodine sorbent canisters may be used in filter respirators.

If this is the case, the Radiological Controls Coordinator may recommend that BVPS petition the NRC for permission to assign protection factors for iodine sorbent canisters as specified in IOCFR20.

6.7.2 Offsite Protective Actions The Nuclear Regulatory Commission has postulated (that in the event of a severe accident) protective actions may be necessary in a ten (10) mile radius Emergency Planning Zone (EPZ) around the Beaver Valley Power Station in order to minimize the exposure of the population to radioactive material in the plume.

Under these conditions, it may also be necessary to monitor and control foodstocks and wildlife in a fifty (50) mile radius Ingestion Pathway Emergency Planning Zone. Both of these zones encompass areas with Pennsylvania, Ohio, and West Virginia. While there may be highly improbable accident sequences that would require extending these zones, the planning established for the ten (10) mile EPZ and the fifty (50) mile ingestion pathway planning zone provides an adequate basis for this expansion, should it be necessary.

To have the maximum effectiveness, the protective measures may require lead times before implementation, and with regard to evacuation, would require time to complete. Because of this, protective action decisions are based on the probability of a significant radioactivity-release, as well as the existence of a current release.

Under the worst postulated scenarios the time between event initiation and the occurrence of a significant release may be as little as thirty (30) minutes.

Although dose assessment methodologies are developed to a reasonable degree of accuracy, there are uncertainties involved with the input data to these assessments.

It is unlikely that the release source term will be adequately quantified when the first protective action decisions are being made during a rapidly developing situation. Similarly, the meteorological conditions at the site may not be consistent with those a few miles from the site. These uncertainties, coupled with the need for rapid decisions in a fast breaking incident, and the significant lead time necessary to implement a protective action, has resulted in greater emphasis being placed on plant systems status assessments against pre-determined criteria, and lesser emphasis on dose assessments.

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Section 6 Emergency Preparedness Plan EMERGENCY MEASURES While it is appropriate that any protective action decision be discussed in conjunction with the three States and with the NRC, and while BVPS shall make reasonable efforts with these agencies to arrive at a common recommendation, in the absence of such an agreement the BVPS recommendation shall be based on the staff's best evaluation of the technical considerations involved, be the plant condition or dose assessment related, and will include only those geographical areas projected to be affected by the plume transport.

The state and local governments within the EPZ have developed emergency response plans for the protection of the general public in their jurisdictions. The role of the Beaver Valley Power Station in offsite protective actions is the notification of cognizant officials, performing accident assessments and apprising the offsite agencies, and making recommendations for offsite protective actions.

The role of the local and state governments is to act upon the information and recommendations provided by the facility and to perform emergency measures necessary for the protection of the public.

The emergency preparedness plans of these jurisdictions are prepared and submitted to the Federal Emergency Management Agency and the Nuclear Regulatory Commission for review and approval. These documents should be consulted for detailed information on offsite protective actions. The following sections summarize the provisions for offsite protective actions in the BVPS EPZ.

.1 Protective Actions Within Beaver County, Pennsylvania. The responsibility for actions to protect offsite individuals rests with Beaver County government as described in the Beaver County Plan. The Beaver County Emergency Management Agency (BCEMA) is responsible for implementation of that plan.

The Pennsylvania Department of Environmental Protection/Bureau of Radiation Protection (DEPIBRP) is responsible for evaluating information obtained from the Beaver Valley Power Station and/or other sources and recommending appropriate offsite protective actions to BCEMA through the Pennsylvania Emergency Management Agency (PEMA). Such recommendations, based on all available data, local constrains and other considerations may include:

  • Shelter for affected populations
  • Evacuation within a-specified radial distance and/or downwind sector 6-33 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

  • Administration of thyroid prophylaxis (as approved by the State)
  • Control of contaminated agricultural products The principal offsite local coordinating agency for providing response to radiological emergencies in the vicinity of the Beaver Valley Power Station is the Beaver County Emergency Management Agency (BCEMA).

Since the area and population inside the ten (10) mile emergency planning zone are partially within Columbiana County, Ohio and Hancock County, WVA; essentially parallel emergency response functions are provided by the coordinating agencies within those Counties. The implementation of protective actions within these areas are discussed in Sections 6.7.2.2 and 6.7.2.3. Upon notification by Beaver Valley Power Station or by PEMA of a situation, which may require protective actions for offsite populations, BCEMA will activate its emergency organization, and if required, will initiate appropriate actions in accordance with specific instructions from PEMA and the BCEMA emergency plans and procedures. If communication cannot be established with PEMA in the necessary time frame, BCEMA may implement limited protective actions with the concurrence of the County Commissioners on the basis of recommendations made by the BVPS Emergency Director (Emergency/Recovery Manager when EOF is activated).

  • Providing assistance for evacuation of the County's population within the ten (10) mile emergency planning zone
  • Identifying reception and mass care centers for individuals evacuated from Beaver County Occupants within the ten (10) mile emergency planning zone of the Beaver Valley Power Station will be provided with information regarding emergency planning. This information will describe the method(s) by which they will be notified of an emergency and will provide specific instructions to follow upon receiving such notification. Additional discussion of the content and method of distribution of this information is contained in Section 8.

A detailed study has been conducted of the status and capacities of roads, traffic patterns, and demography within the ten (10) mile emergency planning zone. This study includes the estimated times to evacuate all or specific segments of the population, identifies potential problem areas 6-34 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES and provides contingencies for dealing with adverse conditions. This study was utilized in the development of detailed evacuation plans by BCEMA, CCEMA, and HCOES. A summary of this study is presented in Appendix B.

The Ohio River, which flows within the exclusion area, is the source of water to communities and industrial facilities downstream. The closest water treatment facilities are at Midland, PA and East Liverpool, OH; less than 1 mile and approximately 5 miles down-stream, respectively.

Additional water supply intakes are located 7 or more miles downstream.

The minimum average flow in the river (Sept.) is approximately 5 million gallons per minute. In the event of an actual or projected release of radioactive material to the river, by any pathway, the Midland and East Liverpool water treatment companies may be notified and a recommendation made to secure water processing depending on the estimated or calculated river activity. If a water treatment plant is shutdown as a result of a recommendation by the BVPS Emergency Director, or by request of DEP/BRP (in the case of Midland), the decision to allow restarting those water treatment plants is the authority and responsibility of governmental agencies responsible for water purity in each of the three jurisdictions.

The Ohio River is navigable, and is routinely used for barge traffic. In the event of an emergency condition requiring protective actions within the BVPS exclusion area, the U.S. Coast Guard will be notified and requested to restrict vessels from entering affected areas. In addition, lockmasters at the New Cumberland Dam, located approximately 20 miles downstream; the Montgomery Dam, located approximately 3.3 miles upstream; and/or the Danshield Dam, located approximately 11.3 miles upstream; can be called upon to restrict access to affected areas on the river.

BCEMA has the capability and detailed plans for implementing protective actions in Beaver County, which include:

  • Implementing prompt notification of the County's population within 10 miles of the Beaver Valley Power Station

. Transmitting specific instructions to the potentially affected populations 6-35 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES

.2 Protective Actions Within Columbiana County, Ohio The responsibility for actions to protect offsite individuals rests with the State of Ohio, as described in the State of Ohio Plan for Response to Radiation Emergencies at Licensed Nuclear Facilities. The Ohio EMA is responsible for implementation of that plan.

The State Department of Health is responsible for evaluating information obtained from the Beaver Valley Power Station and/or other sources and recommending appropriate offsite protective action to the Governor through Ohio EMA. Such recommendations, based on all available data, local constraints and other considerations may include:

  • Shelter for affected populations
  • Evacuation within a specified radial distance and/or downwind sector
  • Administration of thyroid prophylaxis (for emergency workers only)
  • Control for contaminated agricultural products The principal offsite local coordinating agency for providing response to radiological emergencies in Columbiana County is the Columbiana County EMA. Upon notification by the BVPS Emergency Director or by BCEMA or by OEMA of a situation, which may require protective actions for offsite populations, CCEMA will initiate appropriate actions in accordance with specific instructions from the notifying party, and within the guidelines of the CCEMA emergency plans. If time permits, CCEMA will obtain a review and verification by OEMA of recommendations made by the BVPS Emergency Director. CCEMA has the capability and detailed plans for implementing protective actions similar to those for BCEMA described in Section 6.7.2.1 of this Plan.

.3 Protective Actions Within Hancock County, West Virginia The responsibility for coordination of protective action recommendations rests with the State of West Virginia, as described in the West Virginia Emergency Disaster Plan, Volume Four, Response/Radiological Beaver Valley Power Station. The West Virginia Office of Emergency Services (WVOES) is responsible for implementation of that plan.

6-36 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES The West Virginia Bureau For Public Health is responsible for evaluating information obtained from the Beaver Valley Power Station and/or other sources and recommending appropriate offsite protective actions to WVOES. Such recommendations, based on all available data, local constraints and other considerations may include:

  • Shelter for affected populations
  • Evacuation within a specified radial distance and/or downwind sector
  • Administration of thyroid prophylaxis (for emergency workers only)
  • Control of contaminated agricultural products The principal offsite local coordinating agency for providing response to radiological emergencies in Hancock County is the Hancock County Office of Emergency Services. Upon notification by BVPS or by BCEMA or by WVOES of a situation, which may require protective actions for offsite populations, HCOES will initiate appropriate actions in accordance with specific instructions from the notifying party, and within the guidelines of the HCOES emergency plans. If time permits, HCOES will obtain a review and verification by WVOES of recommendations made by the BVPS Emergency Director. HCOES has the capability and detailed plans for implementing protective actions similar to those for BCEMA as described in Section 6.7.2.1 of this Plan.

.4 Public Warning System The primary means for alerting and warning the population of an incident at the Beaver Valley Power Station is the Siren Warning System. C This system involves alerting the population with sirens. In accordance with instructions provided by periodic public information programs (See Section 8.5), the alerted population will turn to Local Emergency Broadcasting radio or television stations for emergency information and instructions. Hardware has been provided for this public warning system within the plume exposure pathway EPZ. The design objective of this system is to have the capability to complete an initial notification of the public within the plume exposure pathway EPZ within about 15 minutes.

6-37 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES The hardware consists of fixed outdoor sirens located within the 10 mile EPZ.. The sirens will be activated remotely by radio from the emergency services office within the respective jurisdictions. 29 The responsibility for activation of the public warning system rests with the emergency services organization in each of the three risk counties.

These organizations will activate their respective portions of the warning system and supply appropriate emergency messages to the Emergency Alert System (EAS) station serving their jurisdiction in accordance with the provisions of their emergency response plans. The control for these systems are located in the respective county emergency services offices.

The Beaver Valley Power Station supplies information for these emergency messages in the form of the initial and follow-up notifications described in Section 6.4.1 and 6.4.2.

As a backup to the Siren Warning System, local fire and police personnel would perform house to house checks to ensure everyone has received the message. This Route Alerting System is described in Local and County Emergency Plans.

.5 Protective Action Guides and Recommendation of Protective Actions A protective action guide is the projected radiological dose, or dose commitment, to individuals in the general public above which protective actions may be warranted following a significant release of radioactive material. Protective Action Guides (PAGs) have been established by the U.S. Environmental Protection Agency. These guides are specified for the population as a whole. The guides for dose commitment for the general public are:

General Public Protective Action Guides Child TEDE Thyroid (CDE)

(rem) (rem) 1 5 6-38 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES As noted earlier, these guides are applied against projections of offsite dose, be they based on an ongoing release or a potential release. The plant system status indicators and the protective actions associated with each indicator, as provided in EPPAIP 4.1, "Offsite Protective Action," are based on the postulated offsite exposures associated with each condition and the protective action guides above.

  • Protective actions such a sheltering or evacuation are mandatory in affected areas if projected offsite doses exceed the value of the protective action guide established above.

- Sheltering is an appropriate protective action for:

Severe events in which evacuation cannot be implemented because of inadequate lead time due to rapid passage of the plume ("puff" release). Evacuation time estimates indicate that 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> are necessary to evacuate out to a five mile radius, and 3-1/2 to 4-1/2 hours out to 10 miles.

When an evacuation is indicated, but local constraints, such as inclement weather, road conditions, etc., dictate that directing the public to seek shelter is a more feasible and effective protective measure than evacuation. Studies indicate that a normal wood structure that can be made reasonably snug can reduce the direct exposure to the plume by 10% and can minimize inhalation dose for about two-hours.

  • Evacuation is an appropriate protective action for:

An incident involving a release, or potential release, which is projected to result in an offsite dose greater than 1 rem TEDE, or 5 rem to the child thyroid (CDE), in situations where the lead time between declaration of the emergency and population relocation is compatible with plume movement, and in the absence of constraints to evacuation (inclement weather, etc.).

  • Situations which do not provide for advance warnings, but for which substantial reductions in population dose can be made by avoiding exposure to residual radioactivity (plume fallout) in the wake of sudden severe incidents involving significant releases of radioiodine or particulate material. In these cases, sheltering should be maintained until the plume passes, if possible.

6-39 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Offsite agencies responsible for implementing protective actions for the public will assign protective actions based on their evaluations and consideration of the BVPS recommendation. While the agencies in the three (3) jurisdictions will coordinate their respective actions with each other, the action taken in each jurisdiction is ultimately the prerogative of that jurisdiction.

The role of BVPS in offsite protective actions is to provide offsite agencies with timely notifications of emergencies, appropriate recommendations for protective actions, appropriate accident assessment data, and data from offsite monitoring performed by BVPS personnel in the event of a release; to provide a capability for warning the public in a timely manner; and to assist local officials with public information programs.

6.8 AID TO AFFECTED PERSONNEL Established Emergency Plan Implementing Procedures, Operating Procedures, and Radiation Control Procedures provide for personnel decontamination and for assistance to injured persons including situations involving complications due to the presence of radiation or radioactive contamination.

6.8.1 Personnel Decontamination The Beaver Valley Power Station Health Physics Manual identifies criteria and provides procedures for personnel decontamination. The provisions of the HPM and supporting procedures shall apply to emergency situations to the maximum extent possible. These procedures commence with simple washing with soap and water by the individual. If contamination is persistent, or involves significant amounts of contamination, particularly in the vicinity of facial openings, decontamination will be performed under the direction of radiation control personnel using established procedures.

Personnel decontamination areas, consisting of showers and sinks, which drain to the Liquid Radwaste System, are available within the Site for routine or emergency use. These facilities are located near the access to the controlled areas of the Site. Portable decontamination kits are maintained for use at remote assembly areas.

A listing of typical decontamination equipment located at the personnel decontamination areas is provided in Appendix D. Personnel having their personal clothing contaminated will be issued clean clothing as temporary replacement clothing.

6-40 4Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES In addition to decontamination within the Site, the Emergency Response Facility will provide a decontamination facility. Decontamination liquids are held-up in tanks for subsequent processing. In the interim, personnel decontamination will be performed prior to the departure from the Site, or at a designated location.

Normal contamination control limits expressed in the HPM shall remain in effect to the extent possible. However, the Radiation Control Coordinator, may modify the contamination control limits as provided in Emergency Implementing Procedures. Under site evacuation conditions, the level of removable contamination above which removable decontamination is mandatory is established as 5000 dpm/100 cm (500 cpm on HP210 detector), five times the normal control limit. No contamination limit applies to contaminated injured personnel needing immediate medical treatment at a hospital.

6.8.2 First Aid At least two persons who are qualified in first aid methods shall be onsite at all times. The qualified individuals are trained in First Aid/CPR. First aid to injured personnel can normally be performed in conjunction with any necessary decontamination methods. However, if immediate treatment of the injury is vital, that treatment shall take precedence over decontamination. This philosophy also extends to offsite emergency medical assistance involving radioactive contamination. For that purpose, measures are established in the Operations and Health Manuals to ensure timely offsite medical treatment. First Aid Kits are available for use at several locations within the Site, and a medical facility is available.

6.8.3 Medical Transportation Arrangements have been made for the transportation of injured personnel from the Beaver Valley Power Station, who may have injuries complicated with radioactive contamination or who may have been involved in a radiation incident, to a medical treatment facility. These organizations can be contacted directly or through the Beaver County Emergency Services Center.

Emergency Medical Services radio provides for communications between the Beaver County Emergency Services Center, the ambulances, and the Beaver County hospitals. Copies of the agreement(s) to provide emergency services from these organizations are on file in the Emergency Preparedness Section.

Ambulance emergency supply kits, which typically contain items shown in Appendix D, are available for use and are stored in the Medical Facility at the Site.

6-41 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES Ambulance personnel arriving at the Site are directed by security personnel to the appropriate area. Personnel dosimetry for ambulance personnel is provided by the Site. Contaminated patients are accompanied by radiation control personnel. The radiation control person is responsible for maintaining appropriate contamination control measures to minimize the contamination of the ambulance, the hospital, and hospital personnel. This individual is responsible for controlling contaminated material, and surveying the ambulance and the hospital treatment area following use.

If an ambulance can not be obtained in a reasonable period of time, a suitable BVPS vehicle, or employee vehicle (only on a voluntary basis), may be utilized to transport injured personnel.

6.8.4 Medical Treatment Arrangements have been made for treatment of injured personnel from the Beaver Valley Power Station, who may have injuries complicated with radioactive contamination at:

  • The Medical Center, Beaver, PA Similar arrangements have been made for medical treatment of contamination injuries and significant over-exposures to radiation, and for evaluation of radioactive material uptakes at:
  • Presbyterian-University Hospital Evaluation of significant contamination injuries, over-exposures, and radioactive materials uptakes can be made by the Radiation Protection Department at BVPS. CM The BVPS Health Services maintains a contract for a qualified physician. This physician has or will complete training through REAC/TS at Oak Ridge, TN, and can assist with clinical diagnosis and/or treatment of contaminated/injured or irradiated persons.

Copies of agreements to provide medical treatment from the above organizations are on file in the Emergency Preparedness Section.

6-42 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES The Medical Center, and the Presbyterian-University Hospital are adequately supplied and equipped to receive and treat contaminated patients. Sets of contamination control supplies are provided at the Medical Center of Beaver County. A typical list of this equipment is shown in Appendix D.

6.9 EMERGENCY PUBLIC INFORMATION First Energy Nuclear Operating Company respects the public's right to information about its operations and service and, in particular, information regarding accidents and unplanned events which occur at Company facilities, including the Beaver Valley Power Station. The Company's policy has and continues to be to make public, accurate information about these events.

The Emergency Public Information procedures describe the objectives, responsibilities, facilities, and protocol for emergency public information. Section 7 of this Plan describes the Joint Public Information Center (JPIC). Section 6.2.4.6 describes activation of the Joint Public Information Center and the Emergency Public Information Response staff.

The Joint Public Information Center, if activated, is the location from which replies to news media inquiries will be made, and at which news briefings will be held. If the situation warrants, news briefings may be held at other locations. The Beaver Valley Power Station will supply operational and technical information, upon request, to JPIC personnel via the onsite Emergency Public Information Response staff at the ERF. This individual shall have access to all information regarding the emergency. Senior management designated individuals will serve as Chief Company Spokesperson. al Space is provided at the Joint Public Information Center for State, local, and Federal public information personnel, and provisions are made for coordination of news announcements and press briefings.

As part of the Emergency Public Information procedures, telephone contact personnel respond during an emergency to handle incoming calls from members of the general public. 0 ' In addition to other functions, these personnel will serve as the point of contact between the general public and BVPS. The purpose of this contact is to respond to concerns of the general public in an effort to suppress unfounded rumors and incorrect information which has not been answered by news announcements. In addition, the Emergency Public Information ERO provides an internal rumor control system to quell rumors to company employees and the news media.

6-43 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES INTENTIONALLY BLANK 6-44 Rev. 19

Section t)

(C Emergency Preparedness Plan EMERGENCY MEASURES TABLE 6.1

SUMMARY

OF IMMEDIATE NOTIFICATION AND RESPONSE IMMEDIATE NOTIFICATIONS IMMEDIATE ACTIONS EMERGENCY CLASS _ l O ONSITE PERSONNEL OFFSITE PERSONNEL l________ CRITERIA __ONSITE jOFFSITE __________ _________

Off-normal Events Which By

  • Fire Brigade
  • Fire Units
  • Make Prompt Offsite
  • Provide Fire Fighting Themselves Do Not Constitute
  • Damage Control Teams
  • Rescue Assistance Notification Assistance Significant Events. But Could Indicate a
  • Surveillance Watches
  • Ambulance Assistance
  • Fight fires
  • Assist in rescue operations Potential Degradation in the Level of
  • First Aid Teams
  • Hospital
  • Perform emergency repairs
  • Provide Medical Safety of the Plant.
  • Rescue Teams
  • BCEMA
  • Designated Surveillance Transportation
  • Monitoring Teams
  • Provide Hospital Medical
  • Security Force
  • OEMA
  • Administer First Aid Treatment
  • Outage Contractors
  • HCOES
  • Conduct Rescue Operations
  • Assist in Damage Control UNUSUAL EVENT
  • CCEMA
  • Perform Onsite Monitoring
  • WVOES
  • Appropriate Security
  • NRC Measures
  • Perform Continuing Assessment
  • Make Prompt Onsite

. Notifications Events Which Indicate an Actual

  • Fire Brigade
  • Fire Units
  • Make Prompt Offsite
  • Provide Onsite Assist. as Degradation in the Level of Safety of the
  • Damage Control Teams
  • BCEMA Notifications required Plant
  • Monitoring Teams
  • Fight Fire
  • Activate Primary Response
  • Dose Projection Personnel
  • OEMA
  • Perform Emergency Repairs Centers
  • Security Force
  • HCOES
  • Onsite and Offsite Monitoring
  • Alert Key Personnel to ALERT
  • Outage Contractors
  • CCEMA
  • Offsite Dose Projection Standby
  • WVOES
  • Approp. Security Measures
  • Conduct Confirmatory Dose
  • NRC
  • Augment Onshift Resources Projections
  • Maintain Emergency Place EOF, JPIC on Communications.

standby 6-45 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES TABLE 6.1

SUMMARY

OF IMMEDIATE NOTIFICATION AND RESPONSE IMMEDIATE NOTIFICATIONS IMMEDIATE ACTIONS EMERGENCY CLASS SIONSITE _ PERSONNEL OFFSITE PERSONNEL

____________CRITERIA ONSITE OFFSITE __________

Events Which Involve Actual or Likely

  • Appro. Emer. Teams
  • Appropriate Local Assist.
  • Make Prompt Offsite
  • Provide Onsite Assistance Major Failures of Plant Functions
  • Security Force
  • BCEMA Notifications as required Needed for Protection of the Public
  • All other station Personnel
  • Take Appro. Corrective
  • Activate and Man Response
  • Outage Contractors
  • OEMA Action Centers
  • HCOES
  • Onsite and Offsite Monitoring
  • Mobilize Emer. Response
  • CCEMA
  • Offsite Dose Projections Personnel
  • WVOES *Appro. Security Measures
  • Continuously Evaluate Dose SITE AREA EMERGENCY
  • NRC *Augment Resources/Activate Projections
  • FENOC Headquarters Emergency Centers
  • Place Public Notification
  • Personnel Evacuation as System and Procedures in Approp. Standby Status
  • Alert Total Emergency Org.
  • Implement Appropriate
  • Perform Continuing Assess. Near-Site Emergency
  • Activate EOF, JPIC Protective Measures
  • Maintain Emergency Communications Events Which Involve Imminent
  • Appropriate Emer. Teams
  • Appro. Local Assistance
  • Make Prompt Offsite Notif.
  • Provide Onsite Assistance Substantial Core Degradation or Melting
  • Security Force
  • BCEMA Take Appro. Corrective as required With Potential for Loss of Containment
  • All Other Station Personnel
  • Fully Staff Response Centers Integrity
  • Outage Contractors
  • OEMA
  • Onsite and Offsite Monitoring
  • Activate all Emergency
  • HCOES
  • Appro. Security Measures Response Personnel GENERAL EMERGENCY
  • CCEMA *Augment Resources/Activate
  • Implement Public Notif.
  • WVOES Emergency Organization Procedures
  • NRC
  • Activate Total Emergency
  • Continuously Evaluate Dose
  • FENOC Headquarters Organization Projections
  • Personnel Evacuation as
  • Implement Appro. Offsite appropriate Emer. Protective Measures
  • Perform Continuing Assess.
  • Maintain Emergency
  • Recommend Offsite Action Communications 6-46 Rev. 19

(..

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES TABLE 6.2 NOTIFICATION MATRIX CONTACT COMMUNICATION 24-HOUR ORGANIZATION PRIMARY ALTERNATE PRIMARY ALTERNATE COVERAGE PURPOSE BCEMA DISPATCHER BCEMA COMMERCIAL BVPS RADIO YES ACTIVATE DIRECTOR TELEPHONE BCEMA SYSTEM PEMA DUTY BCEMA COMMERCIAL BVPS RADIO YES ACTIVATE PEMA DEP/BRP OFFICER TELEPHONE VIAW' VERIFICATION SYSTEM BCEMA CALL OEMA DUTY OHIO HWY COMMERCIAL BVPS RADIO YES ACTIVATE OFFICER PATROL TELEPHONE VIA C2 OEMA DISPATCHER SYSTEM CCEMA WVOES DISPATCHER HCOES COMMERCIAL BVPS RADIO YES ACTIVATE DISPATCHER TELEPHONE VIA C2 WVOES SYSTEM HCOES CCEMA DISPATCHER CCEMA COMMERCIAL BVPS RADIO YES ACTIVATE DIRECTOR TELEPHONE CCEMA SYSTEM HCOES DISPATCHER HCOES COMMERCIAL BVPS RADIO YES ACTIVATE DISPATCHER TELEPHONE HCOES SYSTEM_____

DUTY N/A NRC/ENS TELEPHONE YES ACTIVATE NRC OFFICER (RED PHONE) FEDERAL

RESPONSE

FIRE DEPTS BCEMA N/A COMMERCIAL BVPS RADIO YES FIRE DISPATCHER TELEPHONE ASSISTANCE SYSTEM AMBULANCES BCEMA AMBULANCE COMMERCIAL BVPS RADIO YES MEDICAL DISPATCHER COMPANY TELEPHONE TRANSPORTATION SYSTEM HOSPITALS EMERGENCY BCEMA COMMERCIAL BVPS RADIO YES MEDICAL ROOM DISPATCHER TELEPHONE TREATMENT SYSTEM 6-47 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES INTENTIONALLY BLANK 6-48 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES EMERGENCY EXPOSURE CRITERIA TABLE 6.3 Dose to workers performing emergency services should not exceed the following recommendations of the EPA Manual of Protective Action Guides and Protective actions for Nuclear Incidents (EPA 400-R-92-00 1).

Dose Limit (a) 1 Activity Condition (rem) l l 5 All 10 Protecting valuable property Lower dose not practicable 25 Life saving or protection of Lower Dose not practicable large populations

>25 Life saving or protection of Only on a voluntary basis to large populations persons fully aware of the risks involved (a) Sum of external effective dose equivalent and committed effective dose equivalent to nonpregnant adults from exposure and intake during an emergency situation. Workers performing services during emergencies should limit dose to the lens of the eye to three times the listed value and doses to any other organ (including skin and body extremities) to ten times the listed value. These limits apply to all doses from an incident, except those received in unrestricted areas as members of the public during the intermediate phase of the incident.

  • The BVPS Emergency Director must approve all planned emergency exposures. The Radiological Controls Coordinator should be consulted prior to authorizing the planned emergency exposure, if time permits.

. All reasonable measures must be taken to control contamination and internal exposure.

  • Persons performing emergency activities should be familiar with the consequences of the exposure.
  • Persons performing emergency activities under these provisions should be volunteers.
  • Personnel shall not enter any area where dose rates are unknown or unmeasurable with instruments and dosimetry immediately available.

6-49 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES INTENTIONALLY BLANK 6-50 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES FIG. 6.1 PRIMARY INITIAL NOTIFICATIONS 6-51 Rev. 19

Section 6 Emergency Preparedness Plan EMERGENCY MEASURES INTENTIONALLY BLANK 6-52 Rev. 19

Emergency Preparedness Plan A5.735A SECTION 7 EMERGENCY FACILITIES AND EQUIPMENT CONTROLLED BVPS UNIT 3 Rev. 19

Emergency Preparedness Plan Section 7 EMERGENCY FACILITIES AND EQUIPMENT Table of Contents Paee No.

7.0 EMERGENCY FACILITIES AND EQUIPMENT ....................................... 1 7.1 ONSITE EMERGENCY CENTERS ...........................  : . 1 7.1.1 Control Room ........................... 1 7.1.2 Operations Support Center .......................... 2 7.1.3 Emergency Response Facility ........................... 3

.1 Technical Support Center ................................ 3

.2 Emergency Operations Facility ............ ................... 4

.3 Dosimetry Laboratory ................................ 5

.4 Sample Preparation and Counting Facilities ............................... 5

.5 Nuclear Regulatory Commission .............. ................. 5

.6 Decontamination Facility ................................ 5

.7 Other ................................ 5 7.1.4 Joint Public Information Center (JPIC) ....................................... 6 7.2 EMERGENCY SUPPLIES ...................................... 6 7.3 COUNTY AND STATE EMERGENCY CENTERS .................................... . 7 7.3.1 County Emergency Centers ...................................... 7 7.3.2 State Emergency Operations Center ....................................... 7 7.4 ASSESSMENT FACILITIES ...................................... 8 7.4.1 Radiological Monitors ...................................... 8

.1 Radiation Monitoring System .9

.2 Portable Instrumentation .9

.3 Radiological Laboratory Equipment .9

.4 Environmental Monitors .10

.5 Accident Monitors .10 7-i Rev. 19

Emergency Preparedness Plan Section 7 EMERGENCY FACILITIES AND EQUIPMENT Table of Contents Page No.

7.4.2 Fire Detection Systems .10 7.4.3 Geophysical Phenomena Monitors .11

.1 Meteorology .11

.2 Seismic Equipment .12

.3 Hydrologic Data .................................. 13 7.4.4 Process Monitoring Equipment .13

.1 Safety Parameter Display System .14

.2 Inplant Process Computer and Bypassed & Inoperable Status Indication System .14

.3 The Plant Safety Monitoring System (PSMS) ............................. 14 7.4.5 Post Accident Sampling ............................................ 14 7.4.6 Emergency Response Data System (ERDS) ............................................ 15 7.5 PROTECTIVE FACILITIES ............................................ 15 7.5.1 Station Control Rooms ............................................ 15 7.5.2 Site Assembly Areas ............................................ 16

.1 Primary Assembly Areas .................... ........................ 16

.2 Unit 1/2 Contractor Personnel ............................................ 16

.3 Personnel Access Facility ............................................ 16

.4 Out-Buildings ............................................ 16 7.5.3 Remote Assembly Areas ............................................ 17 7-ii Rev. 19

Emergency Preparedness Plan Section 7 EMERGENCY FACILITIES AND EQUIPMENT Table of Contents Page No.

7.6 COMMUNICATIONS SYSTEMS ......................................... 17 7.6.1 Commercial Telephone System ......................................... 18 7.6.2 PAX System ......................................... 18 7.6.3 Hot Lines to DER/BRP and NRC Communications ............................... 19 7.6.4 Beaver Valley Power Station Industrial Radio ........................................ 20 7.6.5 Beaver Valley Emergency Response System ......................................... 22 7.6.6 Station Page Party Telephone System ......................... ................ 22 7.6.7 Personal Radio Pagers (Beepers) ......................................... 22 7.6.8 Station Emergency Alarm System ......................................... 22 7.7 ONSITE FIRST AID AND MEDICAL FACILITIES ........................................ 22 7.8 DAMAGE CONTROL EQUIPMENT ......................................... 23 7-iii Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.0 EMERGENCY FACILITIES AND EOUIPMENT Emergency facilities and equipment are provided at the Beaver Valley Power Station to ensure the capabilities for prompt, efficient assessment and control of situations over the entire spectrum of probable and postulated emergency conditions. The facilities and associated equipment, and their emergency functions, are described in this section.

7.1 ONSITE EMERGENCY CENTERS Onsite emergency facilities at the Beaver Valley Power Station are described in this section. The Technical Support Center and the Emergency Operations Facility are located in the Emergency Response Facility (ERF) located approximately 1200 feet from the Beaver Valley Power Station Control Rooms. The significant instrumentation and-communications available at each of the BVPS emergency facilities are listed in the Implementing Procedures.

7.1.1 Control Room The Control Room is the primary location for the assessment and coordination of corrective actions for essentially all emergency conditions. The Control Room is equipped with the readout and controls for all critical plant systems, the readout and assessment aids related to radiological and meteorological monitoring systems, and access to all station communications systems.

The Control Room is initially the primary location for accident management and emergency communications until the Technical Support Center is activated.

Located within the Control Room are telephone and radio communications equipment and emergency equipment and supplies necessary to support direction and coordination of emergency response activities.

The Control Room provides for the effective coordination of the following emergency response functions:

  • Plant assessment and coordination of corrective actions
  • Requesting initial call out of emergency response personnel
  • Perform notifications to offsite government agencies
  • Requesting offsite dose projections be initiated and directions provided for offsite monitoring until the TSC/EOF is activated 7-1 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT

  • Communicate with other onsite/offsite Emergency Operations Centers

. Serve as the central location for the receipt of data from radiological monitoring (until the TSC/EOF is activated) and other emergency teams

  • Provide direction to emergency coordinators

. Make recommendations to offsite agencies regarding protective and other actions (until relieved by TSC/EOF)

  • Provide administrative direction (until relieved by TSC/EOF) 7.1.2 Operations Support Center The Operations Support Center (OSC) provides for assembly of Operations support personnel for supplemental emergency team personnel. The location of the OSC is the Outage Central AreaC' 5 located above the BVPS Control Rooms.

This area has communications capability with the Control Room and the BVPS Site. Protective equipment for personnel assigned to the OSC is available in emergency cabinets in the OSC and at the Plant Health Physics Check Area, located adjacent to the access to the controlled area.

The OSC is equipped with the Radcon and Operations circuits, the site page party system and PAX/Commercial phone system capabilities.

The OSC is designated as a central location for coordinating the activities of radcon technicians for both BVPS units. Wall maps are provided for maintaining the status of radiological conditions within the Station.

If the nature of the emergency renders the OSC unusable due to radiological conditions, etc., OSC operations are co-located to the Alternate OSC.

The Alternate OSC is located in the Process Instrument and Rod Position Instrument Area below the Unit I Control Room. This area has the same shielding and ventilation features as the Control Room and the same communications capabilities as the OSC. The BV-1 remote shutdown panel is located in this area.C 15 7-2 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.1.3 Emergency Response Facility The Emergency Response Facility has been designed to satisfy the functional requirements of the Technical Support Center and the Emergency Operations Facility. The design of the building enhances the proper control and coordination of the principle emergency response activities without interfering with plant emergency operations. The facility provides for the following:

.1 Technical Support Center The TSC provides for engineering and management support during emergency situations and has the following features:

a) Reasonably close proximity of the Control Room b) Capability to display real-time plant status data An Inplant Process Computer performs data acquisition, trending, alarm reporting, logging, CRT displays, data storage and various human communication functions to provide for the monitoring of plant variables in the Control Room.

The Safety Parameter Display System (SPDS), provides a display of plant parameters from which the safety status of operations may be assessed. The SPDS will help operating personnel make quick assessments of plant safety status and improve the exchange of information between TSC, EOF and Control Room.

c) Dedicated communications links to Control Room and NRC A dedicated line system is provided between the Control Room and the TSC.c3' This system is powered by emergency power. A base station for the BVPS Industrial Radio System is also provided.

This base station has its own transmitter and antenna and can communicate (via the BVPS repeater) with all units. Emergency Telephone System (ETS) extension for contacting the NRC/ENS and HPN are available, as is PAX and Commercial system telephones.

d) As-built drawings are maintained within the building 7-3 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT e) Environmental Assessment and Dose Projection capability An environmental assessment and dose projection area, located in the EOF area, provides the capability to perform dose projection and offsite radiological assessment functions. A terminal to the meteorological computer provides 15-minute average print-outs of meteorological parameters. An Atmosphere Radiological Effluent Release Assessment System (ARERAS) computer system will provide data needed for determination of meteorological conditions in the vicinity of BVPS and capability to access and monitor actual or potential offsite consequences of a release during a radiological condition. NRC/HPN, BVPS radio transceiver, and extensions to the DEPIBRP hotlines are available.

.2 Emergency Operations Facility In the Emergency Response Facility, an Emergency Operations Facility is established for the Beaver Valley Power Station. Although separate, the EOF is located in the same building as the Technical Support Center (TSC). There is adequate desk space for 50 or more people, including desk space for State representatives. Telephones are provided. The nearsite EOF shares an environmental assessment and dose projection area with the Technical Support Center. When the EOF is activated, the EA&DP area becomes a part of the EOF. In the event this area is uninhabitable, the nearsite EOF may relocate with the TSC. In the event the ERF is uninhabitable, the nearsite EOF will relocate to the Alternate EOF which shares a building with the JPIC on Spring Run Road in Coraopolis, PA. The EOF will serve as the location from which the overall BVPS response will be directed and coordinated; and as a coordinating center for utility, Federal, State and local agencies. BVPS management personnel at this facility provide an interface with the Technical Support Center.

The Coraopolis facility provides adequate desk space for 12 individuals with overflow space for approximately 25 additional personnel. There are direct Commercial telephone lines, FAX units, PAX lines, and an operating console for the BVPS Industrial Radio System and an ERDS Terminal. The alternate EOF is located on Spring Run Road in Coraopolis, PA.

7^4 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT

.3 Dosimetry Laboratory A shielded dosimetry lab is provided with sufficient TLD availability to serve the needs of all Station personnel. Whole body counting facilities are located adjacent to the ERF.

.4 Sample Preparation and Counting Facilities Shielded sample preparation areas are provided. Counting equipment include a gamma spectrometry system.

.5 Nuclear Regulatory Commission Provisions have been made in the ERF to accommodate the complete NRC Site Team Organization. These provisions include desk space, communications capabilities and a conference room.

.6 Decontamination Facility A decontamination facility is provided. This facility is intended for the use of ERF personnel. (Reserve portable survey instruments will be maintained here.)

.7 Other

. Kitchen

  • Rest rooms and sleeping areas (for men and women)

. Medical Services

  • Security and reception areas
  • Records room Increased shielding is provided for the EOF and the dosimetry/sample laboratories. Ventilation will be such that intake air flow can be diverted through high efficiency particulate (HEPA) filters and if necessary, charcoal filters. An emergency diesel generator, with an approximate 180-hour fuel supply, is provided for back-up power. Important instrumentation and communications equipment are powered by UPS and battery. Appropriate communications from the ERF to the Control Room, Onsite Response Facilities, and offsite agency Emergency Operations Centers, are provided.

7-5 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.1.4 Joint Public Information Center (JPIC)

The Joint Public Information Center (JPIC) will serve as the focal point for all Nuclear Communications activities. All media communications by First Energy personnel, including press conferences, will be coordinated through the JPIC. The location of the JPIC is in the Airport Industrial Park, Spring Run Road, Coraopolis, PA. This facility provides working space for the press and for First Energy Communications personnel. A briefing area to seat 300 persons is available. Adequate parking for cars and trailers is available.

The Implementing Procedures provides for activation and operation of this facility. If the facility is unavailable due to radiological conditions, the activities of the JPIC will be transferred to the Corporate Headquarters.

7.2 EMERGENCY SUPPLIES Emergency supplies are located at onsite and offsite locations to provide a ready supply of equipment and material necessary to meet the short-term needs for performing emergency functions. The emergency supplies include portable communication equipment, protective equipment, monitoring equipment, and applicable procedures. Additional, and/or replacement equipment and materials are available at the Station, or can be readily obtained from offsite sources to support longer term emergency measures or the recovery effort. Appendix D provides a typical inventory by general category.

In addition, BVPS maintains an inventory of contamination control material at The Medical Center, Beaver for minimizing the spread of contamination while handling contaminated injured personnel.

The emergency kits are inspected and inventoried at least quarterly and after each use.

7-6 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.3 COUNTY AND STATE EMERGENCY CENTERS 7.3.1 County Emergency Centers The 10-mile emergency planning zone for the Beaver Valley Power Station includes areas and populations in Beaver County, PA; Columbiana County, OH; and Hancock County, WVA. Each of these county jurisdictions has Emergency Operations Centers, which meet or exceed the minimum Federal criteria for sufficient space, communications, warning systems, and self-sufficiency in supplies and accommodations. All three counties maintain employees to coordinate emergency planning and execution, and have made provision for 24-hour per day communications coverage.

Location of the county Emergency Operations Centers are:

- Beaver County Emergency Operations Center Beaver County Emergency Management Agency Beaver County Emergency Services Center 250 East End Avenue Beaver, Pennsylvania

  • Columbiana County Emergency Operations Center Columbiana County Emergency Management Agency 7301 Lisbon Canfield Road Lisbon, Ohio
  • Hancock County Emergencv Operations Center Hancock County Office of Emergency Services Hancock County Court House 102 Court Street New Cumberland, West Virginia 7.3.2 State Emergency Operations Center The 10-mile Emergency Planning Zone (EPZ) for the Beaver Valley Power Station includes areas and populations in Pennsylvania, Ohio, and West Virginia.

All of the states maintain full-time employees to coordinate emergency planning and execution, and have made provision for 24-hour per day communications coverage.

7-7 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT The Pennsylvania Emergency Operations Center is located at the PEMA headquarters in Harrisburg, PA. This center is equipped with a reliable communications system, which ties all area and county emergency operations centers with PEMA headquarters. During an emergency, the State will assemble at the State Emergency Operations Center to manage and support the emergency response activities.

The Ohio Emergency Operations Center is located at the Ohio Emergency Management Agency headquarters in Worthington, Ohio (near Columbus). This center is equipped with extensive communications capability, which ties all area and county emergency operations centers with the OEMA headquarters. During an emergency, representatives from designated State agencies will assemble at the State Emergency Operations Center to manage and support the emergency response activities.

The West Virginia Emergency Operations Center is located in the West Wing, main Capital Building, in Charleston, West Virginia. An integral Emergency Communications center provides communication support for the emergency response effort. Communications and warning links connect all area and county emergency operations centers with the State EOC. During an emergency, the State EOC is staffed by personnel from each of the major State departments and agencies.

7.4 ASSESSMENT FACILITIES The primary emergency assessment facility is the site Control Room. Supplementary and complimentary assessment functions are performed in the TSC. This section discusses the assessment facilities provided for both initial and continuing assessment of emergency conditions.

7.4.1 Radiological Monitors Radiological monitoring equipment has been provided at the Beaver Valley Power Station for the detection and assessment of emergency conditions. Radiological monitors include the process, effluent, and area radiation monitors included in the Radiation Monitoring System; portable radiation, contamination, and airborne activity sampling and measuring equipment; radiological laboratory equipment; radiological environmental monitors; and accident monitors. These monitors are summarized below. More detailed information is found in the BVPS Final Safety Analysis Report (FSAR), the BVPS Health Physics Manual, the BVPS Operating Manual, and Appendix D to this Plan.

7-8 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT

.1 Radiation Monitoring System/Digital Radiation Monitoring System - This onsite system, consisting of effluent monitors, continuous air monitors, area radiation monitors, and process monitors, contributes to personnel protection, equipment monitoring and accident assessment by measuring and recording radiation levels and concentrations of radioactive material at strategically selected locations throughout the station.

Each potential radioactivity release path has been provided with appropriate radiation monitors. These monitors, which provide for radioactivity detection and measurement during normal operations, are tabulated in Appendix D.

.2 Portable Instrumentation Portable radiological sampling and measuring equipment is provided as part of the Beaver Valley Power Station Radiation Controls Program, as established in the BVPS Health Physics Manual. Appropriate gamma survey instruments, contamination monitoring equipment, and air sampling equipment are reserved in emergency kits for emergency use.

With few exceptions, this equipment is battery operated. The reserved equipment is supplemented by the instruments provided for routine use.

Appendix D tabulates, by type, the instruments available. The selection of instruments and sampling media, and the methodology established in Emergency Implementing Procedures, provides for a minimum field detection capability of at least 1 E-7 uCi/cc of Iodine-131 in the presence of radioactive noble gases.

.3 Radiological Laboratory Equipment Appropriate radiological counting equipment is provided in support of routine operations. This equipment is available for use during emergencies. Equipment includes, beta counter, liquid scintillation counters, and gamma spectrometers.

Laboratory support from outside the Site can be requested through the Brookhaven D.O.E. Bettis Atomic Power Labs, located approximately one hour away by car is the nearest D.O.E. facility.Cl A laboratory is included in the Emergency Response Facility.

7-9 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT Laboratory support for environmental sample analyses are available from the environmental contractor. C31

.4 Environmental Monitors The primary functions of the environmental radiological monitoring program are to establish the pre-operational background levels, detect any gradual build-up of long-lived radionuclides and verify that operation of the plant has no detrimental effect on the health and safety of the public or the environment. Field thermoluminescent dosimeters (T.LDs) and sampling media from environmental monitoring locations may, however, be utilized to obtain valuable assessment data in the event of an accident involving the release of a significant amount of radioactive material.

.5 Accident Monitors Several radiological monitors have been provided for assessment of radiological conditions or radiological release rates in the wake of a significant accident. These monitors generally supplement the monitors in the Radiation Monitoring System by extending the range of radiation measurements. Such monitors are provided for each of the major radioactivity release paths to the atmosphere and in the Containment Building. The range of the effluent monitors is about 1 E-7 to 1 E5 uCi/cc (Xe-133), and the range of the Containment area radiation monitor is about 1 R/hour to 1 E7 R/hour.

7.4.2 Fire Detection Systems Fire protection at the Beaver Valley Power Station is provided by a complete network of fire suppression and extinguishing systems. These systems include a central alarm system (with an annunciator panel located in the Control Rooms) which is activated by a variety of fire and smoke detection devices which are located throughout the plant. Although the suppression and extinguishing systems for BV-2 are similar to BV-1 they are not identical. These fire detection systems are identified in the BVPS Fire Protection Plans.

7-10 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.4.3 Geophysical Phenomena Monitors Monitors are provided for detecting and recording geophysical phenomena parameters related to meteorology and seismic events.

.1 Meteorology The Beaver Valley Power Station maintains an onsite Meteorological Measurements Program. This program is comprised of equipment and procedures which provide for indication and recording of meteorological measurements necessary to perform dose projections based on atmospheric dispersion of a radioactivity release from the station. Meteorological sensors are provided on a meteorology tower located near the site to measure and record the following parameters:

  • Wind direction at three altitudes
  • Wind speed at three altitudes
  • Vertical temperature difference
  • Ambient temperature

. Precipitation There are two (2) redundant trains of sensors located on this tower. The output from the two sets of sensors is processed and recorded (chart recorders) by instrumentation in a shelter located near the tower. Two redundant communication links transmit the processed data to the Atmospheric Radioactivity Effluent Release Assessment System (ARERAS) located in the Emergency Response Facility. ARERAS samples the parameters every five (5) seconds and calculates and records an average value every fifteen (15) minutes and once every hour. A minimum of one (1) month of historical hourly data and two (2) weeks of historical quarter hour data is available online at any time. This data is available on request at any ARERAS terminal and is accessed by the MIDAS dose projection software. The MIDAS/ARERAS system provides the States with the capability to receive meteorological data via dial-up modems.

7-11 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT The instrumentation in the meteorological shelter and the tower sensors have an automatic backup power supply. ARERAS is powered by the Emergency Response Facility uninterruptable power supply (UPS).

Backup meteorological information is available through the National Weather Service.

.2 Seismic Equipment Appropriate seismic instrumentation is provided at the Station to monitor and record the motion and peak shock imparted to critical elements of the Station (structures and components) due to an earthquake. Alarms are provided for peak accelerations and mechanical/electrical devices record the extent of the acceleration for subsequent evaluation to determine if maximum allowable accelerations have been exceeded and if any plant corrective actions are necessary.

The seismic instrumentation is categorized into three separate subsystems:

The Triaxial Time History Accelographs This system is continuously energized in standby. A triaxial acceleration switch activates recording equipment and sounds an annunciator in the Control Room at an acceleration of 0.01 g. Three independent triaxial sensors are provided--two in the containment, and one in the Auxiliary Building.

In the event of a system activation, the operator will obtain and assess the results from the recorders using the BVPS Operating Manual.

Both units are AC powered and have internal batteries.

  • Peak Shock Recorders (Triaxial Spectrum Recorders)

Three passive triaxial recorders are provided. One is located in the containment, the others are located in the Control Room and in the Auxiliary Building. The containment recorder provides trigger switches which activate annunciators located in the Control Room, at accelerations equivalent to 70% of the Operational Basis Earthquake (OBE) and 100% OBE. These sensors record the peak shock by reeds which scribe a metal plate. Each sensor contains several reeds of different resonant frequencies to provide for spectrum analysis.

7-12 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT Peak Recording Accelerometers Four peak recording triaxial accelerometers are provided--three in the containment and one in the Auxiliary Building. These units record the peak acceleration by the erasure of prerecorded lines on a small piece of magnetic tape. The tape is prepared for visual evaluation by a chemical process.

.3 Hydrologic Data Data on the river flow in the Ohio River is available from two sources.

The Lockmaster at the Montgomery Dam, located upriver in Industry, PA.,

is the primary source. The US Army Corps of Engineers provide 24-hour coverage at this location. The National Weather Service, River Forecasting Section, Pittsburgh is a source of river flow data during normal work hours, and during emergency periods of high river levels.

7.4.4 Process Monitoring Equipment Process monitoring instrumentation is provided in the Station Control Rooms to provide the operator with necessary data on plant status to operate the plant under normal and emergency situations. This instrumentation generally includes instruments that:

  • Provide information required to take pre-planned manual actions.
  • Provide information to monitor the process of accomplishing critical safety functions.
  • Indicate the potential for damage, or actual damage, to fission product barriers.
  • Indicate the effectiveness of individual safety systems.
  • Provide information for use in determining the magnitude of the release of radioactive materials, as described in Section 7.4.1.

7-13 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT In addition to the instrumentation described above, additional process parameter instrumentation systems are installed. These systems are the Safety Parameter Display System (SPDS) Computer, and the Inplant Process Computer (IPC) and Plant Safety Monitoring System (PSMS).

.1 Safety Parameter Display System The Safety Parameter Display Systems (SPDS) provide displays of essential plant parameters from which the safety status of operations may be assessed. The primary function of the SPDS is to help Control Room personnel make quick assessments of plant safety. Displays for this system are provided in the BVPS Control Rooms and the Technical Support Center (TSC). The display in the TSC serves both the TSC and the Emergency Operations Facility (EOF).

.2 Inplant Process Computer and Bypassed & Inoperable Status Indication System The Inplant Process Computer (LPC) is designed to obtain data from the reactor control, reactor protection, the environmental monitor racks, and other transducers in the plant and provide access to these indications in the Technical Support Center (TSC), the Emergency Operations Facility (EOF) and in the Control Room. The Bypassed & Inoperable Status Indication (BISI) System provides an indication in the Control Room of bypassed or inoperable equipment in the facility to assist the operators in operating the plant.

.3 The Plant Safety Monitoring System (PSMS) is located in Unit 2 Control Room. The PSMS will monitor plant conditions such as incore thermocouples, rod positions, Reactor vessel water level, etc.

7.4.5 Post Accident SamplingC 2 o Beaver Valley Power Station has Contingency Plans for obtaining and analyzing highly radioactive samples of reactor coolant, containment sump, and containment atmosphere in the event of a radiological accident. These Contingency Plans are maintained in the BVPS Chemistry Manual.

7-14 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.4.6 Emergency Response Data System (ERDS)

The BVPS Emergency Response Data System (ERDS) collects and transmits data as specified by the Nuclear Regulatory Commission (NRC). The system is tested for both Units 1 and 2 on a schedule specified by the NRC.

7.5 PROTECTIVE FACILITIES Facilities and designated assembly locations are provided which ensure adequate radiological protection for personnel assigned to emergency duties in the plant, and for the accommodation of other personnel evacuated from areas that may be affected by radiation and/or airborne radioactivity.

7.5.1 Station Control Rooms In addition to serving as the first-line control for emergency situations, the station Control Rooms have the following features which provide protection for personnel who may have emergency or operational duties throughout the course of any emergency:

  • Adequate shielding by concrete walls to permit continuous occupancy under severe accident conditions
  • An independent emergency air supply system, equipped with absolute and activated charcoal filters

. Continuous monitoring of radiation levels in the Control Room and throughout the plant by the RMSIDRMS system, with readout in the Control Room

  • Basic protection equipment for emergency teams (Appendix D), and listings of emergency supplies/equipment, and their locations within the station
  • Communications systems, as described in Section 7.6 7 15 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.5.2 Site Assembly Areas Specific locations are designated for assembly of personnel at the site in the event of a Site Assembly or a Site Accountability. These areas provide space to accommodate all personnel who may be at the station. They are located on the basis of logical access routes and physical separation from likely areas of radiation and/or airborne radioactivity. The locations and the individuals assigned are:

.1 Primary Assembly Area (Unit 1 Service Building-Locker Room Area, South Office Shops Building - Locker Room Area and Nuclear Construction Office and Shops)

Personnel without emergency assignments within the BVPS protected areas will report to these areas. This includes BVPS employees, visitors, and contractor groups not covered by a specific evacuation plan. The responsibility to ensure that a visitor reports to the proper area is that of the individual accompanying the visitor at the time evacuation occurs.

.2 Unit I/Unit 2 Contractor Personnel Construction and contractor personnel are covered by the BVPS procedures, which provides instructions for assembly, accountability and evacuation. Personnel are instructed on these areas upon arrival at the BVPS site.

.3 Personnel Access Facility Members of the Security Section assemble in accordance with the Beaver Valley Power Station Security Procedures.

.4 Training Building and other out-buildings designated in the Implementing Procedures. C19, C25 These buildings are located outside of the protected area. Personnel and visitors outside of the Unit 1-2 protected areas, will assemble in these buildings and await further instructions.

7-16 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.5.3 Remote Assembly Areas These areas are designated for assembly of personnel from within the site in the event of a Site Evacuation. The locations are the Western Power Delivery Division, Raccoon Headquarters and the Hookstown Grange. The Western Power Delivery Division, Raccoon Headquarters facility is located approximately 6.2 miles from the site in the SE sector. The Hookstown Grange is located approximately 3.5 miles from the site in the SW sector. There are telephone links between each of these locations and the Control Room/TSCIEOF.

The BVPS Emergency Director will direct personnel to the appropriate area based on the direction of plume travel. If, based on radiological measurements at the Remote Assembly Areas and/or data from the Control Room, neither of these locations is deemed by the BVPS Emergency Director to be appropriate, the BVPS Emergency Director in cooperation with management and State and county agencies will direct personnel to another location.

Since accountability and radiological monitoring would be performed prior to exiting the site, no provisions are made for inclement weather. If weather conditions make use of the facilities impracticable, evacuated personnel will be sent home (or to their assigned Mass Care Center, identified in the county emergency plans). In cases of extreme weather conditions, non-essential Site personnel would be sent home prior to roads becoming impassable, and thus would not be onsite when the emergency was declared.

7.6 COMMUNICATIONS SYSTEMS Communications are essential for effective activation and implementation of the Emergency Preparedness Plan. Beaver Valley Power Station has five independent systems for outside communication to Federal, state, county authorities, to corporate management, and to offsite support groups. These systems are the Commercial telephone system, the PAX system, the dedicated "hot lines", the Beaver Valley Emergency Response System and the Industrial Radio System. Onsite, the plant alarm system and the Station paging system provides communication/notification for Site personnel. Radio contact with the State agencies is via relay through their respective CountyC2 .

7-17 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT These multiple systems and redundancies ensure the performance of vital functions in transmitting and receiving information throughout the course of the emergency. Systems available at the various emergency facility locations are:

7.6.1 Commercial Telephone System The Beaver Valley Power Station site is provided with telephone service by Verizon. All lines entering the site are direct connections with the telephone exchange (724-643/682) in Midland, (724-775) Rochester or (330-315) in Akron, Ohio. There are numerous direct lines, all of which can be used simultaneously.

Power supply redundancy is provided for by emergency power supplies.

Emergency facilities served by direct lines:

  • Control Rooms
  • Emergency Operations Facility (EOF) and Alternate EOF
  • BVPSUnit 1/2 The Commercial systems are routinely used by station personnel performing routine station activities, thus, periodic testing is not necessary.

7.6.2 PAX System The PAX System includes automatic switchboards in the SOSB and the ERF.

These switchboards are connected to each other and connected via T1 carrier and fiber optic trunks to a digital switchboard at Akron, Ohio which in turn is connected to the public telephone network as well as to other switchboards. The ERF and SOSB switchboards also has direct trunks to the public telephone network.

The PAX System has Direct Inward Dial capability for all telephone lines connected to any of the Company switchboards (724-682-xxxx). These telephone lines also have the capability of calling any other telephone line on the PAX System as well as Direct Dial calling anywhere on the public telephone network.

7-18 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT The PAX systems are routinely used by shift operations personnel performing routine station activities, thus periodic testing is not necessary. Alternate EOF phones shall be checked quarterly.

7.6.3 "Hot Lines" to DEPIBRP and NRC Communications A separate and completely independent telephone "hot line" system provides direct communications with the Pennsylvania Department of Environmental Protection/Bureau of Radiation Protection (DEP/BRP).

The DEP/BRP "blue hotline" located in the EA & DP area of the ERF is used to provide radiological data. The DEP/BRP "White Hot Line" is located in the Control Room and is used to provide technical data. The DEP/BRP does not have 24-hour per day coverage on this circuit, but will activate the DEP/BRP staff upon notification from PEMA that an event has occurred. This phone is tested monthly.

The ENS (Emergency Notification System) is used to make the initial notification of an emergency declaration as well as providing ongoing information on plant status, systems and parameters to the NRC. The Emergency Telephone System (ETS) is a designated set of phones on the commercial phone system that DOES NOT go through either of the Beaver Valley Phone Switches but goes directly to Akron, Ohio for switching. This is to meet the requirements for dissimilar vulnerability to assure contact with the NRC during a declared emergency at Beaver Valley Power Station should the local phone switches become overloaded.

The ETS operates in the same manner as the commercial phone systems when placing a long distance call. Simply lift the receiver, wait for a dial tone and dial "9" then "1" before dialing the ten digit phone number. ENS phones are located in the following locations:

  • Control Room - Communications Console in the Administrative Assistant Area C31
  • Control Room- Unit I Communications ConsoleC31
  • Emergency Operations Facility
  • NRC EOC 7-19 Rev. 19

Section 7 Emergency Preparedness Plin EMERGENCY FACILITIES AND EQUIPMENT The HPN (Health Physics Network) phone, utilized to communicate radiological and meteorological conditions to the NRC, is also accessed by the ETS. These phones are located at:

  • Operations Support Center
  • Emergency Operations Facility (EA & DP Area)

. Technical Support Center (Rad Con Coord.)

NRC EOC Other phones associated with the ETS and dedicated to NRC Communications are located in the ERF and are described as follows:

  • Reactor Safety Counterpart Link (RSCL)
  • Protective Measures Counterpart Link (PMCL)
  • Management Counterpart Link (MCL)
  • Local Area Network (LAN) Access The Control Room ENS phone is tested daily, while the others are tested monthly.

7.6.4 Beaver Valley Power Station Industrial Radio BVPS operates a radio communications network on two frequency bands, 153.47 MHz and 153.635 MHz. This service is used by BVPS, the DLC Power Stations Department, and other corporate groups. Tone-operated squelch prevents standby emergency stations from receiving routine operational transmissions.

There are six fixed base station transceivers operating on the 153.47 MHz band associated with Beaver Valley Power Station (there are others serving other divisions within DLC). These are located at:

Columbiana County Communications Center (CCEMA) 7-20 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT There are operating consoles for this base station located at the Sheriff's Dispatcher, the Ohio Highway Patrol, and at CCEMA.

  • Hancock County Communication Center (HCOES)
  • Remote Relay Station on Shippingport hill SW from BVPS
  • Beaver County Emergency Services Center
  • Western Power Delivery Division, Raccoon Headquarters The remote relay station is operated from the Control Room SM communications console via a UHF radio link or a dedicated telephone line. This station has power redundancy supplied by batteries connected to a battery charger. Remote consoles are located at:
  • US area in the Control Room (BV-1) (Both frequencies)
  • Ul Plant Shutdown Panel
  • U2 Plant Shutdown Panel
  • Control Room Office (shared BV 1-2) (Both frequencies)
  • EA and DP Area (ERF) (153.47)
  • TSC - Radiological Controls Area (153.47)
  • Alternate EOF The offsite monitoring teams are provided with radios capable of communicating with the site.

The industrial radio system is operated routinely by shift operations and security personnel and the base stations are tested by substations and shops. The communications links between the Control Room, the risk counties, and the State Police are tested weekly. Portable transceivers maintained in the Control Room are used daily as part of the normal plant operations.

7-21 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.6.5 Beaver Valley Emergency Response System The Beaver Valley Emergency Response System (BVERS) is a computer aided Voice Mail System with teleconferencing capabilities.

The system provides two basic functions. First, the system will activate the BVPS Emergency Response Organization. Second, the system features a Gold Executive Conference capability for upper level management discussions.

BVERS will be tested monthly.

7.6.6 Station Page Party Telephone System A Station page party telephone system is used for onsite communications and notifications. There are five party lines available at each transceiver location.

Power supply redundance is provided by connection into the vital AC distribution, and by backup batteries.

The page party system is the primary means for alerting and providing instructions to Station personnel.

7.6.7 Personal Radio Pagers (Beepers)

Key personnel in the emergency organizations are provided with personal radio pagers. These pagers can be group-activated by calling the pager services.

BVERS and Voice Mail Systems provide personnel calling in with a message directing them to report to their emergency location, and will record information provided by the caller.

7.6.8 Station Emergency Alarm System A plant emergency alarm system provides audible warning of emergency conditions to station personnel. The emergency alarms are sounded over the station page system. The system is powered from the vital AC distribution.

7.7 ONSITE FIRST AID AND MEDICAL FACILITIES A Medical Facility, equipped with normal industrial first aid supplies, is located in the ERF Building. The BVPS Emergency Squad provides immediate first aid for any emergency within the protected area.

Standard first aid equipment is stored at designated locations throughout the station. The first aid kits are checked periodically, in accordance with station procedures and replenished as necessary. i 7-22 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY FACILITIES AND EQUIPMENT 7.8 DAMAGE CONTROL EQUIPMENT Damage control equipment consists of normal and special purpose tools and devices used for maintenance functions throughout the station. Personnel assigned to damage control teams are cognizant of the locations of specific equipment, which may be required in an emergency. The Emergency Squad Chief and the BVPS Emergency Director have access to keys for maintenance tool cribs, shops and other locations where appropriate damage control equipment may be stored.

Implementing Procedures provide guidance for emergency teams, and include locations for designated emergency equipment.

7-23 Rev. 19

Section 7 Emergency Preparedness Plan EMERGENCY 71 FACILITIES AND EQUIPMENT INTENTIONALLY BLANK 7-24 Rev. 19

Emergency Preparedness Plan A5.735A APPENDIX G REFERENCES CONTROLLED BVP8PUNIT 3 Rev. 11

Emergency Preparedness Plan APPENDIX G REFERENCE Cl - CR# 980708 C2 - CR# 980706 C3 - CR#980480 C4 - NPDAP 5.1 "Report Requirements" C5 - Unit 2 Licensing Condition 2.C(6)

C6 - CR#992882 C7 - CR#990012 C8 - CR#00-0616 C9 - CR#00-0617 CIO - CR#00-0618 ClH - CR#00-0615 C12 - CR#01-0246 C13 - CR#01-1168 C14 - CR#00-3939 C15 - CR#00-2202 C16 - CR#01-0246 C17 - CR#99-1234 C18 - CR#01-1011 App-G-1 Rev. 11

Emergency Preparedness Plan APPENDIX G REFERENCE C19 - CR#01-3556 C20 - LAR #295 and #166 (Letter Number L-01-103, 8/13/01, PASS Elimination, CR# 01-2107)

C21 - CR#02-02195 and NRC Inspection Report 50-334/02-03, 50-412/02-03, dated 4/12102 C22 - CR#02-02524 C23 - CA's # 01-6025-6, 01-3198-98, 02-00444-5 C24 - CA #02-00444-4 C25 - CA's #02-0667-01, 02-07647-06 C26 - CR's #02-08649, 02-09224 C27 - CR#02-09061-01 C28 - CR#03-01371 C29 - CA# 02-02195-8 C30 - CR#04-00104 C31 - CA#03-02202-15 (Includes deletion of Section 7, Figures and Tables App-G-2 Rev. 11

Emergency Preparedness Plan The Emergency Preparedness PlanINUREG-0654 Cross Reference was developed using the following documents:

NUREG-0654 Rev. 1 November 1980 EPP Section 1 Rev. 10 EPP Section 2 Rev. 10 EPP Section 3 Rev. 10 EPP Section 4 Rev. 11 EPP Section 5 Rev. 10 EPP Section 6 Rev. 10 EPP Section 7 Rev. 10 EPP Section 8 Rev. 10 Unless Otherwise Noted EPP Section 9 Rev. 10 EPP Appendix A Rev. 10 EPP Appendix B Rev. 10 EPP Appendix C Rev. 10 EPP Appendix D Rev. 10 EPP Appendix E Rev. 10 EPP Appendix F Rev. 10 App-G-3 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emerlenc Plan Reference NUREG-0654,Section II.A. l.a Paragraph 5.5 Paragraph 5.6.1 Paragraph 5.6.2 NUREG-0654,Section II.A. l.b Paragraph 5.2 Paragraph 5.3 Paragraph 5.4 NUREG-0654,Section II.A.1.c Figures 5.1 through 5.5 Section 5.6 NUREG-0654,Section II.A. I .d Paragraph 5.2.1 Paragraph 5.2.2 NUREG-0654,Section II.A. I.e Paragraph 5.2 Tables 6.1 and 6.2 NUREG-0654,Section II.A.3 Paragraph 8.3.d Appendix A NUREG-0654,Section II.A.4 Paragraph 5.2.1 Paragraph 5.2.2 NUREG-0654,Section II.B. I Figure 5.2 NUREG-0654,Section II.B.2 Paragraph 5.2.1 Paragraph 5.2.2 Appendix E NUREG-0654,Section II.B.3 Paragraph 5.2.1 Paragraph 5.2.3 NUREG-0654,Section II.B.4 Paragraph 5.2.1 NUREG-0654,Section II.B.5 Paragraph 5.2 Table 5.1 NUREG-0654,Section II.B.6 Paragraph 5.5 Figure 5.6 NUREG-0654,Section II.B.7 Paragraph 5.2 Table 5.1 NUREG-0654,Section II.B.7.a Paragraph 5.2.18 App-G-4 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emergenc Plan Reference NUREG-0654, Paragraph 9.3 Section II.B.7.b Paragraph 9.4 NUREG-0654, Paragraph 5.2.19 Section II.B.7.c Paragraph 5.2.2 NUREG-0654,Section II.B.7.d Paragraph 5.3 NUREG-0654, Paragraph 5.5.2 Section II.B.8 Paragraph 5.5.3 Paragraph 5.5.4 NUREG-0654,Section II.B.9 Paragraph 5.5.5 Appendix A NUREG-0654,Section II.C. l.a Paragraph 5.2.1.7 Paragraph 5.2.2.6 NUREG-0654,Section II.C.l.b Paragraph 5.6.2 NUREG-0654,Section II.C.l.c Paragraph 7.1.4 Paragraph 7.6 NUREG-0654,Section II.C.2.b Paragraph 5.6.1 NUREG-0654,Section II.C.3 Paragraph 7.1.4 Paragraph 7.4 NUREG-0654,Section II.C.4 Paragraph 5.5 Paragraph 5.6 Appendix A NUREG-0654,Section II.D. 1 Section 4 NUREG-0654,Section II.D.2 Section 4 NUREG-0654,Section II.E. 1 Paragraph 6.4 NUREG-0654,Section II.E.2 Paragraph 7.6 NUREG-0654,Section II.E.3 Paragraph 6.4.1 App-G-5 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS-REFERENCE Reference Emer enc Plan Reference NUREG-0654, Paragraph 6.4.2 Section JILEA NUREG-0654, Paragraph 6.4.2 Section II.E.4.a NUREG-0654, Paragraph 6.4.2 Section II.E.4.b NUREG-0654, Paragraph 6.4.2 Section II.E.4.c NUREG-0654, Paragraph 6.4.2 Section lI.E.4.d NUREG-0654, Paragraph 6.4.2 Section II.E.4.e NUREG-0654, Paragraph 6.4.2 Section II.E.4.c NUREG-0654, Paragraph 6.4.2 Section II.E.4.g NUREG-0654, Paragraph 6.4.2 Section IIE.4.e NUREG-0654, Paragraph 6.4.2 Section II.E.4.i NUREG-0654, Paragraph 6.4.2 Section II.E.4.j NUREG-0654, Paragraph 6.4.2 Section II.E.4.h NUREG-0654, Paragraph 6.4.2 Section II.E.4.i NUREG-0654, Paragraph 6.4.2 Section II.E.4.M NUREG-0654, Paragraph 6.4.2 Section II.E.4.n NUREG-0654, Paragraph 3.3.3 Section II.E.6 Appendix F App-G-6 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emereencv Plan Reference NUREG-0654,Section II.E.7 Paragraph 6.7.2.5 NUREG-0654, Paragraph 7.6 Section II.F. l.a Table 6.2 NUREG-0654, Paragraph 7.6 Section l.F.1.b Table 6.2 NUREG-0654, Paragraph 7.6 Section II.F. l.c Table 7.1 NUREG-0654, Paragraph 7.6 Section II.F.l.d Table 7.1 NUREG-0654, Paragraph 7.6 Section II.F. l.e Table 7.1 NUREG-0654, Paragraph 7.6.3 Section ll.F.1.f NUREG-0654, Paragraph 7.6.1 Section II.F.2 Paragraph 7.6.2 Paragraph 7.6.5 Paragraph 6.3.1 NUREG-0654, Paragraph 8.1.4.f Section lI.F.3 Paragraph 7.6 NUREG-0654, Paragraph 8.1.1.a Section II.G. I NUREG-0654, Paragraph 8.5 Section II.G.l.a, b, c, d NUREG-0654, Paragraph 8.5 Section II.G.2 NUREG-0654, Paragraph 7.1.5 Section II.G.3.a NUREG-0654, Paragraph 7.1.5 Section II.G.3.b NUREG-0654, Paragraph 5.3.1 Section Il.G.4.a App-G-7 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emereenc Plan Reference NUREG-0654, Paragraph 5.3.1 Section II.G.4.b Paragraph 5.3.2 NUREG-0654, Paragraph 5.3.4.1 Section I.G.4.c NUREG-0654, Paragraph 8.1.2.f Section II.G.5 NUREG-0654, Paragraph 7.1.4.1 Section II.H .1 Paragraph 7.1.2 NUREG-0654, Paragraph 7.1.4.2 Section II.H.2 NUREG-0654, Paragraph 6.2 Section II.H.4 NUREG-0654, Paragraph 7.4 Section II.H.5 NUREG-0654, Paragraph 7.4.3 Section II.H.5.a NUREG-0654, Paragraph 7.4.1 Section II.H.5.b NUREG-0654, Paragraph 7.4.4 Section lI.H.5.c NUREG-0654, Paragraph 7.4.2 Section II.H.5.d NUREG-0654, Paragraph 7.4.3 Section II.H.6.a NUREG-0654, Paragraph 7.4.1 Section II.H.6.b Appendix D NUREG-0654, Paragraph 7.1.4.3 Section II.H.6.c Paragraph 7.1.4.4 Paragraph 7.4.1.3 NUREG-0654, Paragraph 7.2 Section II.H.7 Appendix D NUREG-0654, Paragraph 7.4.3.1 Section II.H.8 App-G-8 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emereency Plan Reference NUREG-0654, Paragraph 7.1.2 Section Il.H.9 NUREG-0654, Paragraph 8.4 Section II.H.1O NUREG-0654, Appendix D Section II.H. I1 NUREG-0654, Paragraph 5.2.8 Section II.H.12 Paragraph 7.1.4.4 NUREG-0654, Section 4 Section II.I. I NUREG-0654, Paragraph 7.4.1 Section II.I.2 Paragraph 7.4.1.6 NUREG-0654, Paragraph 6.5.3 Section I1.I.3.a NUREG-0654, Paragraph 6.5.3 Section II.I.3.b NUREG-0654, Paragraph 6.5.3 Section 11.1.4 Paragraph 6.5.4 NUREG-0654, Paragraph 7.4.3.1 Section Il.1.5 Paragraph 7.1.4.e Paragraph 7.6.3 NUREG-0654, Paragraph 6.5.3.2 Section I.1.6 NUREG-0654, Paragraph 6.5.4 Section 11.1.7 NUREG-0654, Paragraph 6.5.4 Section 11.1.8 Table 5.1 Table 6.1 NUREG-0654, Paragraph 6.5.4.3 Section II.I.9 NUREG-0654, Paragraph 6.5.3.2 Section 11.1.10 NUREG-0654, Paragraph 6.7.1 Section II.J.1 App-G-9 Rev. 11

I Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE N-,

Reference Emereenc Plan Reference NUREG-0654, Paragraph 6.7.1 Section II.J. l.a NUREG-0654, Paragraph 6.7.1 Section IL.J.l .b NUREG-0654, Paragraph 6.7.1 Section IIJ. l .c NUREG-0654, Paragraph 6.7.1 Section IL.J.l .d NUREG-0654, Paragraph 6.7.1 Section II.J.2 Paragraph 7.5.3 Figure 7.2 NUREG-0654, Paragraph 6.7.1.6 Section II.J.3 NUREG-0654, Paragraph 6.7.1.4 Section II.J.4 Paragraph 6.7.1.6 NUREG-0654, Paragraph 5.2.13.3 Section II.J.5 Paragraph 5.2.6.4 Paragraph 6.7.1.5 NUREG-0654, Paragraph 6.7.1.8 Section II.J.6.a NUREG-0654, Paragraph 6.7.1.6 Section I.J.6.b NUREG-0654, Paragraph 6.7.1.8 Section II.J.6.c NUREG-0654, Paragraph 6.7.2 Section II.J.7 NUREG-0654, Appendix B Section II.J.8 NUREG-0654, Figure 7.2 (Evacuation Route)

Section II.J.lO.a Paragraph 7.5.3 NUREG-0654, Appendix B, Figure B-1 Section IJ.IOb App-G-10R Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emergency Plan Reference NUREG-0654, Appendix F Section II.J.lO.c NUREG-0654, Appendix B Section ILIJ.1O.m Paragraph 6.7.1.2 NUREG-0654, Table 6.3 Section I.K. 1 NUREG-0654, Table 6.3 Section II.K. l.a NUREG-0654, Table 6.3 Section I.K. .b NUREG-0654, Table 6.3 Section II.K.l.c NUREG-0654, Table 6.3 Section II.K.1.d NUREG-0654, Table 6.3 Section I.K.l.e NUREG-0654, Table 6.3 Section II.K. l.f NUREG-0654, Table 6.3 Section II.K.1.g NUREG-0654, Paragraph 5.2.1 Section II.K.2 Paragraph 6.7.1.7 NUREG-0654, Table 5.1 Section II.K.3.a Paragraph 6.7.1.7 NUREG-0654, Paragraph 6.7.1.7 Section II.K.3.b NUREG-0654, Paragraph 6.8.1 Section II.K.5.a NUREG-0654, Paragraph 6.8.1 Section II.K.5.b Paragraph 6.8.2 NUREG-0654, Paragraph 6.7.1.6 Section II.K.6.a App-G-11 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emergenc Plan Reference NUREG-0654, Paragraph 6.7.1.6 Section II.K.6.b NUREG-0654, Paragraph 6.7.1.6 Section II.K.6.c NUREG-0654, Paragraph 6.7.1.6 Section II.K.7 NUREG-0654, Appendix A Section II.L.1 Paragraph 6.8.4 NUREG-0654, Paragraph 6.8.2 Section II.L.2 NUREG-0654, Appendix A Section 1IL.4 Paragraph 6.8.3 NUREG-0654, Section 9 Section Il.M. 1 NUREG-0654, Section 9 Section II.M.2 NUREG-0654, Paragraph 9.2 Section II.M.3 NUREG-0654, Paragraph 9.6 Section II.M.4 NUREG-0654, Paragraph 8.1.4.a Section II.N. l.a NUREG-0654, Paragraph 8.1.4.a Section l.N.l.b NUREG-0654, Paragraph 8.1.4(f)

Section lI.N.2.a NUREG-0654, Paragraph 8.1.4(b)

Section lI.N.2.b NUREG-0654, Paragraph 8.1.4(c)

Section Il.N.2.c NUREG-0654, Paragraph 8.1.4(d)

Section II.N.2.d App-G-12R; Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emer enc Plan Reference NUREG-0654, Paragraph 8.1.4(e)

Section II.N.2.e NUREG-0654, Paragraph 8.1.3.d Section II.N.3 NUREG-0654, Paragraph 8.1.3.d Section II.N.3.a NUREG-0654, Paragraph 8.1.3.d Section II.N.3.b NUREG-0654, Paragraph 8.1.3.d Section II.N.3.c NUREG-0654, Paragraph 8.1.3.d Section II.N.3.d NUREG-0654, Paragraph 8.1.3.d Section II.N.3.e NUREG-0654, Paragraph 8.1.3.d Section II.N.3.f NUREG-0654, Paragraph 8.1.3.f Section II.N.4 NUREG-0654, Paragraph 8.1.3.g Section II.N.5 NUREG-0654, Paragraph 8.1.2.b Section II.0. l.a NUREG-0654, Paragraph 8.1.2 Section II.0.2 NUREG-0654, Paragraph 6.8.2 Section 11.0.3 NUREG-0654, Paragraph 8.1.1 .b Section II.0.4.a NUREG-0654, Paragraph 8.1.1 .b Section II.0.4.b NUREG-0654, Paragraph 8.}.1.b Section II.0.4.c App-G-13 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE Reference Emerienc Plan Reference NUREG-0654, Paragraph 8.1.1 .c Section lI.0.4.d Paragraph 8.1.2.c Paragraph 8.1.2e NUREG-0654, Paragraph 8.1.2.a Section II.0.4.e NUREG-0654, Paragraph 8.1.1.b Section Il.O.4.f NUREG-0654, Paragraph 8.1.2.b Section Il.Q.4.g NUREG-0654, Paragraph 8.1.2.d Section II.0.4.h NUREG-0654, Paragraph 8.1.1 .b Section II.O.4.i NUREG-0654, Paragraph 8.1.1 .b Section ILO..j NUREG-0654, Paragraph 8.1.1 (Rev. 11)

Section lI.0.5 NUREG-0654, Paragraph 8.2 Section II.P. I NUREG-0654, Paragraph 8.2 Section II.P.2 NUREG-0654, Paragraph 8.2 Section II.P.3 NUREG-0654, Paragraph 8.3.d Section II.P.4 NUREG-0654, Paragraph 8.3.b Section II.P.5 NUREG-0654, Paragraph 5.6 Section II.P.6 NUREG-0654, Appendix C Section II.P.7 App-G-14 Rev. 11

Emergency Preparedness Plan NUREG-0654 CROSS REFERENCE I Reference l Emereencv Plan Reference I NUREG-0654, Table of Contents in front of Plan and for each Section.

Section II.P.8 NUREG-0654, Paragraph 8.3.e Section II.P.9 Paragraph 8.3.f NUREG-0654, Paragraph 8.3.g Section II.P. 10 Paragraph 8.1.4.f App-G-15 Rev. 11

A5.735B EPPIIMPLEMENTING PROCEDURES - EFFECTIVE INDEX INSTRUCTIONS 1/2-EPP-I-la Recognition and Classification Revision 4 of Emergency Conditions 1/2-EPP-I-lb Recognition and Classification Revision 4 of Emergency Conditions 1/2-EPP-1-2 Unusual Event Revision 19 1/2-EPP-1-3 Alert Revision 18 1/2-EPP-1-4 Site Area Emergency Revision 18 1/2-EPP-I-5 General Emergency Revision 19 IMPLEMENTING PROCEDURES 1/2-EPP-IP 1 Series - Activation

. 1.1 Notification Revision 31 1.2 Communications and Revision 19 Dissemination of Information I

1.3 Turnover Status Checklist ED/ERM Revision 9 1.4 Technical Support Center (TSC) Revision 21 Activation, Operation and Deactivation I 1.5 Operations Support Center (OSC) Revision 15 Activation, Operation and Deactivation 1.6 Emergency Operations Facility (EOF) Revision 17 Activation, Operation and Deactivation 1.7 Emergency Response Organization (ERO) Revision 14 I Teams CONTROLLED BVPS-UNIT 3 REVISION 63

A5.735B EPPIMAPLEMENTING PROCEDURES - EFFECTIVE INDEX 1/2-EPP-IP 2 Series - Assessment 2.1 Emergency Radiological Monitoring Revision 12 l 2.2 Onsite Monitoring for Airborne Release Revision 13 2.3 Offsite Monitoring for Airborne Release Revision 14 2.4 Offsite Monitoring for liquid Release; Revision 9 2.5 Emergency Environmental Monitoring, Revision 11 2.6 Environmental Assessment and Dose Revision 15 Projection Controlling Procedure 2.6.1 Dose Projection - Backup Methods Revision 11 2.6.2 Dose Projection - ARERAS/MIDAS Revision 13 With FSAR Defaults 2.6.3 Dose Projection - ARERAS/MIDAS Revision 13 With Real-Time Inputs 2.6.4 Dose Projection - ARERAS/MIDAS Revision 14 With Manual Inputs 2.6.5 Alternate Meteorological Parameters Revision 11 2.6.6 Dose Projections By Hand Calculation - Revision 7 Known Isotopic Release 2.6.7 Dose Assessment Based on Revision 8 Field Measurements 2.6.8 Dose Assessment Based on Revision 7 Environmental Measurements and Samples 2.6.9 Integrated Dose Assessment Revision 7 2.6.10 Ground Contamination Assessment Revision 8 and Protective Action REVISION 63 I

A5.735B EPPAIMPLEMENTING PROCEDURES - EFFECTIVE INDEX 1/2-EPP-IP 2 Series - Assessment 2.6.11 Dose Projection - Miscellaneous Data Revision 11 2.6.12 Dose Projection -ARERAS/MIDAS Revision 10 With Severe Accident Assessment 2.7 Liquid Release Estimate Revision 8 2.7.1 Liquid Release Estimate - Revision 10 Computer Method 1/2-EPP-IP 3 Series - Onsite Protective Actions 3.1 Evacuation Revision 8 3.2 Site Assembly and Personnel Accountability Revision 14 I 3.3 Emergency Contamination Control Revision 8 3.4 Emergency Respiratory Protection Revision 9 3.5 Traffic and Access Control Revision 10 1/2-EPP-IP 4 Series - Offsite Protective Actions 4.1 Offsite Protective Actions Revision 17 1/2-EPP-IP 5 Series - Aid to Personnel 5.1 Search and Rescue Revision 8 5.2 RESERVED 5.3 Emergency Exposure Criteria and Control Revision 9 5.4 Emergency Personnel Monitoring Revision 9 REVISION 63

A5.735B ~ 7 41 EPPIIMPLEMENTING PROCEDURES - EFFECTIVE INDEX 1/2-EPP-IP 6 Series - Re-entry/Recovery 6.1 Re-entry to Affected Areas - Revision 10 Criteria and Guidance 6.2 Termination of the Emergency and Recovery Revision 11 1/2-EPP-IP 7 Series - Maintainin2 Emerzencv Preparedness 7.1 Emergency Equipment Inventory Revision 17 and Maintenance Procedure I 7.2 Administration of Emergency Preparedness Revision 9 Plan, Drills and Exercises 7.3 Emergency Preparedness Testing Revision 0 1/2-EPP-IP 8 Series - Fire Fightine 8.1 Fires in Radiologically Controlled Areas Revision 11 1/2-EPP-IP 9 Series - Nuclear Communications 9.1 Emergency Public Information Revision 12 Emergency Response Organization Controlling Procedure 9.2 Reserved 9.3 Activation, Operation and Deactivation Revision 6 I of the Emergency Public Information Organization Emergency Operations Facility (EOF) 9.4 Activation, Operation and Deactivation Revision 11 of the Joint Public Information Center (JPIC) 9.5 Activation, Operation and Deactivation Revision 8 of the Penn Power Customer Account Services Department 1/2-EPP-IP 10 Series - Corporate Response 10.1 Emergency Response Organization Revision 3 Corporate Support REVISION 63

A5.735B EPPJIMPLEMENTING PROCEDURES - EFFECTIVE INDEX 1/2-EPP-IP ANNEXES Annex A - Westinghouse Emergency Response Plan Revision 8 Annex B - DELETED Annex C - Major Injury Involving Radioactive Contamination For The Medical Center, Beaver Revision 10 Annex D - Procedure for Transferring Radiation Casualties to the Radiation Emergency Response Program (UPMC Presbyterian) Revision 8 Annex E - Reserved REVISION 63

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