ML18169A227

Attachment 3 - Proposed NAPS Emergency Plan Changes

ML18169A227
Person / Time
Site:	Surry, North Anna
Issue date:	06/13/2018
From:	Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation
References
18-215
Download: ML18169A227 (138)

Text

ATTACHMENT 3 Serial No.18-215 Docket Nos. 50-338/339 50-280/281 PROPOSED NAPS EMERGENCY PLAN CHANGES VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2

, / .. Dom1n1on Emergency Plan Title: North Anna Power Station Emergency Plan Revision Number: #TBD Effective Date: Revision # TBD updates this entire document.

Revised material includes , but is not limited to: 1. Establishment of a consolidated emergency operations facility known as the Corporate Emergency Response Center (CERC) i n Glen Allen , V ir g i nia. Th i s CERC replaces the former on-site Local Emergency Operations Facility (local EOF , LEOF), the former backup Central EOF , and the headquarters support organ i zation assembly location formerly known as the CERC. A near-s it e location is identified for Nuclear Regulatory Commission (NRG) and offsite responders to interact face-t o-f ace with emergency response personnel entering and leaving the nuclear power reactor site. 2. Incorporation of the applicable content previously contained in the Corporate Emergency Response Plan. 3. Elim i nation of automatic ringdown phones between the EOF and Louisa County , and between the EOF and Spotsy l vania County. 4. Replacement of references to " equ i valency cred it" for requ ir ed training sessions w i th reference to administrative processes for train i ng exemptions and equivalent qual i fications. 5. Designat i on of the Fac ili ty Safety Review Comm i ttee (FSRC) as the approval authority for emergency plan revisions and the Manager Nuclear Emergency Preparedness as the approval authority for emergency plan implementing procedu r e revisions. 6. Addition of reference to availability of current letters of ag r eement (LOAs) and removal of LOAs from Appendix 10.1. Items 1-6 authorized by License Amendment

1. 1. 1. /### and associated NRG SER (Reference Incom i ng Seria l ##-###, dated#/#/####~~ This in formatio n is to be added fo ll owi n g receipt of NRC Safety Eva lu ation R eport. Approvals on File SECTION 1.0 1.0 1.1 2.0 2.1 2.2 2.3 3.0 3.0 4.0 4.0 4.1 4.2 4.3 4.4 5.0 5.0 5.1 5.2 5.3 5.4 NORTH ANNA POWER STATION EMERGENCY PLAN TABLE OF CONTENTS SUBJECT TABLE OF CONTENTS Table of Contents NUREG-0654 Cross Reference Index DEFINITIONS Definitions Acronyms and Abbreviations SCOPE AND APPLICABILITY Site Specifics Emergency Plan North Anna Hydroelectric Unit

SUMMARY

OF EMERGENCY PLAN Summary of Emergency Plan EMERGENCY CONDITIONS Emergency Conditions Spectrum of Postulated Accidents Emergency Classification System State and Local County Classification System Requirements for Written Summaries of Emergency Events ORGANIZATIONAL CONTROL OF EMERGENCIES Organizational Control of Emergencies Normal Station Organization Emergency Response Organization Augmentation of Emergency Response Organization Coordination with Participating Government Agencies NAEP Page i.1 Revision # TBD PAGE NO. i.1 i.4 1.1 1.2 1.6 2.1 2.2 2.2 2.3 3.1 3.2 4.1 4.2 4.2 4.3 4.8 4.8 5.1 5.4 5.4 5.4 5.14 5.16 SECTION 6.0 6.0 6.1 6.2 6.3 6.4 6.5 7.0 7.0 7.1 7.2 7.3 7.4 7.5 7.6 8.0 8.0 8.1 8.2 8.3 8.4 8.5 8.6 8.7 8.8 8.9 9.0 9.0 9.1 9.2 SUBJECT EMERGENCY MEASURES Emergency Measures Activation of the Emergency Plan Assessment Actions Protective Actions Aid to Affected Personnel Offsite Support EMERGENCY FACILITIES AND EQUIPMENT Emergency Facilities and Equipment Emergency Response Facilities Communications System Assessment Facilities Available Onsite Assessment Facilities Available Offsite Damage Control Equipment and Supplies Early Warning System MAINTAINING EMERGENCY PREPAREDNESS Maintaining Emergency Preparedness Responsibility for Maintaining Emergency Preparedness NAEP Page i.2 Revision # TBD PAGE NO. 6.1 6.2 6.2 6.2 6.3 6.6 6.8 7.1 7.3 7.3 7.5 7.7 7.10 7.10 7.10 8.1 8.3 8.3 Maintenance of the Emergency Plan Implementing Procedures , and Related Documents 8.4 8.5 8.8 8.8 8.10 8.12 8.13 8.14 Training of Emergency Response Organization Personnel Training of Offsite Support Personnel Emergency Drills Emergency Exercises Testing and Maintenance of Emergency Equ i pment Informing the Public Independent Review of the Emergency Preparedness Program RECOVERY Recovery Recovery Methodology Population Exposure 9.1 9.2 9.2 9.3 i SECTION 10.0 10.1 10.2 10.3 10.4 10.5 10.6 10.7 10.8 10.9 10.10 10.11 SUBJECT APPENDICES Letters of Agreement Deleted NAEP Page i.3 Revision # TBD Maps of Exclusion Area , Low Population and Emergency Planning Zone Boundaries Listing of EPIPs Protective Equipment and Supplies Deleted Supporting Plan Contact Estimation of Evacuat i on Times Radiation Emergency Plan , MCVHNCU -Dominion Power Federal Radiological Monitoring and Assessment Center (FRMAC) Operations Plan Initiating Conditions

/Emergency Action Levels NUREG-0654 Ref. Section A. 1a. A. 1 b. A. 1c. A. 1d. A. 1e. A. 2a. A. 2b. A. 3 A. 4 8. 1 8.2 8.3 8.4 8.5 8.6 8. 7a. 8. 7b. 8. 7c. 8. 7d. 8.8 8.9 C. 1a. C. 1b. C. 1c. C. 2a. C. 2b. C. 3 C.4 D. 1 D. 2 D. 3 D.4 E. 1 E.2 E.3 E. 4.a thru n E.5 E.6 E. 7 NORTH ANNA EMERGENCY PLAN NUREG-0654 CROSS REFERENCE INDEX NAEP NUREG-0654 Section No. Ref. Section 5.3-5.4 F. 1a. 5.4 F. 1b. Figure 5.4 F. 1c. 5.0 F. 1d. 5.2 , 5.4 , 5.4.5 F. 1e. N/A F. 1f. N/A F. 2 5.3 , App x. 10.1 F. 3 5.2 , 5.3 G. 1 5.1 G. 2 5.0 , 5.2 G. 3a. 5.0 G. 3b. 5.2.1.1 G. 4a. 5.2 , Table 5.2 G. 4b. Figure 5.4 G. 4c. 5.3.1 G. 5 5.3.1 5.3.1 H. 1 5.3.1 H.2 5.3.2 H.3 5.3.3 , 5.4 , Appx. 10.1 H.4 H.5 5.3.1 , 5.4. 7 H. 5a. 5.4.7 H. 5b. 5.4.7 H. 5c. N/A H. 5d. 5.3 , 5.4 H. 6a. 5.3.3 H. 6b. 5.3.3 H. 6c. H. 7 4.2 H.8 4.2 H.9 N/A H. 10 N/A H. 11 H. 12 5.4 , 6.0 -6.1 6.1 1 6.1 2 6.1 3a. N/A 3b. 6.3.1 , 7.6 4 6.3.1 5 6 7 8 9 10 11 NAEP Section No. NAEP Page i.4 Revision # T B D 5.2 , 5.4.5 , 7.2 7.2 7.2 7.2 5.2 7.2 6.4.3 8.7 8.8 8.8 8.8 , 7.1.4 , 5.3.1 7.1.5 5.3.1 5.3.1 8.8 8.8 7.1 7.1 7.1 5.2 7.3 7.3.1 , 7.3.3 7.3.2 7.3.4 7.3.5 7.4 7.3.2 7.3.2 7.3.2 7.3.3 7.1.2 8.7 , 7.5 Appx. 10.5 7.1.4 4.2 7.3 6.2 6.2 6.2 7.3.3 , 7.3.4 7.3.2 7.3.2 5.2 , 7.3.2 7.3.2 6.3.1 N/A --

NUREG-0654 Ref. Section J. 1a. J. 1b. J. 1c. J. 1d. J.2 J. 3 J.4 J. 5 J. 6a. J. 6b. J. 6c. J. 7 J.8 J. 9 J. 10a. J. 10b. J. 10c. J. 1 Od.-1. J.10m J. 11 J. 12 K. 1 a.-g. K.2 K. 3a. K. 3b. K.4 K. 5a. K. 5b. K. 6a. K. 6b. K. 6c. K. 7 L. 1 L. 2 L. 3 L. 4 M. 1 M. 2 M.3 M.4 NORTH ANNA EMERGENCY PLAN NUREG-0654 CROSS REFERENCE INDEX NAEP NUREG-0654 Section No. Ref. Section 6.3.2 N. 1a. 6.3.2 N. 1b. 6.3.2 N.1c. 6.3.2 N.1.d. 6.3.2 N.2 6.3.2 N.2a 6.3.2 N. 2b. 6.3.2 N. 2c. 6.3.3 N. 2d. 6.3.3 N. 2e.1 6.3.3 N. 2e.2 6.1 -6.3 N. 3a.-f. 6.3.1 , Appx. 10.8 N.4 N/A N.5 App x. 10.8 Appx. 10.8 0. 1 6.3.1 0. 1.a N/A 0. 1.b 6.3.1 0. 2 N/A 0. 3 N/A 0. 4a. 0. 4b. 6.4.1 0. 4c. 6.4.1 0. 4d. 5.2 , 6.4 0. 4e. 6.4 0. 4f. N/A 0. 4g. 6.4.2 0. 4h. 6.4.2 0. 4i. 6.4.2 0.4j. 6.4.2 0. 5 6.4.2 6.4.2 P. 1 P.2 6.4 P.3 6.4.2 P.4 N/A P. 5 6.4.3 P.6 P. 7 9.1 P.8 9.0 , Figure 9.1 P.9 9.0 P. 10 9.2 NAEP Section No. 8.6 8.6 8.6.1 N/A 8.5 8.5.1 8.5.2 8.5.3 8.5.4 8.5.6 8.5.5 8.5 , 8.6 8.6.5 8.6.5 8.3 8.4 N/A 8.4 NAEP Page i.5 Revision # TBD 6.4.2 , Table 8.1 8.3.3 , Table 8.1 Table 8.1 Table 8.1 Table 8.1 Table 8.1 Table 8.1 Table 8.1 8.4 , Table 8.1 Table 8.1 Table 8.1 8.3.3 8.3.3 8.1 8.1 8.2.1 8.2.3 Appx. 10.1 Index 10.4 Pages i.1 -i.5 8.9 8.2.2 Part 1.0 1.1 Subject Definitions NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 1 DEFINITIONS Acronyms and Abbreviations NAEP Page 1.1 Revision # TBD Page No. 1.2 1.6

1.0 DEFINITIONS

NAEP Page 1.2 Revision # TBD

• Alert -Events are in process or have occurred wh i ch involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening r i sk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the Env i ronmental Protection Agency Protective Action Guideline exposure levels.

• Annually -12 months +/-3 months.

• Biennial -Occurring every two years.

• Buffer Sectors -Two 22 1/2° sectors flanking each side of the 22 1/2° primary sector.

• Commonwealth of Virginia Emergency Operations Plan (COVEOP), Hazard-Specific Annex #1 -Radiological Emergency Response.

• Control Room -Station main control center seNing as the initial location for command and control of the emergency response effort.

• Corporate Emergency Response Center (CERC) -Consolidated emergency operations facility for North Anna Power Station and Surry Power Station. Designated facility seNing as the focal point for inter-company efforts implemented to support stat i on emergency response actions and for dissemination of emergency informat i on. The CERC is located at the Innsbrook Technical Center in Glen Allen , Virginia.

• Deep Dose Equivalent (DOE) -Direct external radiation exposure to the body (e.g., cloud shine , contamination , or direct radiation). DOE is assumed equivalent to Effective (external)

Dose Equivalent (EDE) with respect to uniform exposure.

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

• Effective Date -Date of change; implementat i on date assigned by approval authority; date from which 30-day NRG submittals are required in accordance with 10 CFR 50 , Appendix E.V.

• Emergency

-Any situation that may result in undue risk to the health and safety of the public and/or site personnel, or significant damage to property or equipment.

• Emergency Action Levels (EALs) -Events , such as equipment malfunctions , natural phenomena , radiological dose rates , etc., that may be used as thresholds for initiating such specific emergency measures as designating a particular class of emergency , i nitiating a notification procedure , or initiating a particular protective action.

• Emergency Classifications

Notification of Unusual Event Alert Site Area Emergency General Emergency NAEP Page 1.3 Revision # TBD

• Emergency Plan Implementing Procedures

{EPIPs) -Emergency response procedures that implement the Emergency Plan.

• Emergency Planning Zones (EPZ):

• Plume Exposure Pathway EPZ -An area delineated by an approximate ten-mile radius circle around the North Anna Power Station.

• Ingestion Exposure Pathway EPZ -An area delineated by an approximate fifty-mile radius circle around the North Anna Power Station with the potential of internal exposure from the ingestion of radioactive material through the food pathway.

• Emergency Response Facility {ERF) -Emergency facilities include the Control Room , Technical Support Center , Operational Support Center , Corporate Emergency Response Center, and Joint Information Center.

• Exclusion Area -The area within a 5000 feet radius of the now abandoned North Anna Un i t 3 containment.

• Exercise -A test of the response capabilities of the Emergency Organization that permits the evaluation of training and response to a given situation.

Exercises are conducted in accordance with pre-planned scenarios with defined objectives.

• General Emergency

-Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or security events that result in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed Environmental Protection Agency Protective Action Guideline exposure levels offsite for more than the immediate site area.

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

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

• Interim -A temporary or provisional emergency response position or facility which is augmented or transferred as resources become available.

NAEP Page 1.4 Revision # TBD

• Joint Informat i on Center (JIC) -Designated facility from which official information concerning an emergency is provided to the media. The JIC is located at the Virginia State Police Administrative Headquarters in Chesterfield, Virginia.

• Local Counties -This term shall be used to denote the Counties of Louisa , Spotsylvania , Caroline , Orange , and Hanover in the approximate ten (10) mile emergency planning zone.

• Local Media Center (LMC) -This facility provides a near site location for official media releases. The Local Media Center is in the North Anna Nuclear Information Center.

• Nearsite -Within the Exclus i on Area , but beyond Protected Area.

• Notification of Unusual Event -Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

• Offsite -Beyond the Exclusion Area.

• Onsite -Within the Protected Area, (surrounded by security fence).

• Operational Support Center (OSC) -An assembly area that serves as the staging location for Damage Control Teams, the Fire Brigade , the First Aid Team, and the Search and Rescue Team.

• Primary Sector-The 22 1/2° sector which bounds the existing wind direction.

• Projected Dose -An estimated radioactive dose which affected population groups could potentially receive if no protective actions are taken.

• Protected Area (PA) -An area encompassed by physical barr i ers and to which access is controlled.

For the purposes of this plan, the Protected Area refers to the designated security area around the reactor and turbine buildings.

• Protective Action Guides (PAGs) -The projected dose to individuals in the general population or the dose rate which warrants taking protective actions.

• Protective Actions -Those emergency measures taken before or after an uncontrolled release of radioactive material has occurred for the purpose of preventing or min i mizing radiological exposure.

• Recovery Actions -Those actions taken after the emergency to restore the station as nearly as possible to its pre-emergency condition.

• Rem (Roentgen Equivalent Man) -A unit of radiation dose that relates exposure to the biological effects of the exposure (absorbed exposure or dose). A unit related to the rem is the millirem (mrem). 1 mrem = 1/1000 rem.

• Restricted Area -Any area where access is controlled for the purpose of radiation protection.

• Semi-annual

-Occurring once during each of the first and last six months of the calendar year.

• Site -The Power Station proper and the 5000 foot radius exclusion area around the Power Station.

NAEP Page 1.5 Revision # TBD

• Site Area Emergency

-Events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevents effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed Environmental Protection Agency Protective Action Guideline exposure levels beyond the site boundary.

• Station Emergency Manager (SEM) -Designated onsite individual having the responsibility and authority for implementing the North Anna Emergency Plan.

• Technical Support Center -A facility located adjacent to Unit 1 Control Room which will be the central control center for the onsite emergency response organization after the on sh i ft staff has been augmented.

• Thyroid Committed Dose Equivalent (COE) -Radiation exposure to the thyroid through inhalation or ingestion of radioactive material assuming a 50 year exposure period from uptake.

• Total Effective Dose Equivalent (TEDE) -The sum of external and internal dose.

1.1 ACRONYMS

AND ABBREVIATIONS AC ARD Asst. cc Ce COE CEDE CERC CFR CH COVEOP cpm CR Cs CSD CTS eves DBE DC DOE DEGON DEPT. DOE EAD EALs EAS ECCS EDE e.g. EMO ENS EOC EOD EOF EPA Alternating Current Automatic Ringdown Line Assistant Cubic Centimeter Cerium Committed Dose Equivalent Committed Effective Dose Equivalent Corporate Emergency Response Center Code of Federal Regulations Charging System Commonwealth of Virgin i a Emergency Operations Plan Counts per minute Control Room Ces i um Cold Shutdown Current Technical Specifications Chemical Volume Control System Design Basis Earthquake Direct Current Deep Dose Equivalent Decontaminate Department Department of Energy Emergency Administrative Director Emergency Action Levels Emergency Alert System Emergency Core Cooling System Effective Dose Equivalent For example [From Latin exempli gratia] Emergency Maintenance Director NRC Emergency Notification System Emergency Operations Center Emergency Operations Director Emergency Operations Facility Environmental Protection Agency NAEP Page 1.6 Revision # TBD -1 EPC EPIPs EPZs EROS ERF ERGs ERO etc. ETD EWS F FEMA FRMAC FRMAP FSRC ft GOVT. gpm HP HPN HRSS HSD IAW i.e. IEIN 1/0 ISFSI ITS JOG JIC Kl Kr KW LAN LCO Emergency Procedures Coordinator Emergency Plan Implementing Procedures Emergency Planning Zones Emergency Response Data System Emergency Response Facility Emergency Response Guidelines Emergency Response Organization et cetera Emergency Technical Director Early Warning System Fahrenheit Federal Emergency Management Agency Federal Radiological Monitoring and Assessment Center Federal Radiological Monitoring and Assessment Plan Facility Safety Review Committee Feet Government Gallons per minute Health Physics Health Physics Network (Communications System) High Radiation Sampling System Hot Shutdown Iodine In accordance with That is [From Latin id est] Inspection and Enforcement Information Notice (NRC) lnpuVOutput Independent Spent Fuel Storage Installation Improved Technical Specifications Job Demonstration Guide Joint Information Center Potassium Iodide Krypton Kilowatt Local Area Network License Condition of Operation NAEP Page 1.7 Revision # TBD LMC LOCA LW MCL MCVH MIDAS mph mR/hr MSL Mwe MWt N/A NAEP NANIC NAPS NDT NEP NRG NSSS NUREG QBE ODCM OPX osc PAGs PAR PBX PCS Pk. PLS PMCL PORV psi , psia , psig RAA RAC Local Media Center Loss of Coolant Accident Liquid Waste System Management Counterpart Link Medical College of Virginia Hospital Meteorological Information and Dose Assessment System Miles per hour Millirem per hour Mean Sea Level Megawatt electric Megawatt thermal Not applicable North Anna Emergency Plan North Anna Nuclear Information Center North Anna Power Station Nil Ductil i ty Transition Nuclear Emergency Preparedness Nuclear Regulatory Commission Nuclear Steam Supply System NRG Report Operating Basis Earthquake Offsite Dose Calculation Manual Off-Premises exchange (Communications System) Operational Support Center (Onsite Operations Assembly Area) Protective Action Guides Protective Action Recommendation Private Branch exchange (Communications System) Plant Computer System Package Plus Local Support Protective Measures Counterpart Link Power Operated Relief Valve Pounds per square inch , psi absolute , psi guage Remote Assembly Area Radiological Assessment Coordinator NAEP Page 1.8 Revision # TBD RAD , Rad , rad RCP RCS Rem RERP R/hr RHR RIC RM , RMS RO RPS RSCL Ru RVLIS Rx SCBA SEM SI SN SONET SPDS SRO sssc STA SW Te TR T.S., Tech Specs TEDE THY TLD TSC µCi UFSAR UHF NAEP Page 1.9 Revision # TBD Radiological Assessment Director , radiation or radiological depending on context Reactor Coolant Pump Reactor Coolant System Roentgen Equivalent Man Radiological Emergency Response Plan Roentgen per hour Residual Heat Removal Richmond International Concourse (Airport)

Radiation monitor or Radiation Monitoring System depending on context Reactor Operator Radiation Protection Supervisor Reactor Safety Counterpart Link Ruthenium Reactor Vessel Level Indication System Reactor Self contained breathing apparatus Station Emergency Manager Safety Injection Serial number Synchronous Optical Network Safety Parameter Display System Senior Reactor Operator Sealed Surface Storage Cask Shift Technical Advisor Service Water system Tellurium Technical Requirement (from Technical Requirements Manual) Technical Specification(s)

Total Effective Dose Equivalent Thyroid Thermoluminescent Dosimeter Technical Support Center Micro (µ) Curie Updated Final Safety Analysis Report Ultrahigh frequency (radio)

U.S. V vcu VCUMC VDEM VG VPAP WAN Xe X/Q United States Volts Virginia Commonwealth University Virginia Commonwealth University Medical Center Virginia Department of Emergency Management Vents -Gaseous Virginia Power Administrative Procedure Wide Area Network Xenon Chi/Q; Dilution and dispersion factor , seconds per cubic meter NAEP Page 1.10 Revision # TBD Part 2.1 2.2 2.3 Subject Site Specifics Emergency Plan NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 2 SCOPE AND APPLICABILITY North Anna Hydroelectric Unit NAEP Page 2.1 Revision # TBD Page No. 2.2 2.2 2.3

2.0 SCOPE

AND APPLICABILITY 2.1 SITE SPECIFICS NAEP Page 2.2 Revision # TBD The North Anna Power Station consists of two units , each of which includes a three loop pressurized light water reactor , nuclear steam supply system (NSSS) and turbine generator furnished by Westinghouse Electric Corporation.

The balance of the stat i on was designed and constructed by the Company with the assistance of its ArchitecVEngineer , the Stone and Webster Engineering Corporation. Each reactor unit design output is limited to maximum power level stated in the current Operating License. The un i ts are located on a peninsula on the southern shore of Lake Anna in Louisa County approximately 40 miles North Northwest of Richmond , Virginia; 38 miles East of Charlottesville , Virginia; and 24 miles Southwest of Fredericksburg, Virginia. Cooling water , contained by an earthen dam structure , is obtained from the 17 mile long North Anna Reservoir.

An Independent Spent Fuel Storage Installation (ISFSI) is located on the plant site. 2.2 EMERGENCY PLAN The North Anna Power Station Emergency Plan (the Plan) describes the organization , facilities, emergency response measures , and functional interfaces with offsite agencies which can be used to respond to a broad range of defined emergencies. The organization has well defined responsibilities and specific authorities which provide for effective control and coordination of the emergency response , both onsite and offsite. The organization is augmented , as required , to address situations with the most serious potential consequences.

The Plan is formulated for compatibility with existing local , State , and Federal response organizations which may render emergency assistance.

A coordinated response effort between the company and other agencies supports the mutual goals of protecting public health and safety and of minimizing damage to both public and private properties. The basic purposes of the Plan are as follows: 1) To define potential types of emergencies

2) To establish an organization for managing an emergency; 3) To provide measures for coping with an emergency; 4) To provide facilities from which to perform selected measures; 5) To provide for a recovery program following an emergency; and , 6) To provide methods for maintaining the Plan active and current. Emergency Plan Implementing Procedures (EPIPs) provide instructions for accomplishing the provisions established in the Plan. The procedures guide the classification of the emergency , provide for offsite notifications , and activation of the full response organization. They also provide techniques for estimating the consequences of offsite releases and making recommended Protective Action Recommendations.

NAEP Page 2.3 Revision # TBD The Plan satisfies the emergency plan requirements for the North Anna ISFSI under prov i sions of Title 10 of the Code of Federal Regulations , Part 72 , Subpart B , Section 32 , Subsection (c). 2.3 NORTH ANNA HYDROELECTRIC UNIT In addition to the North Anna Emergency Plan , an Emergency Action Plan has been prepared for the North Anna Hydroelectric Plant. The North Anna Hydroelectric Plant , a small hydroelectric generating unit of 855KW capacity , is operated by Dominion and located on the North Anna River at the Lake Anna Dam (approximately

5.5 miles

Southeast of the North Anna Power Station). I The North Anna Hydroelectric Plant Emergency Action Plan was prepared to conform with the provisions of Title 18 of the Code of Federal Regulations , Part 12 , Subpart C , and was developed in consultation and cooperation with Federal , State , and local agencies responsible for public health and safety. The action Plan includes provisions for notifying State and downstream counties that may be affected by a classified project (dam) emergency.

It also sets forth procedures to be followed by station personnel to control the emergency and to notify the appropriate authorities.

In order to meet the requirements of 18 CFR Part 12 , Subpart C , provisions for operation of spillway equipment concurrent with an incident at North Anna Power Station is addressed as part of this plan. Should a (nuclear) station emergency occur , the Auxiliary Operator(s) shall remain at the dam to ensure proper operation of spillway gates , unless contacted by Security or Operations to evacuate because of safety reasons.

Part 3.0 Subject NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 3

SUMMARY

OF EMERGENCY PLAN Summary of Emergency Plan NAEP Page 3.1 Revision # TBD Page No. 3.2 3.0

SUMMARY

OF EMERGENCY PLAN NAEP Page 3.2 Revision # TBD Types of emergencies are divided into four classifications which cover a broad spectrum of potential occurrences. The classifications range from a "Notification of Unusual Event" , in which offsite officials are notified of an unusual condition , through "General Emergency ," in which onsite and offsite evacuation may be required and a major state of emergency exists. This classification scheme is compatible with existing State and local plans. An emergency response organization is established with specific duties and responsibilities defined , and points of contact between onsite and offsite supporting agencies are designated.

Augmentation of the emergency organization will occur at "Alert" and higher levels. Provisions for prompt notification of State , Local and Federal agencies are established and include pre-planned information which may be required for offsite agency response. Methods and procedures provide corrective and protective actions including evaluation of the operability of the unaffected unit. The use of protective equipment , protective action guides and exposure limits are also pre-specified. The facilities available for assessment and management of the emergency consist of onsite and offsite response facilities , communication systems , and portable or fixed equipment and systems for detection and measurement of those parameters causing or resulting from the emergency.

Medical facilities are also available.

Provisions are provided for public information activities , including development and issuance of press releases , media briefings, and responding to public inquiries. A recovery program describes the organization and procedural approach required to re-start the affected unit. The recovery program provides guidance for relaxing protective measures that have been instituted and requires the periodic estimation of total population exposure.

The Emergency Plan and Emergency Plan Implement i ng Procedures are reviewed annually. The Facility Safety Review Committee (FSRC) shall evaluate the review and may provide additional recommendations as necessary.

Periodic drills and exercises involving communications , fire-fighting, radiological monitoring and Health Physics activities are routinely conducted. A joint exercise involving participation by State and local response agencies will be held on even-numbered years at North Anna (on odd-numbered years , the State participates at Surry) to ensure all major elements of the Plan are tested within an eight year period. Federal response agencies may also participate in these joint exercises. Critiques of each implementation of the Plan allow for critical reviews of technique , methods , and shortcomings.

Improvements will be factored into the Plan and/or Implementing Procedures through revisions.

Part 4.0 4.1 4.2 4.3 4.4 Subject NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 4 EMERGENCY CONDITIONS Emergency Conditions Spectrum of Postulated Accidents Emergency Classification System State and Local County Emergency Classification System Requirements For Written Summa r ies of Emergency Events NAEP Page 4.1 Revision # TBD Page No. 4.2 4.2 4.3 4.8 4.8

4.0 EMERGENCY

CONDITIONS NAEP Page 4.2 Revision # TBD The following guidelines describe the criteria used by station personnel in classify i ng or determining the type of an emergency.

The types of potential accidents or emergencies can be numerous and vary in magnitude. Accordingly , the classification system is wide-ranged , although flexible and straight forward. The four classifications are defined in accordance with Appendix 1 of NU REG 0654 , "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." The classification system is not intended to include minor deviations during normal operation.

Furthermore , it may be discovered that an event or condition , which met the classification criteria , had existed , but that the basis for the emergency class no longer exists at the time of discovery. For example, the event may have rapidly concluded or been discovered during a post-event review. As discussed in NUREG-1022, "Event Reporting Guidel i nes: 10 CFR 50.72 and 50.73" (Revision 1), actual declaration of an emergency class is not necessary in these circumstances , although notification to the Nuclear Regulatory Commission and Virginia Department of Emergency Management (VDEM) is warranted.

4.1 SPECTRUM

OF POSTULATED ACCIDENTS The spectrum of emergencies peculiar to nuclear power stations range from accidents with minor implications on health and safety to the postulation of major occurrences resulting in the release of significant quantities of radioactive material.

Examples of minor accidents include unplanned or uncontrolled releases of small amounts of radioactive material in excess of allowable limits as well as equipment malfunctions.

Major occurrences , though not expected to take place , have been postulated for planning and design purposes because their consequences could include the potential for release of significant amounts of radioactive material.

The range of conditions in Appendix 1 to NUREG-0654 and Section 15 of the North Anna Updated Final Safety Analysis Report (UFSAR) have been included in the classification system of this Plan. Of the Condition IV -Limiting Faults analyzed in the UFSAR, three are considered to have the potential for releasing significant amounts of radioactivity. These are the loss of coolant accident , the steam generator tube rupture accident and the fuel handling accident.

The nature of these three accidents is such that a safety analysis can produce results which vary considerably in the radiological consequences.

The analysis results depend on assumptions used concerning such items as the status of primary coolant radioactivity content , meteorological conditions , or performance of station safety systems. The UFSAR makes very conservative estimates of the consequences. The Emergency Plan Implementing Procedures are written in anticipation of having to contend with these worst case consequences.

4.2 EMERGENCY

CLASSIFICATION SYSTEM NAEP Page 4.3 Revision # TBD Emergency conditions which may develop will be categorized as one of the following emergency classifications (defined in Section 1 of this plan): 1. Notification of Unusual Event. 2. Alert. 3. Site Area Emergency.

4. General Emergency.

The Notification of Unusual Event classification requires notification of appropriate offsite support groups and station management personnel that an abnormal condition exists at the station. The purpose of this notification is to increase the awareness of key offsite support organizations and station management of a condition which can currently be managed by the onsite resources , but which could escalate to a more serious condition. The on-shift operations personnel are assigned response tasks in accordance with the pre-augmentation organization responsibilities defined in Section 5 of this plan. The Alert classification is indicative of a more serious condition which has the potential for radioactive release. As a result , the emergency response organ i zation is notified to augment onsite resources and activate emergency response facilities. The Site Area Emergency classification reflects conditions where some sign i ficant radiation releases are likely or are occurring , but where a core melt situation is not currently indicated. In this situation, there would be full mobilization in the nearsite environs of monitoring teams and associated communications.

A Site Area Emergency can be declared for reasons other than radiological releases.

The General Emergency class i fication is indicative of actual or imminent substantial core degradation or melting with the potential for loss of containment , or non-radiological events which could endanger public health and/or safety. Within fifteen minutes of declaring a General Emergency , predetermined protective action recommendations will be made to the State based on plant and meteorological conditions. Tables 4.1 -4.4 list the initiating conditions for each emergency classification. The Emergency Action Level Matrix groups these conditions by event category for easy reference and identification. For each condition , specific indications available from instruments and unit operating response are defined in the matrix to confirm that the proper thresholds have been met for declaring a given classification. Once indications are available to plant operators that an emergency action level has been exceeded , the event is promptly assessed and classified, and the corresponding emergency classification level is declared. This declaration occurs as soon as possible and within 15 minutes of when these indications become available.

TABLE 4.1 INITIATING CONDITIONS:

NOTIFICATION OF UNUSUAL EVENT NAEP Page 4.4 Revision # TBD NOTE: The alpha-numeric designator , [AAN], preceding each initiating condition below , indicates the Emergency Action Level Identifier category , emergency classification and subcategory number; respectively.

Recognition Category C -Cold Shutdown/Refueling System Malfunction (Cold Conditions (RCS .s. 200°F) only)) CU1 a AC power capability to emergency busses reduced to a single power source for greater than 15 minutes such that any additional single failure would result in loss of all AC power to emergency busses CU 1 b Unplanned loss of required DC power for greater than 15 minutes CU2 Unplanned loss of RCS inventory with irradiated fuel in the Reactor Vessel CU3 Unplanned loss of decay heat removal capability with irradiated fuel in the Reactor Vessel CU4 Unplanned loss of all onsite or offsite communications capabilities CU5 RCS leakage CU6 Inadvertent cr i ticality Recognition Category E -Independent Spent Fuel Storage Installation (ISFSI) EU1 Damage to a loaded cask confinement boundary Recognition Category F -Fission Product Barriers (Hot Conditions (RCS > 200 °F) only)) FU1 Any loss or any potential loss of Containment Recognition Category H -Hazards HU1 Natural or destructive phenomena affecting the Protected Area or Main Dam HU2 Fire or explosion within the Protected Area boundary HU3 Release of toxic , corrosive , asphyxiant or flammable gases deemed detrimental to normal operation of the plant HU4 Confirmed security condition or threat which indicates a potential degradat i on in the level of safety of the plant HU5 None HU6 Other conditions existing which in the judgment of the SEM warrant declaration of a NOUE Recognition Category R -Abnormal Radiological Release / Radiological Effluent RU 1 a Any unplanned release of liquid radioactivity to the environment that exceeds two times the radiological effluent Technical Specifications for 60 minutes or longer RU 1 b Any unplanned release of gaseous radioactivity to the environment that exceeds two times the allocated radiological effluent ODCM limits for 60 minutes or longer RU2 Unexpected increase in plant radiation Recognition Category S -System Malfunction (Hot Conditions (RCS >200°F) only)) SU1 Loss of all offsite power to emergency busses for greater than 15 minutes SU2 None SU3 Inability to reach required shutdown within Technical Specification limits SU4a Unplanned loss of most or all safety-related structures , systems and components annunciation or indication in the Control Room for greater than 15 minutes SU4b Unplanned loss of all onsite or offsite communications capabilities SU5 Fuel clad degradation SU6 RCS leakage for 15 minutes or longer SU? Inadvertent criticality TABLE 4.2 INITIATING CONDITIONS:

ALERT Recognition Category C -Cold Shutdown/Refueling System Malfunction (Cold Conditions (RCS :s 200°F} only)) Loss of all offsite power and loss of all onsite AC power to emergency busses Loss of RCS inventory NAEP Page 4.5 Revision # TBD CA1 CA2 CA3 CA4 CA5 CA6 Inability to maintain plant in cold shutdown with irradiated fuel in the Reactor Vessel None None None Recognition Category F -Fission Product Barriers (Hot Conditions (RCS> 200°F) only)) FA 1 Any loss or any potential loss of either Fuel Clad or RCS Recognition Category H -Hazards HA 1 Natural or destructive phenomena affecting a plant safe shutdown area HA2 Fire or explosion affecting the operability of plant safety-related structures , systems or components required to establish or maintain safe shutdown HA3 Access to a safe shutdown area is prohibited due to release of toxic , corrosive , asphyxiant or flammable gases which jeopardize operation of systems required to maintain safe operations or safely shutdown the reactor HA4 Hostile action within the Owner Controlled Area or airborne attack threat HA5 Control Room evacuation has been initiated HA6 Other conditions existing which in the judgment of the SEM warrant declaration of an Alert Recognition Category R -Abnormal Radiological Release/ Radiological Effluent RA 1 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 200 times the radiological effluent Technical Specifications for 15 minutes or longer RA2a Damage to irradiated fuel or loss of water level that has or will result in the uncovering of irradiated fuel outside the Reactor Vessel RA2b Release of radioactive material or increases in radiation levels within the facility that impedes operation of systems required to maintain safe operations or to establish or maintain cold shutdown Recognition Category S -System Malfunction (Hot Conditions (RCS >200 °F) only)) SA 1 AC power capability to emergency busses reduced to a single power source for greater than 15 minutes such that any additional single failure would result in loss of all AC power to emergency busses SA2 Automatic trip fails to shutdown the reactor and the manual actions taken from the reactor control console are successful in shutting down the reactor SA3 None SA4 Unplanned loss of most or all safety-related structures , systems and components annunciation or indication in Control Room with EITHER (1) a significant transient in progress , OR (2) compensatory non-alarming indicators are unavailable SA5 None SA6 None SA? None TABLE 4.3 INITIATING CONDITIONS:

SITE AREA EMERGENCY Recognition Category C -Cold Shutdown/Refuel System Malfunction (Cold Conditions (RCS .s. 200°F) only)) CS1 None CS2 Loss of Reactor Vessel inventory affecting core decay heat removal capability CS3 None CS4 None CS5 None CS6 None Recognition Category F -Fission Product Barriers {Hot Conditions (RCS> 200°F) only)) FS 1 Loss or potential loss of any two barriers Recognition Category H -Hazards HS1 None HS2 None HS3 None HS4 Hostile action within the Protected Area NAEP Page 4.6 Revision # TBD HS5 Control Room evacuation has been initiated and plant control cannot be established HS6 Other conditions existing which in the judgment of the SEM warrant declaration of Site Area Emergency Recognition Category R -Abnormal Radiological Release / Radiological Effluent RS1 Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mRem TEDE or 500 mRem thyroid COE for the actual or projected duration of the release RS2 None Recognition Category S -System Malfunction

{Hot Conditions

{RCS >200 °F) SS1a Loss of all offsite power and loss of all onsite AC power to emergency busses SS 1 b Loss of all vital DC power SS2 Automatic trip fails to shutdown the reactor and manual actions taken from the reactor control console are not successful in shutting down the reactor SS3 None SS4 Inability to monitor a significant transient in progress SS5 None SS6 None SS7 None TABLE 4.4 INITIATING CONDITIONS:

GENERAL EMERGENCY Recognition Category C -Cold Shutdown/Refuel System Malfunction (Cold Conditions (RCS~ 200°F) only)) CG1 None NAEP Page 4.7 Revision # TBD CG2 Loss of Reactor Vessel inventory affecting fuel clad integ r ity w i th Con t ainment challenged and irradiated fuel in the Reacto r Vessel CG3 None CG4 None CG5 None CG6 None Recognition Category F -Fission Product Barriers {Hot Conditions (RCS > 200 "F) only)) FG1 Loss of any two barriers AND Loss or potential loss of third barrier Recognition Category H -Hazards HG1 None HG2 None HG3 None HG4 Hostile act i on resulting in loss of physical control of the facility HG5 None HG6 Other conditions existing which in the judgment of the SEM warrant declaration of General Emergency Recognition Category R -Abnormal Radiological Release / Radiological Effluent RG1 Offsite dose resulting from an actual or imminent r elease of gaseous rad i oactivity exceeds 1000 mRem TEDE or 5000 mRem thyroid COE for the actual or projected duration of the release using actual meteorology RG2 None Recognition Category S -System Malfunction (Hot Conditions (RCS >200F) SG 1 P r olonged loss of all offsite power and prolonged loss of all onsite AC power to emergency busses SG2 Automatic trip and all manual actions fail to shutdown the reactor and ind i cation of an extreme SG3 SG4 SG5 SG6 SG7 challenge to the ability to cool the core exists None None None None None NOTE: The appropriate Protective Action Recommendations for the preceding conditions MUST BE provided to the State w i thin 15 minutes follow i ng the declaration of a General Eme r gency.

4.3 STATE

AND LOCAL COUNTY EMERGENCY CLASSIFICATION SYSTEM NAEP Page 4.8 Revision # TBD The Commonwealth of Virginia Emergency Operations Plan (COVEOP) emergency classification system defines two levels based on projected radiological doses resulting from the release of radioactive materials from a fixed nuclear facility.

The company will provide projected radiological doses based on plant parameters and meteorological conditions. Provisions are in the COVEOP for dose assessments within 50 miles of the station for the ingestion of radioactive material via the food pathway. Thresholds used for protective action determination are based on projected doses recommended in Table 2.1 of EPA-400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" , as implemented by the Commonwealth of Virginia.

4.4 REQUIREMENTS

FOR WRITTEN SUMMARIES OF EMERGENCY EVENTS NUREG-0654, Appendix 1 establishes the guidance for providing written summaries of emergency events to offsite authorities.

A written summary is provided to VDEM following activation of the North Anna Emergency Plan. The schedule for submitting the written summary for a Notification of Unusual Event is within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following declaration.

For any other classification, the schedule for submitting the written summary is within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following termination. This schedule was established with the concurrence of VDEM and subsequent notification to the NRG (reference Letter, Serial Number 84-302, dated 5-31-84).

Part 5.0 5.1 5.2 5.2.1 5.2.1.1 5.2.1.2 5.2.1.3 5.2.1.4 5.2.1.5 5.2.1.6 5.2.1.7 5.2.1.8 5.2.1.9 5.2.1.10 5.2.1.11 5.2.1.12 5.2.1.13 5.2.1.14 5.2.1.15 5.2.1.16 5.2.1.17 5.2.1.18 5.2.1.19 5.2.1.20 5.2.1.21 5.2.1.22 5.2.1.23 NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 5 ORGANIZATIONAL CONTROL OF EMERGENCIES Subject Organizational Control of Emergencies Normal Station Organization Emergency Response Organization Station Emergency Position and Team Descriptions Station Emergency Manager Emergency Communicator Emergency Procedures Coordinator Emergency Operations Director Emergency Maintenance Director Emergency Technical Director Shift Technical Advisor Emergency Administrative Director Radiological Assessment Director Radiation Protection Supervisor Operational Support Center Director (OSC Director)

OSC Support Team Technical Support Team Chemistry Team Administrative Support Team Security Team Dose Assessment T earn Offsite Monitoring Team Evacuation Monitoring Team In-Plant Monitoring Team Sample Analysis Team Personnel Monitoring And Decontamination Team Onsite (Out of Plant) Monitoring Team NAEP Page 5.1 Revision # TBD Page No. 5.4 5.4 5.4 5.5 5.6 5.7 5.7 5.7 5.7 5.7 5.8 5.8 5.8 5.8 5.9 5.9 5.9 5.9 5.9 5.10 5.10 5.10 5.10 5.10 5.10 5.11 5.11 5.2.1.24 5.2.1.25 5.2.1.26 5.2.1.27 5.2.2 5.2.2.1 5.2.2.2 5.2.2.3 5.2.2.4 5.2.2.5 5.2.2.6 5.2.2.7 5.2.2.8 5.2.2.9 5.2.2.10 5.2.2.11 5.2.2.12 5.2.2.13 5.2.2.14 5.3 5.3.1 5.3.1.1 5.3.1.2 5.3.1.3 5.3.1.4 5.3.1.5 5.3.2 5.3.3 Fire Brigade First Aid T earn Damage Control Team Search and Rescue Team Corporate Emergency Positions and Team Descriptions Corporate Response Manager Technical Support Manager Resource Manager Nuclear News Manager Chief Technical Spokesperson Executive Liaison Emergency Plan Advisor Operations Support Coordinator Operations Support T earn Radiological Assessment Coordinator Accident Assessment Team Resource T earn News Team Joint Information Center Support Team Augmentation of Emergency Response Organization Notification and Response Environmental Monitoring Logistics Support for Emergency Personnel Technical Support for Planning and Re-entry/Recovery Operations Interface with Governmental Authorities Release of Information to News Media Vendor and Supplemental Personnel Local Services Support NAEP Page 5.2 Revision # TBD 5.11 5.11 5.11 5.11 5.12 5.12 5.12 5.12 5.12 5.12 5.13 5.13 5.13 5.13 5.13 5.13 5.13 5.13 5.14 5.14 5.14 5.14 5.14 5.14 5.15 5.15 5.15 5.16 5.4 Coordination with Participating Government Agencies 5.16 5.4.1 Commonwealth of Virginia Department of Emergency Management (VDEM) 5.18 5.4.2 Commonwealth of Virginia Department of Health (VDH) 5.18 5.4.3 5.4.4 5.4.5 5.4.6 Additional State Agency Support Louisa County Spotsylvania , Caroline , Hanover , and Orange Counties Counties and C i ties Within the Fifty Mile Ingestion Emergency Planning Zone 5.18 5.18 5.19 5.19

5.4.7 Table

5.1 Table 5.2 Table 5.3 Figure 5.1 Figure 5.2 Figure 5.3 Figure 5.4 Figure 5.5.a Figure 5.5.b Figure 5.5.c Figure 5.5.d Federal Radiological Monitoring and Assessment Center (FRMAC) Operations Plan Minimum Shift Manning Requirements Emergency and Recovery Corporate Response Required for Nuclear Station Emergencies (Alert Status And Above) Cities and Counties With i n the North Anna 50 Mile Emergency Planning Zone Station Emergency Organization Prior to Augmentation Station Emergency Organization Following Augmentation Station to Support Group I nterface Prior to Augmentation of the Onsite Emergency Organization Station to Support Group Interface After CERC Activation Technical Support Center Organization Operational Support Center Organization Radiation Protection Organization Corporate Emergency Response Center Organization NAEP Page 5.3 Revision # TBD 5.19 5.21 5.24 5.25 5.26 5.27 5.28 5.29 5.30 5.31 5.32 5.33

5.0 ORGANIZATIONAL

CONTROL OF EMERGENCIES NAEP Page 5.4 Rev i sion # TBD An i ntegral part of th i s Emergency plan i s to assure that classificat i ons of Not i fication of Unusual Event , Alert , Site Area Emergency , and General Eme r gency are consistently made in a timely manner. All employees are instructed to contact the Shift Manager to report any emergency. This notification and the information available to the Shift Manager in the Control Room enable a timely classification of the emergency and subsequent act i ons. The Shift Manager or Unit Supervisor initially acts in the capacity of the Stat i on Emergency Manager (SEM) and takes actions as outl i ned i n the EPIPs. If required by the emergency classification , or if deemed appropriate by the Station Emergency Manager , emergency response personnel will be notified and instructed to report to their emergency response locations. The Shift Manager is r elieved as Station Emergency Manager when the Site Vice President or his designated alternate reports to the station (normally to the Control Room) and is updated as to the status of the un i t , the emergency act i ons taken , and the current status of the emergency. Following this relief , the Station Emergency Manager may relocate to the onsite Technical Support Center (TSC). The Corporate Emergency Response Cen t er (CERC) is act i vated concurrent with the TSC. The CERC is staffed by corporate personnel , including the Corporate Response Manager and Technical Support Manager , who direct the act i vit i es of this facility.

The Technical Support Manager is responsible for ensuring the CERC communicates emergency status to the State and local governments , directs the efforts of the offsite mon i toring teams , makes radiological assessments , recommending offsite protective measures to the State , and arranging for dispatch of any spec i al assistance or services requested by the station. The Corporate Response Manager has the ultimate authority to comm i t company resources and set policy as part of managing the long term recovery effort. 5.1 NORMAL STATION ORGANIZATION The Site Vice Pres i dent is ultimately responsible for the operation of the Station. The minimum staff required to conduct Station operation is ma i ntained at the station at all times. For purposes of the Emergency Plan , the on-shift manning is assumed to be on back-shift because the normal stat i on complement of pe r sonnel is only present during regular duty hours on scheduled work days. The basic shift (back-shift}

complement of personnel is comprised of Operations, Health Physics , Chemistry , and Security personnel with coverage by Maintenance on designated shifts. In addition , technical/engineering support is available on all shifts from the Shift Technical Adv i sor (STA). Station administrative procedures provide the details of the normal station organ i zation including reporting relationships. 5.2 EMERGENCY RESPONSE ORGANIZATION The first line of control in an emergency at North Anna Power Station lies with the on-shift personnel.

The shift complement is staffed with personnel qualified to take the initial actions necessary to respond to an emergency. The organizational relationship of the on-shift emergency organization prior to augmentation is shown in Figure 5.1. Coverage by the Chemistry Team and the Damage Control Team NAEP Page 5.5 Revision # TBD would be provided on an as needed basis. However , augmentation of the onsite emergency organization will specifically provide such coverage. Also , personnel assigned to the Search and Rescue Team , the First Aid Team , and the Fire Brigade may be assigned other functions until their services are required. The capability of the on-shift personnel to effectively manage an emergency is assured by the timely call out of supplementary emergency response personnel.

The capabilities of the assigned on-shift personnel are adequate to assess the condition of the affected unit(s) and take initial mitigative actions in accordance with emergency operating procedures including corrective actions necessary to implement procedures consistent with operations personnel training. Additionally, on-shift personnel make notifications to off-site authorities and initiate a call out of supplementary emergency response personnel as required.

The EPIPs are used to procedurally control these actions. A detailed analysis of on-shift personnel assigned emergency plan implementation functions was performed under provisions of 10 CFR 50 Appendix E Part IV.A.9. This analysis determined the staff complement listed in the on-shift column of Table 5.1 can adequately perform required emergency response actions in a timely manner until augmenting ERO staff is required to arrive. This analysis considered a spectrum of events , including UFSAR Condition IV events requiring augmented ERO response , a probable aircraft threat , a design basis threat , a fire requiring Control Room evacuation and remote shutdown , a station black out , etc. This staffing analysis is incorporated by reference as a part of this emergency plan. Should the Station Emergency Manager deem that additional emergency response personnel are needed or the emergency classification is upgraded to Alert or higher , he shall initiate the augmentation of the on shift Emergency Organization by instructing Station Security to commence callout of supplementary emergency response personnel.

Table 5.1 represents the minimum number of personnel that are required to augment emergency operations and the estimated response times of these personnel.

The responsibilities of the emergency response personnel assigned on shift and those who make up the augmentation crews meet the staffing functions identified in Table B-1 of NUREG-0654.

The numbers of emergency response personnel designated for both the on-shift and augmentation contingents meet or exceed the guidance.

Sufficient training has been provided for the on-shift personnel to ensure that the response actions needed to bring the affected unit(s) to a stable condition in preparation for the longer term recovery will be taken. If an emergency occurs on one of the two units , the Shift Manager or Unit Supervisor assumes the operational responsibility for the unaffected unit. This allows the other to assume the position of Station Emergency Manager until relieved.

Figure 5.2 shows the station emergency organization after full augmentation.

5.2.1 Station

Emergency Position and Team Descriptions The Station Emergency Organization, when fully implemented , will consist of at least the positions discussed below. Reporting relationships are as depicted in Figure 5.2. Additional personnel may be designated by Station Management as emergency responders providing special expertise deemed beneficial, but not mandatory , to the planned response. The individuals assigned as interim, primary and NAEP Page 5.6 Revision # TBD alternate responders for the emergency positions will be designated by Station Management based on the technical requirements of the position. Guidance for selection of emergency responders is provided in administrative procedures.

Designated ind i viduals will receive training in accordance with Section 8 of the North Anna Emergency Plan. 5.2.1.1 Station Emergency Manager The Station Emergency Manager (SEM) has the responsibility of managing and directing emergency operations during the course of the emergency.

The SEM initially operates from the Control Room and then transitions to the Technical Support Center. The SEM ultimately reports to the Corporate Response Manager, once augmented.

SEM responsibilities shall include , but not be limited to: 1) Classifying the emergency , 2) Authorizing notification to the N RC , State and local agencies of the emergency status , 3) Recommending protective measures , 4) Authorizing emergency exposure limits , 5) Activating emergency personnel and facilities , 6) Reducing power or shutting down both reactors , 7) Committing company funds as necessary , 8) Acquiring emergency equipment or supplies , 9) Ordering site evacuation , 10) Restricting access to the site , 11) Notifying company management , 12) Implementing work schedules , and 13) Directing onsite emergency activ i ties. Items 1 through 4 above MAY NOT BE DELEGATED.

The CERC Technical Support Manager will be responsible for assuming the non-delegatable responsibilities of notifying State and local governments of the emergency status , and for recommending offsite protective measures to the State.

5.2.1.2 Emergency Communicator NAEP Page 5.7 Revision # TBD The Emergency Communicators report to the SEM in the Control Room prior to activation of the TSC , and to the TSC after its activation.

The duties of the Emergency communicators are to initially notify and periodically update the Emergency Operations Centers of the counties within the 10-mile Emergency Planning Zone , the Virginia Emergency Operations Center (VEOC), and the NRG. The CERC staff becomes responsible for notification of State and local governments. 5.2.1.3 Emergency Procedures Coordinator The Emergency Procedures Coordinator (EPC) will report to the SEM in the Control Room and then relocates to the TSC as part of the augmentation of the on-shift emergency organization.

The responsibilities of the EPC include: 1) Assisting the SEM in assuring all appropriate procedures and responses are initiated , 2) Monitoring emergency action level entry conditions , 3) Assisting the SEM in maintaining a working document of the controlling EPIP procedures and other appropriate procedures , 4) Assisting the SEM in obtaining all procedures generated as a result of the emergency , 5) Reviewing procedures for accuracy and completeness , and 6) Assisting in the preparation of these documents for review by the Facility Safety Review Committee.

5.2.1.4 Emergency Operations Director The Emergency Operations Director (EOD) reports to the SEM in the Technical Support Center as part of the augmentation of the on-shift emergency organization.

His duties include directing the activities of Operations personnel , advising the SEM on emergency operat i ons , and directing the development of procedures necessary for conducting emergency operations.

5.2.1.5 Emergency Maintenance Director The Emergency Maintenance Director (EMD) reports to the SEM in the TSC as part of the augmentation of the on-shift emergency organization. The EMD is responsible for advising the SEM on emergency maintenance activities including prioritization , status and providing interface with the Operational Support Center (OSC) Director (when necessary). 5.2.1.6 Emergency Technical Director The Emergency Techn i cal Director (ETD) reports to the SEM in the TSC as part of the augmentation of the on-shift emergency organization. He directs the activities of the Technical Support Team. The Emergency Technical Director will analyze mechanical , electrical , instrumentation and control , hydraulic , thermodynamic , and reactor physics problems , and develop solutions to the problems. He shall provide technical support to the SEM and assist in developing procedures necessary for conducting emergency operations and ma i ntenance.

5.2.1.7 Shift Technical Advisor NAEP Page 5.8 Revision # TBD The Shift Technical Advisor (Control Room) will remain in the Control Room to advise the Shift Manager or Unit Supervisor on operations activities.

He also provides engineering support until the Technical Support Team is staffed. Shift Technical Advisor (STA) coverage is provided on a 24-hour per day , 7-days per week on-shift basis to enable timely assistance in the Control Room. 5.2.1.8 Emergency Administrative Director The Emergency Administrative Director (EAD) reports to the SEM in the TSC as part of the augmentation of the on-shift emergency organization.

He directs activities of the Administrative Support Team and advises the Station Emergency Manager on emergency First Aid, Fire Protection, Security , Administrative and Logistical Support activities.

He coordinates the acquisition of equipment, supplies, personnel , and other assistance needed to cope with the emergency. He also ensures that the TSC log keeper ma i ntains a chronological record of key events. 5.2.1.9 Radiological Assessment Director The Radiological Assessment Director (RAD) reports to the Station Emergency Manager in the Technical Support Center after relieving the interim director who was the Senior Radiological Protection representative on-site at the initiation of the emergency.

He directs the activities of the Radiation Protection Supervisor in maintaining the Radiation Protection Program on-site during an emergency.

He also directs the activities of the Dose Assessment Team and Offsite Monitoring Teams in determining offsite consequences of radiological releases until control is assumed by the Radiological Assessment Coordinator (RAC) at the CERC. Other duties of the Radiological Assessment Director are to provide the status of offsite releases to the Station Emergency Manager , to direct the activities of the Chemistry Team (following augmentation), to evaluate radiological conditions and recommend onsite and offsite protective actions to the Station Emergency Manager, to provide recommendations and Health Physics coverage for onsite corrective actions , to direct decontamination efforts, and to provide advice and monitoring for evacuation of on-site personnel.

5.2.1.10 Radiation Protection Supervisor The position of Radiation Protection Supervisor will be filled upon augmentation of the on-shift emergency organization.

The Radiation Protection Supervisor normally operates from the Station Health Physics office and reports to the Radiological Assessment Director. The Radiation Protection Supervisor directs the activities of the In Plant Monitoring Team, the Sample Analysis Team, the Personnel Monitoring and Decontamination Team, the Onsite (Out of Plant) Monitoring Team, and the Evacuation Monitoring Team. He will also provide radiological support , as needed, to the Fire Brigade , First Aid Team, Search and Rescue Team , and the Damage Control Team. Additional duties include evaluating onsite radiological conditions , ensuring that appropriate monitoring and sampling is performed , checking that appropriate personnel monitoring is performed and personnel exposures are evaluated, and maintaining dose records.

NAEP Page 5.9 Revision # TBD He shall also recommend onsite protective measures to the Radiological Assessment Director and provide him with survey results and sample analysis results needed for offsite dose assessment.

5.2.1.11 Operational Support Center Director (OSC Director)

Upon augmentation of the on-site shift , the pos i tion of OSC Director will be manned. He will base his activities from the Operational Support Center and shall report to the Station Emergency Manager , normally through the EMO. The duties and responsibilities of the OSC Director include directing the activities of the Operational Support Team, planning , scheduling and material requisitioning in support of damage control tasks and development of procedures necessary for conducting emergency maintenance.

The OSC Director is also responsible for dispatch and control of the Reserve Fire Brigade , the Reserve First Aid Team , the Damage Control Team , the Search and Rescue Team and standby operations personnel.

5.2.1.12 OSC Support Team The OSC Support Team will operate out of the OSC under the direction of the OSC Director after augmentation of the on-shift emergency organization.

The OSC Support Team plans required maintenance evolutions, develops emergency maintenance procedures , arranges for material acquisition , and can direct the efforts of the Damage Control Teams , if activated. 5.2.1.13 Technical Support Team The Technical Support Team will operate out of the TSC under the direction of the ETD after augmentation of the on-shift emergency organization.

The Team members include an Operational Advisor , a Reactor Engineer , a Mechanical and an Electrical Engineer.

The on-duty Shift Technical Advisor has the required training to provide technical support until the Team is fully manned. The Team shall assist the ETD in analyzing electrical , mechanical , instrumentation and control , chemistry , reactor physics , hydraulic and thermodynamic problems and in developing solutions to the problems.

The Team shall also assist in developing procedures necessary to deal with the emergency condition.

5.2.1.14 Chemistry Team The Chemistry Team , after augmentation , reports to the RAD/designee and operates out of the Chemistry area of the Station. The Chemistry Team will conduct liquid and gaseous sampling , and sample analysis , as directed. 5.2.1.15 Administrative Support Team The Administrative Support Team will assist the Emergency Administrative Director on emergency fire protection, security, administrative and logistical support activities. The Team will also provide clerical and records support. If the emergency is Security related , the Administrative Support Team Leader may report directly to the Station Emergency Manager. In a fire or first aid emergency , the Safety/Loss Prevention representative may transfer from the Administrative Support team and report directly to the Station Emergency Manager.

5.2.1.16 Security Team NAEP Page 5.10 Revision # TBD The Security Team reports to the EAD. The Team will maintain personnel accountability, provide site access control , and provide station security. The Team will also maintain liaison and communications with local law enforcement agencies in accordance with procedural guidelines or when directed to do so by the Station Emergency Manager. 5.2.1.17 Dose Assessment Team This Team will operate out of the TSC under the direction of the RAD. The Dose Assessment Team maintains contact with and transmits instructions to Offsite Monitoring Teams, performs offsite dose assessment calculations, and provides the Radiological Assessment Director with offsite release calculations and dose projections. The Team will also assign an individual to transmit Health Physics and environmental information to the NRG using the Health Physics Network (HPN) phone. The Dose Assessment Team Leader will report the results of the offsite releases and dose projections to date to the RAC. The Dose Assessment Team Leader will also inform the RAC of the locations of the Offsite Monitoring Teams and of the current data received from these teams. Control of Offsite Monitoring Teams and responsibility for making HPN notifications will transfer to the CERC. The Dose Assessment Team will then provide support to the RAD regarding onsite response and interface with the CERC. 5.2.1.18 Offsite Monitoring Teams These Teams will report to the Dose Assessment Team in the TSC or to the Accident Assessment Team in the CERC. These Teams will provide offsite monitoring and sample collection as directed.

5.2.1.19 Evacuation Monitoring Team This Team is under the direction of Radiation Protection Supervisor and is activated at the Remote Assembly Area only if a s i te evacuation is ordered. The duties of this Team include monitoring station personnel at the Remote Assembly Area following a site evacuation, collecting evacuated personnel dosimetry, and decontaminating personnel as necessary. 5.2.1.20 In-Plant Monitoring Team The In-Plant Monitoring Team reports to the Radiation Protection Supervisor in the Station Health Physics Office. This Team will perform monitoring and sample collection inside the protected area. The team will also provide monitoring services to the Search and Rescue Team , the Damage Control Team, the Fire Brigade , and the First Aid Team , if required. 5.2.1.21 Sample Analysis Team The Sample Analysis T earn reports to the Radiation Protection Supervisor in the Station Health Physics Office. The team shall analyze samples collected offsite as well as post accident liquid and gaseous samples.

5.2.1.22 Personnel Monitoring and Decontamination Team NAEP Page 5.11 Revision # TBD This Team reports to the RPS in the Station HP Office. The Team will monitor personnel , decontaminate personnel , and provide monitoring services to the Search and Rescue Team , the Damage Control Team , the Fire Brigade , and the First Aid Team , if required.

5.2.1.23 Onsite (Out of Plant) Monitoring Team This Team reports to the RPS and operates out of the Station HP Office. The team will perform monitoring and sample collection within the site boundary but outside the protected area. 5.2.1.24 Fire Brigade The Fire Brigade members arriving at the Station to augment the on-shift Fire Brigade will report to the Loss Prevention Coordinator in the OSC and remain there until their services are needed. Upon activation , the Team reports to the Loss Prevention Coordinator , Station Emergency Manager or responsible Emergency Director , as needed. The Fire Brigade will combat fires in accordance with the Station Fire Protection Program. The shift Fire Brigade members with other duties will not report to the OSC, but will remain in their normal duties unless called out to combat a fire. 5.2.1.25 First Aid Team The First Aid Team members reporting to the Station to augment the on-shift First Aid Team will report to the Loss Prevention Coordinator in the OSC and rema i n there until their services are needed. Upon act i vation , the Team reports to the Loss Prevention Coordinator , Station Emergency Manager or responsible Emergency Director , as needed. The Team will respond to first aid emergencies in accordance with the Station Administrative Procedures and in accordance with standard first aid practices.

The on-shift First Aid Team members will remain in their normal duties unless activated to respond to a first aid emergency. 5.2.1.26 Damage Control Team The Damage Control Team will report to the OSC Director.

When their support is required , the team will report to the EMO or the responsible emergency director as needed. The Damage Control Team will perform emergency assessment and repairs. The Team composition will be determined by the technical expertise required to address the specific problem. Personnel capable of dealing with mechanical , electrical, or instrumentation problems will be assigned to the Team. 5.2.1.27 Search and Rescue Team This Team will report to the OSC Director in the OSC until circumstances require their function to be performed. Upon activation , the Team will report to the SEM , the Safety/Loss Prevention representative or the designated Emergency Director as needed. Prior to arrival of augmentary personnel , an on-shift Fire Brigade Scene Leader will lead the Team. The Team members will be members of the Fire Brigade and the First Aid Team. The Search and Rescue NAEP Page 5.12 Revision # TBD Team will search for and rescue personnel following an explosion , a fire , or any other hazardous event. The Team can be used to locate personnel who are unaccounted for during an emergency.

5.2.2 Corporate

Emergency Position and Team Descriptions The CERC Emergency Organization , when fully implemented , will consist of at least the positions discussed below. Reporting relationships a r e as depicted in Figure 5.2. Additional personnel may be designated by corporate management as emergency responders providing special expertise deemed beneficial, but not mandatory , to the planned response. The individuals assigned as interim , primary and alternate responders for the emergency positions will be designated by corporate management based on the technical requirements of the position. Guidance for selection of emergency responders is provided in administrative procedures. The Joint Information Center (JIC) is activated in accordance with the Commonwealth of Virginia Radiological Emergency Response Plan. 5.2.2.1 Corporate Response Manager The Corporate Response Manager (CRM) assumes overall control and operation of the CERC , and is responsible for allocating the use of company resources to aid the affected station(s) in the m i tigation of and recovery from an accident.

The CRM works with state and federal agency representatives located in the CERC and approves press releases.

The CRM supervises the Station Emergency Manager, the Technical Support Manager , the Resource Manager , the Nuclear News Manager , the Chief Technical Spokesperson , the Executive Liaison and Emergency Plan Advisor. 5.2.2.2 Technical Support Manager The Technical Support Manager (TSM) reports to the CRM and is responsible for ensuring that prompt and accurate dose assessments are performed; notifying state and local governments of the emergency status and any changes in a timely manner; assessing and providing protective action recommendations to offsite authorities

ensuring that statements issued to the media are technically correct and factual; and working with the SEM to determine the need to escalate or de-escalate the emergency classification. The TSM supervises the Operations Support Team and Accident Assessment Team. 5.2.2.3 Resource Manager The Resource Manager (RM) reports to the CRM and i s responsible for logistical and administrative support for the CERC. The RM superv i ses the Resource Team. 5.2.2.4 Nuclear News Manager The Nuclear News Manager (NNM) reports to the CRM and is responsible for overall control for all media and public information functions.

The NNM supervises the News Team and coordinates with the JIC Support Team. 5.2.2.5 Chief Technical Spokesperson The Chief Technical Spokesperson (CTS) reports to the CRM and is responsible for serving as the official company spokesperson , responding to technical inquiries from the news media , and conducting press briefings.

The CTS supervises the JIC Support Team.

5.2.2.6 Executive Liaison NAEP Page 5.13 Revision # TBD The Executive Liaison (EL) reports to the CRM and i s responsible for interfacing with senior Dominion management with respect to event status. 5.2.2.7 Emergency Plan Advisor The Emergency Plan Advisor (EPA) reports to the CRM and is responsible for providing assistance with facility operations and interpretation of the North Anna Emergency Plan , including emergency action levels, emergency classifications , protective action recommendations , monitoring s i ren control system status , and interface with offsite response organizations.

5.2.2.8 Operations Support Coordinator The Operations Support Coordinator (OSC) reports to the TSM and is responsible for providing advice on unit conditions and methods being implemented to mitigate the incident , and assisting in the development of the Recovery Plan after incident mitigation. The OSC supervises the Operations Support Team. 5.2.2.9 Operations Support Team The Operations Support Team monitors plant conditions using the Plant Computer System (PCS), transmits notifications to the VEOC and local governments, maintains communications with the TSC , and maintains a log of significant events. 5.2.2.10 Radiological Assessment Coordinator The Radiological Assessment Coordinator (RAC) reports to the TSM and is responsible for directing performance of emergency dose calculations

directing field team radio operator activities

dispatching Offsite Field Team members , as necessary; tracking the dose of Offsite Field Team members; projecting offsite doses; obtaining weather forecasts , as necessary; comparing offsite survey data with offsite dose projections

formulating protective action recommendations (PARs); briefing the CERC staff and federal/state counterparts on radiological conditions and PARs; tracking the plume; and identifying any supplemental resources needed. The RAC supervises the Accident Assessment Team. 5.2.2.11 Accident Assessment Team The Accident Assessment Team will analyze core conditions and accident progression , develop dose projections , direct the movement and activities of Offsite Field Teams described in Section 5.2.1.18 , and establish the Health Physics Network (HPN) when requested by the NRG. 5.2.2.12 Resource Team The Resource Team will provide logistical and administrative support , including development of long-term staffing plans and and acquiring supplemental staff as appropriate (e.g., Telecommunications , Information Technology , Company Meteorologist , etc.). 5.2.2.13 News Team The News T earn will develop and coordinate review of press releases and other means of providing information to the public, and issue approved information.

5.2.2.14 Joint Information Center Support Team NAEP Page 5.14 Revision # TBD The Joint Information Center Support Team will assist the CTS by providing technical advice and interface with offsite response organization public informat i on staff at the JIC , when activated.

5.3 AUGMENTATION

OF EMERGENCY RESPONSE ORGANIZATION The Station Emergency Manager has the authority to request assistance from any organization which he deems necessary to mitigate the conditions causing the emergency. In addition , the Station Emergency Manager may request offsite assistance in fire fighting , rescue services, law enforcement , and medical support prior to augmentation of the onsite emergency organization (see Figure 5.3). The participating agencies and support services with whom emergency support services have been negotiated are listed in Appendix 10.1 of this Plan. If conditions at the Station require an Alert or higher classification, the CERC , TSC and OSC shall be activated. The facility activation goal for the TSC and OSC is approximately 60 minutes. The activation time goal for the CERC is within 75 minutes of the declaration of an Alert or higher emergency class , with activation defined as the assembly of required positions in the CERC and the CERC Corporate Response Manager declaring the facility activated. The Station Emergency Manager would normally forward information or request additional support through the Corporate Response Manager located in the CERC (See Figure 5.4). Additional resources shall be obtained through personnel assigned to the CERC. Those additional personnel directed to report to the site during the emergency shall report to the Station Emergency Manager for assignment.

Figures 5.5.a-d display minimum staff required for activation. 5.3.1 Notification and Response The emergency response organization (ERO) is notified to augment in the event of an Alert , Site Area Emergency or General Emergency. The following functions may be necessary for emergency mitigation and recovery:

5.3.1.1 Environmental Monitoring Provisions for obtaining additional environmental monitoring personnel shall be the responsibility of the CERC. 5.3.1.2 Logistics Support for Emergency Personnel The CERC Resources Manager will be responsible for all administration and logistics including accommodations , Corporate communications , pu r chasing , finance , commissary , sanitary , transportation , and security services.

5.3.1.3 Technical Support for Planning and Re-entry/Recovery Operations Technical support for recovery and subsequent re-entry would be directed by the Corporate Response Manager. Trained technical personnel are available in the areas of nuclear fuel management , water quality , air quality , engineering , health physics , and chemistry.

Additional technical support would be obtained from Surry Power Station , A/E , and NSSS vendor. Consulting services would be obtained as necessary.

NOT E: U pd ate of r efe r e n ces t o l egacy ve nd o r s i s b eyo nd th e sco p e of thi s li ce n se a m e ndm e nt r e qu es t. Technical support for recovery and subsequent re-entry wo NAEP Page 5.15 Revision # TBD by the Recovery Manager. Trained technical personnel a r e ava i lable in the areas of nuc ar fuel management , water quality , air quality , engineering , health physics , and chemistry. Additional tee nical support would be obtained from Su r ry Power Station , A/E, and NSSS vendor. Consulting services uld be obtained as necessary. 5.3.1.4 Interface with Governmental Authorities CERC management is responsible for contacting agencies when coordinat i ng mobilization of resources or requesting additional support. e CERC , once activated , serves as principal point of interaction between Station and governmental auth 5.3.1.5 Release of Information to News Media News releases shall be coordinated with the xternal Affairs Department.

The Chief Technical Spokesperson is responsible for meet i ng with the ews media. Releases will be coordinated with the appropriate governmental authorities. Briefings II be conducted at the Joint Information Center at the Virginia State Police Administrative Headquarter in Chesterfield , Virginia and , when activated , at the Local Media Center in the North Anna Nuclear lnfor tion Center (NANIC). 5.3.2 Vendor and Su Support will be obtained from th A/E , the NSSS vendor , and other consultants and vendors as needed to respond to the emergency nd recovery operations. Experienced personnel with in-depth expertise in Station design , engineeri and construction will be obtained to aid in solving critical technical problems. Th i s support is normally icited by the Corporate Response Manager or his representative. In the event of an emergency , Westinghouse (the NSSS vendor) will also be informed of the plant status. In addition , the Institute of Nuclear Power Operations can be contacted to provide sources of addit i onal support , if necessary. In addition , radiological count laboratory resources are available through the Commonwealth to respond to an emergency at the Station. These resources include those facil i t i es listed below. Estimated travel t i mes to the station are provided parenthetically

1. University of Virginia , Charlottesv i lle , VA (45 minutes) 2. Virginia Department of General Services , Division of Conso l idated Laboratory Services , Richmond , VA (75 minutes) 3. Virginia Commonwealth University Medical Cente r , Richmond , VA (75 minutes) 4. Newport News Shipbuilding

& Drydock , Newport News , VA (3 1/2 hours) 5. Virginia Department of Health , Off i ce of Radiological Health Mobile Laboratory (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) If required at the time of the event , additional resources can be obtained through purchase agreements with private i nstitutions. These agreements would not be prepared in advance , but would be negotiated on an as needed basis.

5.3.3 Local

Services Support NOTE: U pd ate of t hi s l egacy ti tl e i s b eyo nd th e sco p e o f this li ce n se ame ndm e n t r e qu es t. NAEP Page 5.16 Revision # TBD Agreements have been arranged to provid fire fighting , rescue squad , medical and hospital services. Responding rescue squads are trained i the handling , treatment , and transportation of injured personnel.

The Virginia Commonwealth Universit Medical Center (VCUMC) has developed an Emergency Plan designed to provide medical care in th case of a radiation emergency.

The MCVHNCU Radiation Emergency Plan supports the company's clear power stations in the case of occupational and/or major accidents , including contaminated perso nel. In the event of a need for their support , a call ahead to VCUMC will be made to alert them t activate their Rad i ation Emergency Plan. A copy of the plan is maintained on file by Nuclear Erner ncy Preparedness Department and is incorporated into this plan by reference as Appendix 10.9. Letters of Agreement in upport of the North Anna Emergency Plan are re-negotiated once every 2 years. Copies of current agr ements are maintained on file by the Nuclear Emergency Preparedness department.

Agreement lett are limited to Federal , State , Local , and volunteer organizations.

Negotiation responsibility lies with the Director Nuclear Emergency Preparedness. 5.4 COORDINATION WITH PARTICIPATING GOVERNMENT AGENCIES The State organization for response to radiological emergencies is based on normal governmental structures and channels of communication. The Governor , in his role as Director of Emergency Management , directs the emergency response through the State Coordinator of Emergency Management.

The State Coordinator of Emergency Management coordinates the overall response , and the Department of Health provides technical advice and assistance on radiological accident assessment , protective action , radiological control , and radiological monitoring.

Responsibility for radiological emergency response rests primarily with the elected officials of local governments.

As time is a major factor in realizing the benefits of protective action in the event of a radiological emergency , certain of these actions are predetermined and agreed upon by the local governing body and are implemented without delay upon notification of a radiological emergency. An lnsta-phone (dedicated county and state ringdown loop), continuously monitored by the Operations Shift , with extensions available in the Control Room , TSC and CERC , is used for normal transmission of emergency notifications to these authorities (See Section 7.2.2.5). Procedures for authentication of an emergency , via the use of restricted , unpublished call-back telephone numbers , are maintained in State and local Radiolog i cal Emergency Response Plans. When notification is received , the Commonwealth of Virginia Emergency Operations Plan (COVEOP) is implemented and the Virginia Department of Health (VDH) initiates action to assess and evaluate the radiological situation in order to provide guidance and assistance to local governments. After the initial immediate actions , subsequent protective actions are made based on the results of the State evaluation of the radiological situation and the company's recommendations. State and Federal agencies provide assistance as required.

Response operations at the State level are coordinated by the Virginia Department of Emergency Management (VDEM).

NAEP Page 5.17 Revis i on # TBD The State will also provide police support during activation of this plan. In the event of an emergency, the dispatcher at the State Police Headquarters in Richmond, Virginia would normally be called. The first response would most likely be from police units normally based in the local area. These resources would be supplemented by additional units dispatched from other parts of the state. The State Police would also provide traffic control and additional security. The Virginia Department of Game and Inland Fisheries is also part of the response to this Plan. Their role would be to assist in monitoring Lake Anna and provide knowledge of local terrain. The local County Sheriffs of Louisa and Spotsylvania counties also respond to this Plan. They can perform essentially the same functions as the State Police and coordinate their efforts with that organization.

In the event of an emergency, the Station will be in communication with the Louisa, Spotsylvania , Orange, Hanover, and Caroline Directors of Emergency Services who have the capability of activating their Emergency Operations Centers. The Station relies upon these counties to provide assistance in the event an evacuation from the site requires a remote assembly point or for any services the counties are capable of providing to mitigate the results of the emergency.

The Station relies upon Louisa and the Commonwealth of Virginia to coordinate response with other local, state, and federal agencies during a large scale incident , such as a hostile action against the station or a security event. Response agencies will use Incident Command Systems (ICS) guidelines in managing large scale incidents.

The Station will also maintain close contact with the NRG Operations Center and/or the NRG Region II offices in Atlanta , Georgia. This is an important function to ensure that accurate information and assessment of the emergency are available to the Federal Government.

As a result of these communications, the NRG can best appraise their response to the emergency.

In a like manner , the U.S. Department of Energy, Oak Ridge Operations, is available to provide radiological assistance to the Station. The Station has the responsibility to provide to supporting agencies involved in the recovery of the facility or participating in controlling the emergency the necessary information to permit them to use their resources.

In the case of the local counties, the Company provides communication and , when needed, training. This training takes the form of participation in drills and exercises by the county and radiological training for members of local volunteer rescue squads and fire departments. The Company and/or Station will arrange drills and exercises on a routine basis to ensure the plan is workable and to gain experience in its implementation.

The total effort of all parties involved shall be directed toward minimizing the results of an emergency and working toward the recovery of the facility with the least impact on the population at large. CERC personnel coordinate support activities with federal and state agencies responding to the emergency and/or recovery.

The Corporate Response Manager may also assemble NRG, state , vendor , and/or consultant support at the CERC. Assistance may be sought from other nuclear utilities, if needed. If requested by the State EOG , a Company technical representative will be dispatched to provide technical NAEP Page 5.18 Revision # TBD interpretation or clarification of data transmitted to that office. (This individual's responsibilit i es do not include making statements to the media.) 5.4.1 Commonwealth of Virginia Department of Emergency Management (VDEM) The State Coord i nator of Emergency Management coordinates the overall response operations at the State level and performs specific duties as defined in the COVEOP. The VEOC is located in Richmond, Virginia. There are local Emergency Operations Centers in Louisa and Spotsylvania Counties. The VDEM will send appropriate liaison personnel to the Corporate Emergency Response Center upon activation. 5.4.2 Commonwealth of Virginia Department of Health (VDH) VDH personnel, in coordination with VDEM, provide technical advice and assistance on radiological accident assessment , protective actions , radiological exposure control , and radiological monitoring. (Reference COVEOP for more specific information

.) Upon either an Alert or higher classification , VDEM will notify VDH's Office of Radiological Health which will then implement its response procedures. Included in the planned response is a team sent to the CERC , which provides a direct interface between VDH and their Radiological Emergency Response Team (RERT) operating from the VEOC. VDH also provides advice and assistance , as required, to Local Health Districts which provide primary health services to their respective areas. 5.4.3 Additional State Agency Support Add i tional State organizations having possible responsibilities in a radiological emergency are listed in COVEOP. Requests for support services from these organizations will be coordinated through VDEM by the SEM or the CERC Resource Manager. 5.4.4 Louisa County The authority and responsibilities of Louisa County are presented in the Louisa County Radiological Emergency Response Plan (RERP). The Louisa County Radiological Emergency Response Plan applies to radiological emergencies within the county and: a. Assigns responsibilities to county offices and organizat i ons for radiological emergency response and preparedness. b. Sets forth procedures for disseminating warning of radiological emergencies to the citizens of the county. c. Specifies response actions for specific emergency classifications.

d. Delineates the policies and concepts under which the county government will operate in radiological emergency response. Upon notification from the Station Emergency Manager , the Sheriff's Office will notify the County Coordinator of Emergency Services , or his designated representative , who shall: a. Check the notification from the Power Station. b. Initiate the key county official's alert system. c. Initiate public warning procedures , as authorized by the appropriate State authority.

NAEP Page 5.19 Revision # TBD d. Prepare for evacuation of people for the affected a r ea if authorized by the appropriate State authority.

The County Coordinator of Emergency Services or his representative will act i vate and ensure that the EOG is manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. Once initial notificat i ons are complete , the Station Emergency Manager or Technical Support Manager provides periodic status reports to the County Coordinato r of Emergency Services. These reports will include any changes in status or emergency classification.

The County Sheriff's Office will serve as the local point for official communications within and out of the county , pr i or to establishment of the County Emergency Operations Center (EOG). When the EOG is established , this responsibility will transfer to the EOG. 5.4.5 Spotsylvania, Caroline, Hanover, and Orange Counties The authority and responsib i lities of the above counties during a radiological emergency are presented in their respect i ve RERP. The RERPs apply to the rad i ological emergencies with i n these localities caused by events at the North Anna Power Stat i on. The Spotsylvania , Caroline , Hanover , and Orange County RERPs are identical to the Louisa RERP , as described in Sect i on 5.4.4 of this Plan , except for information that is specific to the respective counties. In the event of an emergency of any classification , the SEM will notify all local jurisdictions (Louisa , Spotsylvania , Caroline , Hanover , and Orange and the State) by using the lnsta-phone loop. If the phone is out of service , regular commercial telephone will be used to make the notifications and the above localities have a system to call back to the power station and check the message. All local jur i sdictions provide 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day coverage.

5.4.6 Counties

and Cities Within the Fifty Mile Ingestion Emergency Planning Zone (EPZ) The counties that are directly involved in the emergency plan are Louisa and Spotsylvania. These counties are the major component of the 1 O mile zone. They have emergency response functions as previously stated in this section. The counties and cities within the fifty mile EPZ are listed in Table 5.3. In the event of an emergency , notification and coordination with these entities is the responsibility of the VEOC. 5.4.7 Federal Radiological Monitoring and Assessment Center {FRMAC) Operations Plan The FRMAC Operations Plan provides for the coordinated management of Federal technical response activities related to a radiological emergency. Its primary goa l s include:

• Assisting the State and Federal Coordinating Agency with personnel , equipment , and technical resources , as needed;

• Collecting offsite environmental radiological data; and ,

• Prov i ding the data and related assessments to involved State agencies and to the Federal Coordinating Agency. The Department of Energy (DOE), because of its history and capabilit i es in radiological monitoring and assessment , was assigned the responsibility to prepare for , establish , and manage the FRMAC. The FRMAC may be activated when a major radiological emergency exists , and the Federal government will NAEP Page 5.20 Revision # TBD respond when a State , other governmental entity with jurisdiction , or a regulated entity requests federal support. The SEM or Corporate Response Manager may request FRMAC assistance directly or through the NRC (Federal Coordinating Agency). The Company will provide designated facilities (space and communications equipment) fo r the NRC (Federal Coordinating Agency) in the CERC. It is estimated that a FRMAC Advance Party could be expected at the site within 6 to 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> following the order to deploy , based on the availability of a i rports near North Anna. Richmond International Airport (RIC) is a major commercial facility and is within about an 85 minute drive from the station. Smaller airports located within about an hour of the site may also be used. Further information concerning objectives and organization is provided in the FRMAC Operations Plan (See Appendix 10.10).

TABLE5.1 MINIMUM STAFFING REQUIREMENTS FOR EMERGENCIES NAEP Page 5.21 Revision # TBD Bolded titles indicate 1 o CFR 50 Appendi x E Part IV.A.9 minimum on-shift requirements. Additiona l Within Approx. Major Functional On 45 60 Area Locat i on Major Tasks Emergency Title Shift Min. Min. Assessment of CR Supervision of Shift Manager-Operat i onal Station Operations (SRO) 1 Aspects and Assessment of Operationa l Aspects CR Plant Operations Unit Supervisor (SRO) 2 Control Room Operator (RO) 4 Control Room Operator (AO) 8 Emergency CR/TSC Direction and Station Direction and Control of On-S i te Emergency Control Emergency Manager 1 a Activities Notifications and CR/TSC Notify Offsite Emergency Communicat i ons Support Groups and Communicator 2 b 2 Mainta i n Communications Support of CERC Management of Technical Support (Refer to Table 5.2) Operat i onal Emergency Manager Accident Response Assessment Resources and Recovery Operations Radiological TSC/ Rad i ological Dose Radiological Accident CERC Assessment/

Assessment Assessment Accident Director/ 1c Assessment Radiological Assessment Coordinator Offsite Offsite Surveys Offsite Mon i toring Team Leader Offsite Monitoring Team Member Onsite Onsite (Out of Plant) Onsite Monito r ing Surveys Team Leader Ons i te Monitoring Team Member NAEP Page 5.22 Revision # TBD Additional Within Approx. Major Functional On 45 60 Area Location Major Tasks Emergenc:x'.

Title Shift Min. Min. Radiological In-Plant In-Plant Surveys In-Plant Accident and Radiochemistry Monitoring Team Assessment Leader 1 [continued]

In-Plant Monitoring T earn Member In-Plant Chemistry Chemistry Team Leader Chemistry Team Member 1 Plant Systems cRrrsc Operational Shift Technical Engineering Technical Support Advisor 1d Repair and (STA) Technical Support Corrective Team Member Actions (Operational Advisor) 1 e TSC Core and Thermal Technical Support Hydraulics Team Member 1 f TSC Electrical Technical Support Team Member TSC Mechanical Technical Support Team Member Repair and Corrective Actions osc Mechanical Damage Control Maintenance Team Member 19 2 osc Electrical Damage Control Maintenance Team Member 1 9 osc Instrumentation and Damage Control Control Team Member In-Plant In-Plant Radiation Protection Personnel Protective Monitoring Team Actions Personnel Leader Monitoring and H.P. Personnel Coverage, Monitoring Team 1h Dosimetry and Member 2 Access Control Major Functional Area Location Major Tasks Emergency Title Firefighting In-Plant Firefighting Fire Brigade Members (Operations)

Fire Brigade Members (Security)

First Aid & In-Plant First Aid First Aid T earn Rescue Member In-Plant Search and Rescue Search and Rescue Team Member Site Access In-Plant Security and Access Security Control and Control Team Personnel Members Accountability In-Plant Personnel Security T earn Accountability Leader NOTES: a This coverage is provided by the Shift Manager until relieved.

On Shift NAEP Page 5.23 Revision # TBD Additional Within Approx. 45 Min. 3; local support 2 i local support (Proprietary) (Proprietary) 22 9 19 b Communicator taken from the complement of reactor operators/auxiliary operators on shift. c This coverage is provided by the Senior RP representative onsite until relieved. d Numbers shown are for 2 Unit Operation.

With both units in cold shutdown condition , the minimum shift crew will be as defined in 1 OCFR50.54(m)(2)(i) and the Technical Specifications. e The candidates for this position are limited to qualified ST As , SROs, former ST As , or former SROs. The on-duty Shift Technical Advisor performs the responsibilities of this position prior to augmentation.

g Mechanical and electrical maintenance personnel are normally onsite on a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> per day , 7 day per week basis. This coverage may be provided by personnel who are assigned to other functions during the period that mechanical and electrical maintenance personnel are not onsite (not counted in total). h This personnel monitoring team member is qualified to provide RP job coverage duties. The Fire Brigade consists of auxiliary operators on shift and other qualified non-operations personnel.

This coverage is provided by personnel who may be assigned other functions (not counted in total).

TABLE5.2 EMERGENCY AND RECOVERY CORPORATE RESPONSE REQUIRED FOR NUCLEAR STATION EMERGENCIES Major Functional Area (Emergency Position Title) Management of Corporate Emergency Response Center (Corporate Response Manager) Health Physics & Chemistry (Radiological Assessment Coordinator)

Techn i cal Support (Technical Support Manager) Plan/Design/Construction (Resource Manager) News Center interface (Chief Technical Spokesperson) (ALERT STATUS AND ABOVE) Major Tasks To coordinate the Company's response to emergency and recovery with Federal , State and local authorities. Report to the T echncial Support Manager to conduct radiological assessment activities.

Reports to the Corporate Response Manager to provide technical and evaluation support. Reports to the Corporate Response Manager to provide engineering technical and vendor support in areas dealing with construction or design changes. Reports to the Corporate Response Manager to become the Company Spokesperson in any statements to the News Media. Available

_In_ 75min. 75 min. 75 min. 75 min. 75 m i n. NAEP Page 5.24 Revision # TBD

1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20 ** TABLE 5.3 NAEP Page 5.25 Revision # TBD CITIES AND COUNTIES WITHIN THE NORTH ANNA 50 MILE EMERGENCY PLANNING ZONE** City of Charlottesville

21. Louisa County City of Fredericksburg

22. Madison County C i ty of Richmond

• 23. Nelson County Albemarle County 24. Orange County Amelia County 25. Page County Buckingham County 26. Powhatan County Caroline County 27. Prince William County Chesterfield County

• 28. Rappahannock County Culpeper County 29. Rock i ngham County Cumberland County 30. Spotsylvania County Essex County

• 31. Stafford County Fauquier County 32. Westmoreland County Fluvanna County Goochland County Green County Hanover County

• Henrico County

• King and Queen County

• King George County King William County* With i n 50 miles of both Surry and North Anna That portion of the State of Maryland lying within the 50 mile zone has been excluded. (Reference NRG Letter of February 6 , 1981 , Serial Number 100).

• ** # ## NAEP Page 5.26 Rev i s i on # TBD STATION EMERGENCY ORGANIZATION PRIOR TO AUGMENTATION

• FIGURE 5.1 STATION EMERGENCY MANAGER H EMERGENCY COMMUNICATOR

.____ _ ____. I SHIFT MANAGER OR UNIT SUPERVISOR I ON-DUTY OPERATIONS PERSONNEL CHEMISTRY TEAM I ON-DUTY I I STA## II .__ _____ __. DAMAGE CONTROL TEAM# SECURITY TEAM FIRE TEAM TEAM** H FIRST AID '--------'

...____ SEARCH AND RESCUE TEAM** Augmented for Alert, Site Area Emergency and General Emergency.

This coverage is provided by personne l who may be assigned other functions. This coverage may not be provided on a full time basis. I RADIOLOGICAL ASSESSMENT DIRECTOR I IN-PLANT MONITORING TEAM The on-duty ST A provides technical support as well as operations support to the SEM until the Technical Support Team is activated.

--* ** # NAEP Page 5.27 Rev i s i on # TBD STATION EMERGENCY ORGANIZATION FOLLOWING AUGMENTATION

• FIGURE 5.2 STATION EMERGENCY MAN~GER EMERGENCY I EMERGENCY PROCEDURES I COMMUNICATOR I COORDINATOR I I I I EMERGENCY EMERGENCY EMERGENCY EMERGENCY OPERATIONS MAINTENANCE TECHNICAL ADMINISTRATIVE DIRECTOR DIRECTOR DIRECTOR DIRECTOR I I I SHIFT TECHNICAL ADMINISTRATIVE MANAGER SUPPORT SUPPORT OR TEAM TEAM UNIT I SUPERVISOR I I RADIOLOGICAL SECURITY osc ASSESSMENT DIRECTOR TEAM -DIRECTOR O N-DUTY I OPERATIONS I I DOSE RADIATION osc PERSONNEL ASSESSMENT PROTECTION SUPPORT ..... -TEAM SUPERVISOR TEAM ON-DUTY I STA## OFFSITE IN-PLANT FIRE MONITORING MONITORING TEAM ..... -TEAMS (2) TEAM **,# SAMPLE FIRST AID ANALYS I S TEAM --EVACUATION TEAM **,# MONITORING DAMAGE TEAMS** CHEMISTRY CONTROL T EAM -PERSONNEL TEAM**,# MONITORING SEA R CH AND AND ON-SITE RESCUE DECON TEAM ** (OUT OF PLANT) --TEAM**,# MONITORING TEAM STANDBY OPERATIO N S -Augmented for Alert, Site Area Emergency and General Emergency. PERSONNEL, # This team will be activated only if circumstances req u ire this function to be performed.

Norma l reporting str u ct u re is shown. If the team is activated , contro l of the team wi ll transfer to the Station Eme r gency Manager or appropriate Emergency D i rector.

STATION TO SUPPORT GROUP INTERFACE PRIOR TO AUGMENTATION OF THE EMERGENCY ORGANIZATION FIGURE 5.3 STATION EMERGENCY ORGANIZATION SEE FIGURE 5.1 LOCAL FIRE FIGHTING SERVICES VIRGINIA COMMONWEALTH UNIVERSITY MEDICAL CENTER STATION EMERGENCY MANAGER OTHER SERVICES CORPORATE OFFICE I NEWS MEDIA LOCAL RESCUE SERVICES LOCAL LAW ENFORCEMENT AGENCIES NAEP Page 5.28 Revision # TBD NUCLEAR STAT IO N T O S UP POR T G RO UP INTERFACE F OLLO WIN G C E R C ACTN A TIO N FIGURE 5.4 CORPORATE

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NAEP Page 5.29 Revision # TBD UNAFFECTED REGULATORY

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RESPONSE POWE R COMMISSION MANAGER STATION I I I I EXECUT IV E LIAISON t-CHIEF JOINT INFO RM ATIO N I I -TECHNICAL

-I CENTE R (IlC) I I EMERGENCY PLAN ADVISOR~ SPOKES P E R SON SUPPORT TEAM I I I I I I I I I : I I STATION TECHNICAL RESOURCE NUCLEAR EMERGENCY SUPPO R T MANA G ER NEWS --, MANAGER MANAGER MANAGE R I I I I I I I I I I I I STATION OP ERATIONS I I I : I RES O U R CE I I NEWS I I EME R GENCY SUPPO R T & : TEAM I TEAM I I ORGANIZATION ACCIDENT I I I (SEE FIG. 5.2) ASSESS M ENT INDUST R Y I u." s. DEPT. TEAM S I SUPPO RT OFENE R GY I I I I (DOE) I r I ----------------------T -, I I VIRGINIA DEPT. OF EME RG ENCY MANA G EMENT VIRGINIA DEPT. OF HEALTH (OFFICE OF RAD IOLOG ICAL HEALTH) DEPT. OF V IRG INIA STATE POLICE V IRGINI A COMMONWEALTH UNIVERSITY MEDICAL CENTER VIRGINI A D EPT. OF G AME AND INLAND SYMBOLS: FISHERIES MANAGEMENT CONTROL COORDINATED ASSISTANCE

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I DIRECTOR EME RG ENCY SE R VICES (LOCAL GOV'T) OFFICE OF EME RG E N CY S E RVIC ES SUPERINTENDENT SCH O O LS SHERIFF OR POLICE FIRE DEPAR T MENTS RESCUE I I ......__s_Q_U_AD_s _ ___.r SHADED BOX IDENTIFIES SUPPLEMENTAL STAFFING WHEN CE R C SUPPORTING SURRY AND NORTH ANNA DEPT.OF SOCIAL SERVICES DEPT.O F PUBLIC HEALT H n TECHNICAL SUPPORT CENTER ORGANIZATION FIGURE 5.5.a I I I I ml'rgl'nc:, ( )pl'l .tlll)Jl', D11L'Llilr I ---------------1 __ : Plant Status : : Communicator

1--------------*

Emergency Procedures Coordinator I llll'I t'.L'lll > I c:cl1111Lal 1)11 L'l'[ill Technical Support Team Leader

• TSC Communicator fulfill s state/local notification function if EOF unavailable. S1.1t1on I 111<:1gc:11L>

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• Indicates positions necessary for facility activation.

D Indicates fully augmented organization positions. ;--: Indicates position established if needed. L--I rnl'rgl'nc>

I\Lunll'llallL"L' I )11 L'L"((l( Emergency Administrative Director Administrative Support Team Leader TSC Logkeeper Administrative Support Team Clerk (3) NAEP Page 5.30 Revision # TBD Rad 10 logic al 1\"-l-\llll'lll I )11 L'L°lil1 Dil,l' . \ \Sl'SSlllL'Jl[

TL*a111 I .caLkr I lllSl' . \ SSL-\ll)L'lll learn I 111'\: ( *,)1n1m1nicall>rJ OPERATIONAL SUPPORT CENTER ORG ANIZATION FIGURE 5.5.b OSC I )11 c'L l ll l !---~~~-~~~-~~~**;~~:************************************

• • • • • • • • ----------

--************************** ***********************-*************************-----**------*****

• 1 i i i l ! J :.= Radiological

',, Operations OSC Team Lead er I Coo,d;oato, i:a:::~, I '**:

ii, Material Outage & Planning Coordinator

! Coordinator Coordinator i.1 Status Boa,d Safet y ~';:',~:::

I i Keeper Coordinator i 1 I ! Instrument

! I Logkeepe, Cootdioato, I .I I ECo~pon~nt i ngmeenn g ! j Coordinator 1 f, I ; I I------.--------I! : .. Operat10ns Team , 1 i I I I! NAEP Page 5.31 Revision # TBD ' I I i ~-----------~-~~~~----_-_-_-l 1 I I I I I -------'--'---'---'

I !:1~~~t:_dJ , : : Rad Wa s t e : ! !. -Team Leader : i I* i ' I I 1----------------1 L -*Auxiliary Operator s , l--------------

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.: I I I .------_ J_ -------, I I , First Aid T ea m * ' I I L---------------J

,--------L -------1 I I : Fire Brigad e * : L---------------J i--------L -------1 , Search & Rescue 1 I I , Team** ' L---------------J

• First Aid Team and Fire Brigade functions are addressed by on-shift personnel.

Additional qualified per so nnel who report to the OSC may b e designated for these functions. ** Search & R esc u e Team fo rm ed from Fire Brigade/First Aid Team/Security staff as appropriate.

• Indicates position s necessary for facility activation.

D Indicates fully augmented organization p ositions.

--: Indicates team established as needed. L--

I~-RA D IATION P RO TECTION ORGANIZATION FI G URE 5.5.c I 11-l'lanl i\lo111l(l1Jllg Tc,1111 I cadc, I 11-l'lanl i\l()nitoring Team i\kmhL*r I 11-l'lanl i\fonit()ring Team i\kmhLT On-Site (( )ul-()l-l'l,1111 I i\l()111t()f 111g I c.im I cadc, R.1d1.t[Hlll 1'11llCC[IOll Supc1, 1,01 I I I r----------------------r-------

1 I I <)II site i\lo111l()l lllg *1 cam 11 1 LcadL'I Ol! ,1 IL' i\ I, lllJ l()1111g I L',1111 ii:. I L'.tdc1

• Indicates positions necessary for ac t ivation. l'c1,01111cl i\l()111101111g

• 1 cam I.L'alk, NAEP Page 5.32 Revision # TBD Chc1111,tl\

I ca111 I.L*adL'I ( 'hL'lllistr~

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• Offsite Monitoring Teams are controlled by CERC Acci d ent Assessment Team after being staged.

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• D NAEP Page 5.33 Re vi s i on # TBD CORPORATE EMERGENCY RES PO NSE CENTER ORGANIZATION FI G U RE 5.5.d Corplll ate J{cs_pll11SC

\J,111;1gc1 Ex ec u ti v e Li ais on ChiL'I I ccl1111L;tl Splikc,pcr,(in

• • • • • • • • • • • • • • • • • • • • • • • • • • • ---**---****---****

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• • • • • • • • • -******-*****

• • • • • .. ' : : J o int In f ormat i on C e nt e r : I S u pport Team I j i j i Emergen cy Plan Advi s or i D . . D o minion i 1-----1 i orru m on T ec hnical ! i L i ai so n Advi s or i ( >pc1.ttll111al Suppll1 t (0 (Hlldllldl<ll I cch111c,tl Suppll1 l \Lllld!!L'I J<.tdllllll!!IL,tJ

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(0 (Hl1dil1dllll r* ---.......................................................... 1 : 1 i Operational i ! Acci d ent ! i S u pport i ,! TAesasem s sment 1 , ! Team ! : : i i i 1 i Ac c id e nt ! I 11 :e:::=:, I I ~~:~~i:,;;

11 D ose I 1___:::::~J I I Indic a te s p os i tio n s n e ce ss ary for facilit y a cti va ti o n. In d ic a t es full y a u gme n ted o r ganizatio n p osi ti o n s. i i I I ' ' i i I I l ............................ ___________ .................

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• • • • • • • • • • • -**-****-***********************.

i I I ~:::= I ' : ' : ' : I I ' : ' : i L og i stics ! I Coordinat o r I ' ' : ' : ' : ' ' ' ! Meteoro l ogi s t ! ' : I ' i ! ! Admini s trative I / ! : -o,h~;:;;o;,--: ! ! -Personnel

! I '---------------*: ' : :. ... -................... ______ , .......................... : !\ tiL JcaJ \;L'I\ S \L111.igc1 I New s ! I Team I ' : ' : ' : ' : ' ' ! New s ! ' ' ! Wri t er i i i : ' : ' : ' I Ta~~~:;ints I ' : I i i S o cia l Media i ' : i Coordinator

! I I i nformation C e n t e r i i Coordi n at o r : : ' : ' . -*************************-

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--: Ind ica te s t ea m L --es t a b l i s h e d as n eeded. I I 0 Indi ca t es ex p an d ed ERO fo r du al-s t at i o n r espo n se. i : ' : ' : L.*-****------

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• • -************..I Part 6.0 6.1 6.2 6.3 6.3.1 6.3.2 6.3.3 6.3.3.1 6.3.3.2 6.3.3.3 6.4 6.4.1 6.4.2 6.4.3 6.4.4 6.5 Table 6.1 Table 6.2 Table 6.3 Figure 6.1 Figure 6.2 Figure 6.3 Figure 6.4 Figure 6.5 Figure 6.6 NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 6 EMERGENCY MEASURES Subject Emergency Measures Activation of the Emergency Plan Assessment Actions Protective Actions Offsite Criteria for the 10 Mile Emergency Planning Zone (EPZ) Onsite Criteria for the Exclusion Area Use Onsite of Protective Equipment and Supplies Respiratory Protection Protective Clothing Thyroid Blocking Agent Aid to Affected Personnel Emergency Exposure Limits Decontamination and First Aid Medical Transportation Medical Treatment Offsite Support Radionuclides with Significant Contribution to Dominant Exposure Modes North Anna Population Distribution and Evacuation Time Estimates North Anna Power Station Population Data by Sector Sample Form: Report of Emergency to State and Local Governments Sample Form: Protective Action Recommendation Sample Form: Radiological Status Form (M I DAS generated)

Sample Form: Radiological Status Form (manual) NAPS 10 -Mile Emergency Planning Zone Remote Assembly Areas NAEP Page 6.1 Revision # TBD Page No. 6.2 6.2 6.2 6.3 6.3 6.4 6.5 6.5 6.6 6.6 6.6 6.6 6.7 6.7 6.8 6.8 6.9 6.10 6.11 6.12 6.13 6.14 6.15 6.16 6.17

6.0 EMERGENCY

MEASURES NAEP Page 6.2 Revision # TBD Emergency measures provide pre-planned actions , methods, and criteria which guide personnel during the course of an emergency.

The initial response to any emergency condition will be the activation of the Emergency Plan. After activation, the emergency organization that is formulated by activation of the Emergency Plan performs the necessary assessment activities to classify the type of emergency. If the emergency is radiological in nature , the potential consequences of the emergency will be evaluated for the necessary offsite and onsite protective actions to guard the health and safety of the population. If additional assistance is required , offsite support will be requested as provided for in letters of agreements established with a variety of government agencies and volunteer organizations.

6.1 ACTIVATION

OF THE EMERGENCY PLAN Each full time employee of the station is required to be familiar with the provisions of the Emergency Plan. Any employee, upon becoming aware of an emergency condition , shall immediately notify the Shift Manager on duty unless it is apparent notification has already taken place. Upon such notification or other indications , the Shift Manager or Unit Supervisor assumes the responsibilities of the Station Emergency Manager. The SEM will classify the emergency , initiate the appropriate notifications and call outs , and coordinate the actions of the emergency response organization. State and local community officials will be notified within 15 minutes after declaration of an emergency (meaning the emergency classification level has been provided to the Virginia and risk-jurisdiction Emergency Operations Centers (EOCs)). The initial information following declaration of any emergency class includes the class of emergency , whether a release is in progress , and any recommended protective measures. Additional informat i on will be provided as it becomes available. Figures 6.1 through 6.4 are samples of message forms used for these notifications.

The content of the messages have been established in conjunction with the State and local governments. Notifications will be made to the NRG as soon as possible but within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after declaration of an emergency. Initial information is provided to the NRG as required by 10 CFR 50.72 (Immediate notification requirements for operating nuclear power reactors).

Dedicated communicators will be available to provide regular updates to state and local officials approximately every 60 minutes , when conditions change or as otherwise agreed , and to maintain a continuous channel of communications with the NRG. 6.2 ASSESSMENT ACTIONS EPIP-1.01 , Emergency Manager Controlling Procedure, is the procedure for emergency event categorization and classification , while EPIP-4.01, Radiological Assessment Director Controlling Procedure , provides guidance for conducting dose assessment, source term determination , atmospheric diffusion factor determination , monitoring team activities, personnel monitoring and decontamination , monitoring of onsite facilit i es , evacuation , respiratory protection, sampling and sample analysis , and use of the MIDAS computer model. Once the emergency classification has been determined, the appropriate EPIPs are initiated to direct the activation of the required emergency response facilities and call out of designated emergency response NAEP Page 6.3 Revision # TBD personnel.

The design of the facilities and the data retrieval and monitoring capab i lities provide the information needed to make timely assessments and formulate appropriate protective actions. 6.3 PROTECTIVE ACTIONS The Technical Support Manager or the Station Emergency Manager (if the CERC is not yet activated) is responsible for recommending offsite protective actions to the State. The State and local governments are responsible for notification of the public and implementation of the appropriate protective measures. 6.3.1 Offsite Criteria for the 10 Mile Emergency Planning Zone (EPZ) Dose contribution from key isotopes such as those listed in Table 6.1 (and analyzed in UFSAR Sections 11 and 15) are used to calculate offsite doses for comparison to protective action recommendation thresholds.

Protective action recommendations are required to be made to the State within 15 minutes of declaring a General Emergency.

Specific protective action recommendations tied to plant and meteorological conditions have been designed to facilitate meeting this time requirement.

Th i s guidance is based on Supplement 3 (Guidance for Protective Action Strategies) to NUREG-0654

/FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." The initial protective action recommendation for any event classified as a General Emergency will be to evacuate a 2 mile radius and 5 miles in the downwind sectors unless severe accident conditions exist, an evacuation dose threshold is exceeded beyond 2 miles or sheltering

-in-place is appropriate.

Sheltering-inplace may be appropriate when known conditions make evacuation dangerous , such as a hostile action based event. Follow-up protective action recommendations that the station may make to the state will be based on current meteorological data such as wind direction , wind speed and stability class , and dose projections.

Also , consistent with the Commonwealth of Virginia's strategies for supplementing these protective actions with use of potassium iodide (Kl) by the general public as a prophylactic , recommendations will be made for implementing these strategies. A Site Area Emergency will be declared when offsite doses are projected to exceed 0.1 Rem TEDE or 0.5 Rem Thyroid COE. A General Emergency will be declared when offsite Protect i ve Action Guides (PAGs) of 1.0 Rem TEDE and/or 5.0 Rem Thyroid COE are projected to be exceeded due to a direct radiat i on or i nhalation hazard , or when non-radiological conditions exceed General Emergency EALs. Warnings to the public within the 10-mile EPZ (Figure 6.5) w i ll be the responsibility of State and local officials who will be assisted by the Virg i nia Department of State Police upon request. The primary method of warning the public is by the use of the Early Warning System sirens. Route alerting provides backup alert and notification capability (reference 10 CFR 50, Appendix E , paragraph IV.0.4). Other warning methods may include telephone communications , television and radio Emergency Alert System stations , public address systems, bull horns from patrol cars and personal contact. There are currently no hospitals, prisons , or nursing homes within the 10 mile EPZ.

NAEP Page 6.4 Revision # TBD It is estimated that the primary sector and the two buffer sectors (spanning 67 1/2°} can be alerted of the emergency within 15 minutes using the Early Warning System. If evacuation is recommended , it is estimated that the 67 1 /2 ° sector can be evacuated within 2 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Evacuation zones , routes , and relocation centers have been established in the event that an evacuation is recommended.

This information is published in brochures and distributed by the State. Population distribution and evacuation time estimates are maintained on file by the Nuclear Emergency Preparedness Department (reference Appendix 10.8) and are summarized in Tables 6.2 and 6.3. Written pre-planned messages intended for transmittal to the public via radio and television stations will be consistent with the classification scheme. They will be released to the media by the State Coordinator of Emergency Management or Local Coordinator of Emergency Services or his designated representative. The messages will give instruction with regard to specific actions to be taken by the occupants of the inhabited area. The messages will , as appropriate , give instruction on the aspects of sheltering , thyroid blocking , evacuation, the nature of the emergency , and recommended protective actions. The local governments are charged by the COVEOP with the responsibility to conduct information programs to educate their citizens on: 1. Radiological hazards, 2. Procedures for notification of a radiological emergency , 3. Evacuation routes and assembly points , and 4. Other protective measures.

The COVEOP identifies the methods to be utilized in preventing or minimizing direct or subsequent ingestion exposure to radioactive materials deposited on the ground or other surfaces.

Upon notification of a radiological emergency which may affect livestock , crops , or farmlands , the Virginia Department of Agriculture and Consumer Services will institute a program to assess the impact upon the agriculture community.

Members of that department will take samples of milk from dairy cattle in the affected area for analysis and will monitor soil, crops and farm equipment for contamination.

Follow-up action includes the disposition of radiologically contaminated materials. The local county government(s) has the prime responsibility for controlling affected area ingress and egress. Assistance from the State Police shall be supplied as requested by local officials.

6.3.2 Onsite

Criteria for the Exclusion Area The area within 5000 feet of the former North Anna Unit 3 containment is defined as the Exclusion Area for the purposes of this Plan. Company employees , supplemental personnel, occasional visitors at the site , and boaters on the reservoir and cooling lagoons may be inside the Exclusion Area. The area immediately surrounding the units which is enclosed by a security fence is defined as the Protected Area. The Station Emergency Manager is responsible for making the decision to evacuate the Protected Area , and will take appropriate measures in cooperation with State and local agencies for evacuation of persons in the Exclusion Area and those members of the public who may be passing through the site or within Company property.

The company will also commit personnel and appropriate equipment (search lights , power NAEP Page 6.5 Revision # TBD amplified l oudspeakers) to assist the Virginia Department of Game and Inland Fisheries in clearing the Exclusion Area when required.

Visitors to the Protected Area of the station are under continuous escort by personnel knowledgeable in emergency personnel accountability procedures.

Supplemental personnel are also trained in personnel accountability procedures.

Onsite personnel will be immediately notified of an emergency that is initially classified as an Alert or higher event, unless doing so poses a threat to personnel safety. For example , hurricane force winds, a tornado, or a security breach may dictate suspension or deferral of assembly , accountability and/or initiation of facility staffing.

However , these activities would be implemented as quickly as achievable given the specific situation.

Station procedures provide for a range of protective actions to protect onsite personnel during hostile action and ensure continued ability to safely shut down the reactor and perform emergency plan functions.

Normally, alarms will be sounded and announcements will be made to conduct personnel accountability or, if necessary, a site evacuation of non-essential workers. Those individuals within the Exclusion Area will be alerted by station personnel , Security , and/or personnel from the Virginia Department of Game and Inland Fisheries.

In the event of an evacuation , radiation monitoring teams will be dispatched to the appropriate Remote Assembly Area. Emergency Assembly Areas have been established outside the Protected Area to facilitate the dissemination of information to personnel.

The Station has the capability to conduct personnel accountability for individuals inside the Protected Area within approximately 30 minutes. After accountability is completed , an evaluation is made and search teams may be dispatched to locate any individual noted as missing or unaccounted. If onsite evacuation is to occur , Security collects only the security key cards , not the dosimetry , of all personnel leaving the Protected Area. Continuous accountabil i ty of personnel in the Protected Area not evacuating the site shall be maintained throughout the emergency.

Evacuees , who may use personal vehicles , proceed to either the primary or secondary remote assembly area (See Figure 6.6). Station evacuees will be surveyed for contamination following events involving a radiological release , and decontaminated , if necessary , prior to being released from the remote assembly area. Decontamination agents and supplies are available at the station which can be transported to the remote assembly areas to provide decontamination capabilities.

6.3.3 Use of Onsite Protective Equipment and Supplies 6.3.3.1 Respiratory Protection The company has a comprehensive respiratory protection program at its nuclear stations. VPAP 2101 , "Radiation Protection Plan" , establishes the Respiratory Protect i on Program which is implemented by HP procedures. Those individuals likely to wear respirators are given a pulmonary examination and training on respiratory protection including a practical examination. A "fit test" is given before an individual is allowed to enter an area requiring respiratory protection.

NOTE: Examp l es of protective clothing to be upd ate d to reflect c urr e nt inventories.

This change is beyond th e sco p e of this li cense a m e ndm ent request. 6.3.3.2 Protective Clothing NAEP Page 6.6 Revision # TBD The station maintains an adequate inventory of protective clothing *n the Clean Change Room. Contaminated clothing is washed at the station and re-issued provided conta

• ation is below established radiation criteria. A Radiation Work Permit system is utilized whereby Radiolog al Protection establishes personnel protect i ve clothing and equipment criteria.

Such clothing may consist of cotton coveralls , hoods , cotton glove inserts, rubber gloves, plastic shoe covers, rubber shoe covers and rubber boots. Station personnel requiring access to a Radiological Control Area are given training on how to don and remove protective clothing so as to m i nimize personal contamination or introduction of contamination into adjacent areas. 6.3.3.3 Thyroid Blocking Agent The process for administering a thyroid blocking agent in a potential radioiodine inhalation situation was authorized by the company's employee health services staff in consultation with its medical support staff. 6.4 AID TO AFFECTED PERSONNEL The Company has made arrangements with the Virginia Commonwealth University Medical Center (VCUMC), to provide medical assistance to personnel injured or exposed to radiation and/or radioactive material.

VCUMC has developed its own plan for responding to the emergency. VCUMC's plan establishes a specialized area of the hospital for treatment with appropriate Health Physics functions, and implements a coded system to alert hospital team members. Radiation monitoring equipment , dosimetry , and protective clothing are available at VCUMC. The Station will provide and distribute self reading and cumulative type dosimeters to all personnel involved in emergency onsite response regardless of their affiliation.

Dose records shall be maintained and checked throughout the emergency.

6.4.1 Emergency

Exposure Limits Emergency response personnel may , because of necess i ty , receive once-in-a-lifetime exposure to contamination and radiation up to the 1 OCFR20 annual limits , not including accumulated occupational exposure. Approval from the Station Emergency Manager is necessary for planned exposures greater than the 1 OCFR20 annual limits. Under limited circumstances , exposure levels greater than 5 times the 1 OCFR20 annual limits are allowed, but only on a voluntary basis to persons fully aware of the risks involved.

Selection criteria for volunteer emergency workers includes consideration of those who are in good physical health , are familiar with the consequences of emergency exposure , and are not a "declared pregnant adult". It is preferable , though not mandatory , that volunteers be older than 45 years of age and not be a female capable of reproduction.

Emergency exposure may be authorized for such needs as removal of injured personnel , undertaking corrective actions , performing assessment actions , providing first aid , performing personnel decontamination , providing ambulance service , providing medical treatment , etc. Guidelines for emergency exposure limits , including life saving actions , are consistent with EPA Emergency Worker and Life Saving Activity Protective Action Guides.

6.4.2 Decontamination

and First Aid NAEP Page 6.7 Revision # TBD There are First Aid stations located throughout the North Anna Power Station that contain the normal complement of first aid supplies and equipment necessary to treat those injuries not involving hospitalization or professional medical services.

At least two First Aid Team members are available at all times to respond to personnel injury. As a minimum , the First Aid Team personnel are Multi-Media first aid trained. In addition , the following Medical facilities and services are available:

1. Company nurse available during normal working hours (Mon. -Fri.). 2. Company ambulance.

3. Company designated physicians in the area. 4. Local Rescue Squads. 5. The Virginia Commonwealth University Medical Center facilit i es. Actions are required to be taken when levels of radioactive contamination for workers , equipment or areas exceed 1,000 dpm / 100 square centimeters of removable contamination. Any detected personnel contamination will initiate appropr i ate evaluation and decontamination. The Station controls access for onsite contamination and the return of these areas and their contents to normal use. No food supplies are grown on the site and the water supplies come from deep wells. Areas designated permissible for employees to eat and drink during the emergency and recovery phases of operations are monitored for contamination. If onsite personnel are required to relocate or routinely leave the site during an emergency , the Station will provide adequate supplies for personnel decontamination , clothing and means to provide for decontaminating the clothing. If radioiodine contamination of the skin is determined , provisions will be made to provide for decontamination. Monitoring of vehicles and personnel will be performed at the Remote Assembly Areas (RAA). Should decontamination of vehicles or personnel be warranted , Health Physics personnel can perform the task at the Station , the RAA , or if necessary , at Patrick Henry High School in Hanover County. 6.4.3 Medical Transportation A Station ambulance is available to transport contaminated injured personnel.

Contaminated injured personnel will be suitably clothed or prepared to prevent the spread of contamination in the transporting vehicle. Communication can be maintained with VCUMC from the station. The Station can also communicate with the ambulance by use of a UHF radio , and the ambulance can communicate with VCUMC by way of the HEAR system. In addition , arrangements have been made with local volunteer rescue squads to transport injured contaminated personnel to the Virginia Commonwealth University Medical Center. Response team members have received training concerning transportation of contaminated in j ured individuals. A Health Physics technician , with appropriate instrumentation , would normally accompany NAEP Page 6.8 Revision # TBD contaminated injured personnel to VCUMC. The approximate time to transport a patient to VCUMC is 75 minutes. The estimated time for local rescue squads to arrive at the station is 30 minutes. 6.4.4 Medical Treatment The MCVH/VCU-Dominion Power Radiation Emergency Plan (Appendix 10.9) provides guidance for the treatment of contaminated injured personnel by qualified individuals. The Radiation Emergency Plan includes provisions to request assistance from other facilities having the capability to receive and treat injured and/or contaminated individuals. In the event the facilities at VCUMC become over extended , VCUMC may coordinate further assistance with these facilities directly or through the Virginia Department of Health. 6.5 OFFSITE SUPPORT In addition to the offsite agencies listed above, local volunteer fire departments have agreed to assist in fighting fires. A list of services and equipment is included in the Agreement Letters referenced in Appendix 10.1. The response time of these volunteer fire departments varies from 30 minutes to 45 minutes , unless adverse weather conditions prevail. Police support for an emergency is provided by State and local governments as detailed in their respective Emergency Plans.

TABLE 6.1 NAEP Page 6.9 Revision # TBD RADIONUCLIDES WITH SIGNIFICANT CONTRIBUTION TO DOMINANT EXPOSURE MODEs<1> Radionuclides with Sign i ficant Contribution to Thyro i d Exposure Half life Radionuclide (days) 1-131 8.05 1-132 0.0958 1-133 0.875 1-134 0.0366 1-135 0.280 Te-132 3.25 (1) Derived from NU REG 0654 Rad i onuclides with Significant Contr i but i on to TEDE Exposu r e Half l i fe Radionuclide (days) 1-131 8.05 Te-132 3.25 Xe-133 5.28 1-133 0.875 Xe-135 0.384 1-135 0.280 Cs-134 750 K r-88 0.117 Cs-137 11 , 000 Radionuclides with Significant Contribut i on to Lung Exposure (Lung only controlling when thyroid dose is reduced by iod i ne block i ng or there i s a long delay prior to releases)

Half Life Radionuclide (days) 1-131 8.05 1-132 0.0958 1-133 0.875 1-134 0.0366 1-135 0.280 Cs-134 750 Kr-88 0.117 Cs-137 11 , 000 Ru-106 365 Te-132 3.25 Ce-144 284 NAEP Page 6.10 Revision # TSO NORTH ANNA POPULATION DISTRIBUTION AND EVACUATION T I ME ESTIMATES (In hours and minutes) TABLE 6.2 Region 1 Region 2 Region 3 Scenario 2mile Smile 10 mile EPZ EPZ EPZ Summer Midweek Mid-day Good Weather 2: 30 2: 30 2: 35 Summer Midweek Mid-day Rain 2: 30 2: 30 2:40 Summer Weekend Mid-day Good Weather 1 :45 1 :45 2: 00 Summer Weekend Mid-day Rain 1 :50 1 :50 2:00 Summer Evening Good Weather 1 :50 1 :50 1 :55 Winter Midweek Mid-day Good Weather 2:30 2: 30 2:40 Winter Midweek Mid-day Rain 2: 30 2: 35 2:40 Winter Midweek Mid-day Snow 3: 20 3: 25 3: 30 Winter Weekend Mid-day Good Weather 1 : 50 1 :50 2:00 Winter Weekend Mid-day Rain 1 :50 1 :50 2:00 Winter Weekend Mid-day Snow 2: 50 2: 55 3: 05 Winter Evening Good Weather 1 : 50 1 : 55 2:00 Winter Weekend Mid-day Special Event 1 : 50 1 :50 2: 00 Winter Weekend Mid-day Road Impacted 2:30 2:30 2: 35 Region 1 Region 2 Region 3 Total Population Evacuated 2mile Smile 10 mile EPZ EPZ EPZ 2 , 969 13,705 46 , 186 Information summarized above derived from KLD Engineering, P.C. Evacuation Time Estimates for the North Anna Power Station and Surrounding Jurisdictions dated November 2012 (Figure 3-2 , Permanent Resident Population by Sector , and Figure 3-13, Transient Population by Sector Table 5) and Table 3-7 , Summary of Population Demand. Total population evacuated represents the total population loaded onto the network during the 14 simulations listed and evacuation time estimates were calculated based on when approximately 90% of that population has exited the 10-mile radius. A region is a grouping of contiguous Protective Action Zones (PAZ) evacuated in response to a radiological emergency A scenario is a combination of circumstances, including time of day , day of week, season , and weather conditions. Scenarios define the number of people in each of the affected population groups and their respective mobilization time distributions.

NORTH ANNA POWER STATION POPULATION DATA BY SECTOR TABLE 6.3 Direction/Sector Population 2-Mile RinQ 5-Mile RinQ Direction: North Permanent Resident 76 367 Sector: A Transient 0 159 Direction: North Northeast Permanent Resident 21 282 Sector: B Transient 150 35 Direction:

Northeast Permanent Resident 12 142 Sector: C Transient 0 0 Direction:

East Northeast Permanent Resident 0 163 Sector: D Transient 0 0 Direction: East Permanent Resident 63 263 Sector: E Transient 0 58 Direction: East Southeast Permanent Resident 20 378 Sector: F Transient 0 0 Direction: Southeast Permanent Resident 29 231 Sector: G Transient 0 0 Direction:

South Southeast Permanent Resident 64 341 Sector: H Transient 0 0 Direction:

South Permanent Resident 92 261 Sector: J Transient 0 0 Direction: South Southwest Permanent Resident 39 128 Sector: K Transient 0 0 Direction: Southwest Permanent Resident 11 220 Sector: L Transient 0 0 Direction: West Southwest Permanent Resident 12 142 Sector: M Transient 0 0 Direction:

West Permanent Resident 149 188 Sector: N Transient 0 0 Direction:

West Northwest Permanent Resident 41 546 Sector: P Transient 0 0 Direction:

Northwest Permanent Resident 0 405 Sector: Q Transient 0 390 Direction:

North Northwest Permanent Resident 58 161 Sector: R Transient 0 2383 NAEP Page 6.11 Revision # TBD 10-Mile Ring 1181 0 1305 0 1678 0 1720 0 1258 0 1064 0 931 0 1184 0 1714 0 861 0 1598 0 1683 0 750 0 812 2000 1429 98 980 0 22.5° conical sectors are designated by compass direction point outward from the plant on the centerline of the sector , e.g., sector from 348.75° to 11.25° is designated as Direction: North. Sectors are designated by letter beginning with A for North and where the remaining 15 sectors are designated in a clockwise direction by the subsequent letter , excluding I and 0. Rings are defined as the area between circles of radius O and 2 miles , 2 and 5 miles , and 5 and 10 miles. Information summarized above derived from KLD Engineering , P.C. Evacuation Time Estimates for the North Anna Power Station and Surrounding Jurisdictions dated November 2012 (Figure 3-2 , Permanent Resident Population by Sector , and Figure 3-13. Table 5 , Transient Population by Sector).

NAEP Page 6.12 Revi s i on # TBD F igure 6.1 REPORT OF E M ERGENCY T O STATE AND L OCAL GOVER NM ENTS ROE MESSAGE# __ _ APPRO V AL:----=-------=----,,.,.(S tati on Emergen cy Manager or Recovery Manager) ATTE N TIO N A L L STA TI ONS. Th i s i s North Anna Power Sta ti o n. Standby for a (n) D Dr\11 Message D Emergenc y Message D Drill Term i nation Message D Emergen cy Term i na ti on Message. Use the Report of EmerQencv form t o copy messaQe. (READ S L OWL Y) It e m 1. E M ERGE N C Y C LA SS I F I CA TI O N: 0 N O UE 0Alert D Site Are a Emergen cy D General Emergenc y In a ccordan c e wit h E AL *--------Declared at (2 4-hr ti me} on (d ate). Th i s i s (name) I Emergen cy Commun i ca t o r. Please ackno wl edge rece i p t o rt h i s message: (Con d uct r o ll-ca ll and c h ec k bo x e s a s ea c h p arty answers.) D V A EO C D Lou i sa Co un ty D Spot syl van i a Co u n ty D H anover C oun ty D Orange c oun ty D Caro li ne Coun ty N oti fica ti on completed a t (24-hr time) o n (da t e). I te m 2. M ETEORO L OG IC AL DATA: Based on: D O n-site Measuremen t s D Off-site Measuremen t s D No t A v a il ab l e Time: A V E \II/i nd Speed mph; A VE Wi nd D i rect io n fr om degrees co* t o 36 0°) (24-hr ti me) I t em 3. RE L EASE OF RADIOAC T I V E M ATERI AL: Routine releases ongo in g due to plant opera tio ns. Add i tion a l rad i olog i ca l releases as socia ted With the even t D A. No radiolog i ca l release. Wdl NOT t ransmit Report of Rad iol og i cal Conditions IO Vi rg i n i a E OC. D B. Radiolog i ca l re l ease in p r ogress. Will transm it Report or Rad i ological Conditions to Vi rg in i a E OC. D C. Radiolog i cal release n ow t erm i na t ed. Wi ll transm i t Report of Racft0log l cal Conditicins t o Vi rg i n i a E OC. D D. Rad i olog i cal r elease projected to occu r. Wi U t ransm it RePQrt of Rad i olog i cal cond ition s t o Virgin ia EOC . Ite m 4. SITE A C CESS: D Available D Not Available

.... . -It e m 5. PROTECTIVE ACTIO N RECO MM ENDA TI ON: 0 i s NOT requ ir ed O Wi ll be uans m itt e d t o V E OC O ha s be e n tra n sm i tted to V EO C. Item 6. UPDATE SC H EDULE: 0 60 m i nutes (recommended

); 0 Other ; EOC W at ch Office r: .... N OTE: Items 7 -1 1 optio nal for m essage report in g m ltl a l Emet:genc y Plan e ntry , eme r g ency classi fic a ti o n ch a n ge °' PAR changes a n d " Ex cl uded fr o m message* ma y be checked " Items 7 -1 1 ant excluded from message" ma y be read in l i eu o f read i ng each i tem. It e m 7. E M ERGENCY RESPONSE ACTIO N S U N DERWA Y: , ' D Exduded from message 0 None D station emergen cy personnel called i n D Station mon it oring teams d i spa t ched off-s it e .. D ot her Item 8. E V AC U ATION OR CO M PANY DISM I SSA L .... OF SITE PERSONNEL: D Exduded from message 0No 0 Evaruation to P ri m ary Remote Assembl y Area: D Planned D In prog r e s s D Comple t ed D Released from RAA D Evacuation to S e co ndary Remote Assembly Area: D Planned D In progress D COmpleted D Released from RAA O Compan y Dism i ssal: O Planned D In p r ogress D Completed D Other It e m 9. PROG N OS I S OF S I TUA TI ON SINCE LAST REPOR T: D Excl u ded from message D Stable o w orsen i ng 0 Improving D Other It em 1 0. ASSISTANCE REQUESTED OR BEING PRO VI DED: D Exduded from message O None ___ (#) Fire Units from ___ (#) Pol i ce Units from (#) Rescue Un i ts from (#)Other Item 11. ADDITIO N AL I N FOR M ATION (Do n ot use abbre vi a ti o ns , m ark n umbe rs or a c ronym s.): D Excluded from message Th i s I s North Anna Power Sta ti on out at (24-hr time) on (date). Item 1 2. TER MI NATIO N I NFORMATION (Comp l ete ONLY f or t e rmi nat i on messag e): Event Term i nated a t (24-hr time) on (date). Please aek.nowtedge rece i pt or this message: (Cond u ct roll-call and chec k bo x es as each pa rty ans w e rs.) D V A E OC D Lou i sa County D Spotsylvan i a County D Hanover County D Orange County D Caroline County This is North Anna Po-wer Sta ti on ou t at 24-hr ti me on date .

Figure 6.2 Protect iv e Act i on Recommend.it i o n PROTECT IV E ACTION RECO MM ENDATION: NAEP Page6.13 Revision # TBD D SHELTER-IN-PLACE

__ Mile radius 360° and __ M il es downw i nd in the follow i ng sectors: D EVACUATE: __ Mile radius 360° and __ Miles downwind in the f ollowtng sectors: D BEYOND 10 MILE EPZ: D Evacuate Area: __ Centerline in degrees; __ D i stance in M i l es; __ Width i n feet D Shelter-i n-place: __ Cente r l i ne i n degree s , __ Distance in M i les; __ Width in feet D POT ASS I UM IODID E: Recommend implementation of Po tass i um Iodide (Kl) strateg i es for the general public. The pro j ected dose at t he s it e boundary is_ 5 Rem T hyroid COE. The ti me is ______ (24-hr time). Message rece i ved by: Vi rg i n i a E OC Watch Officer (name) _______________

_

FigureG.3 Radiological Status Form ~-MIDAS~ Method (circle one): Monjtor Reading Plume Correlation A. MIDAS PROJECTION: .to~ naiu., rim 'th y COE mn. .. RATIO T£DEiO'OE at oeakDD B PLUME ARR[VAL f ro m tart o fret= NAEP Page 6.14 Revision # TBD Prepared by: ___ _ Re vimvodby: ____ _ Jla\a!Jbmr;

____ _ :Rnflln: ____ _ What-If (HypotheticaQ am rem lOl&al .__ __ __,._x_t Q ___ s_e_cJ_m_3...__ ____ sc_cl_n_13_._

____ sccl __ m_:S..._, _ __s .m.;. __ 3......._ ____ se_: cl--'m_3_, Distance to which 4-hour TEDE e x ceeds I rem: Miles Distance to which 4-hour Thyroid CO E exceed s 5 rem: . *1es % ofTcchnical Specification

( 8:IS<d o n S it e ll ou ndar)* Dose Rac es) Remarks: B. RELEASE DESCRIPTION:

Site: Reactor Shutdown Time: Start of Release Time: Remaining Release Duration (t Pathway: Plume Height (0): Percent of Plume on Ground: Noble Gas Release Rate (Ci/sec):

Radio.iodine Release Ra te C i/sec) Partlwtate Re ease.Rate Ci/sec}: o/o of TS for lo of TS for Th y COE hours since Reactor s hutdown 1'otal Release Durati o n (h r) GROUND PROCVNT TEAM VENTVNT TOTAL C, METEOROLOGICAL CONDITIONS!

Time Period: WWDiral\m~ Wind Speed (mph):

Figure 6.4 RADIOLOG I CAL STATUS NAEP Page 6.15 Revision # TBD Complete bas ed on in f ormatio n available whe n form prepared.

Report 'It:. -------Prepared b y: ______ _ A U m/Re l ease Stat u s: S it~ North Anna A1fected U * (s)/Area: 1; 2; lS F SI Unit 1: Power ___ %; Reac o r ShutlOY,1n Date I T ime: ____ ----~ Un it 2: Power %; Reac o r Shutlown Date /T ime: ____ *----~ D NIA ON/A Release in progress: o No; U n it 1 , Date/ Ti me Release S ar~d: ____ f, ____ _ o No: U n it 2, Date/ Ti me Release StarEd: ___ / ____ _ ONo; Other , _____ Oate/Tl!l1e: ___ / Release Pathwa y: _______ ; o Unknown Release O l.l"at ll.. '~ , . __

• U n known Release Pahwa y:

• o Unknown Release D 11 ation , o Unkno.,.,11 B. Metecrological Conditions as of ____ (24-time) Average LCM*e r ind dir ec t io n is from __ degree, * .., , o*) Average LO,Ne r Wind Speed is ____ n~; 00,Nr od Sect. .s ___ _ Average Uppe r Wind di r ec t ion is from__ ")ree, .J 360") Average Uppe r 1od Speed is ____ Ill-* Do. 'l'ind Secb r is ___ _ Stl b H Class is __ ......, A.mti eo en,, *at u re i s ____ deg r ees F Precipilatlon

D None; D Rai n~ D s ,. '* '*

• 0 O t her ______ _ C. Radiological Conditions base o, , *":it>l e a~ O On-sii! SLl"Vf!'/ results indi~ _ 3'n kl r at ___________ (l ocation). Additiona l irlow-* . ., will be * ,ided when avai l able. 0 Off-siEsi.rvr resuts jr,..<;rate ___ r ern.tirat

___________ (l ocalion). Additiona l ir , ml~ ' .vu, pn. ,ided when avai l able. o No survey i nfomiation , ext , ia l exposure es ima t es dos im etry informa io n o r a ny radlolog l cal in fcrn* .. -.iva l lable. o ___________________

___________ _ D. Remarks:-----------------------------

Reviewoo by: _____________

_ _ Radologica l Assessmeot D i rector or Raciok>gical Assessmen t Coordina t or Da t e/ r ime

.----------------

---~---~~-FIGURE 6.5 NORTH ANNA POWER STATION 10 -MILE EMERGENCY PLANNING ZONE (EPZ) NAEP Page 6.16 Revision # TBD FIGURE 6.6 Rt. 700 !Mineral!

NAPS NORTH ANNA POWER STATION REMOTE ASSEMBL V AREAS North Anna Dam: Secondary Remote Primary Remote Assembly Area

• Assembly Area ,-Rt. 54 NAEP Page 6.17 Revision # TBD Patrick Henry High School (Evacuation Assembly Center) G raphic, N o. S B1 2 128 PRIMARY REMOTE ASSEMBLY AREA: PROCEED TO INTERSECTION OF RT. 700 AND 618. TURN RIGHT ON RT. 618 AND PROCEED 0.3 MILES TO RT. 700 AND TURN LEFT. PROCEED 1.3 MILES AND TURN LEFT ON SACRED HEART AVENUE. PROCEED 0.5 MILES TO THE ANIMAL SHELTER ACCESS ROAD ON THE RIGHT. TURN RIGHT. THE ENTRANCE TO THE ASSEMBLY AREA (LOUISA FIRE TRAINING CENTER) I S ON THE LEFT. SECONDARY REMOTE ASSEMBLY AREA: PROCEED TO INTERSECTION OF RT. 7 00 AND 652. TURN LEFT ON RT. 652 AND PROCEED TO RT. 622. TURN LEFT ON RT. 622 AND PROCEED TO RT. 70 1. TURN LEFT ON RT. 701 AND PROCEED TO RT. 60 1. TURN LEFT ON RT. 601 AND PROCEED 0.1 M I LES. THE ASSEMBLY AREA IS ON THE LEFT , T H ROUGH THE GA T E , AT THE DAM.

Part 7.0 7.1 7.1.1 7.1.2 7.1.3 7.1.4 7.1.5 7.1.6 7.1.7 7.2 7.2.1 7.2.1.1 7.2.1.2 7.2.1.3 7.2.1.4 7.2.2 7.2.2.1 7.2.2.2 7.2.2.3 7.2.2.4 7.2.2.5 7.2.3 7.2.4 NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 7 EMERGENCY FACILITIES AND EQUIPMENT Subject Emergency Facilities and Equipment Emergency Response Facilities Control Room Operational Support Center Technical Support Center Corporate Emergency Response Center Joint Information Center and Local Media Center Alternate Facility When Under Threat or Experiencing Hostile Action Near-Site Location For Offsite Agency Coordination Communications Systems Communications Systems Within the Station Public Address and Intercom System Radio Communications System (Onsite) Private Branch Telephone Exchange (PBX) Sound Powered Telephone System Offsite Communications Systems Commercial Telephone Synchronous Optical Network (SON ET) Ring Radio Communications System (Offsite)

Dedicated NRC Communications lnsta-phone Loop Communications System Reliability Emergency Response Facility Communications NAEP Page 7.1 Revision # TBD Page No. 7.3 7.3 7.3 7.3 7.3 7.4 7.4 7.4 7.4 7.5 7.5 7.5 7.5 7.5 7.5 7.6 7.6 7.6 7.6 7.6 7.7 7.7 7.7 Part 7.3 7.3.1 7.3.2 7.3.3 7.3.4 7.3.5 7.3.6 7.4 7.5 7.6 Table 7.1 Table 7.2 Figure 7.1 Figure 7.2 Subject Assessment Facilities Available Onsite Seismic Monitoring Radiological Monitoring Meteorological Monitoring Plant Process Parameter Monitoring Fire Detection Post Accident Sampling Assessment Facilit i es Available Offsite Damage Control Equipment and Supplies Early Warning System ERF Communications Meteorological Monitoring System Parameters Environmental Monitoring Locations Map Environmental Monitoring Locations Listing NAEP Page 7.2 Revision # TBD Page No. 7.7 7.7 7.8 7.9 7.9 7.9 7.9 7.10 7.10 7.10 7.12 7.14 7.15 7.16

7.0 EMERGENCY

FACILITIES AND EQUIPMENT NAEP Page 7.3 Revision # TBD The facilities required in the implementation of the Emergency Plan consist of the Control Room (shared for both Unit 1 and 2), the Operational Support Center (OSC), the Technical Support Center (TSC), and the Corporate Emergency Response Center (CERC). These facilities were designed to meet the intent of the guidance in NUREG-0696 and the clarification in NUREG-0737 Supplement

1. In addition , a Joint Information Center (JIC) and a Local Media Center (LMC) are required for the implementation of the Emergency Plan. A description of each is given below. 7.1 EMERGENCY RESPONSE FACILITIES 7 .1.1 Control Room The Control Room of the affected unit(s) shall be the initial location for command and control of the emergency response effort. All controls and instrumentation needed to diagnose plant conditions and to take immediate actions to place the affected unit(s) in a safe condition are available in the Control Room. Within the Control Room , the Station Emergency Manager has access to the information needed to classify the emergency.

Redundant communication systems are also available in the Control Room to make the required onsite and offsite notifications.

The Control Room has the required shielding and ventilation system to remain habitable during the emergency.

Access to the Control Room shall be limited to those individuals responsible for carrying out assigned emergency response tasks plus other technical advisors, as necessary.

7.1.2 Operational

Support Center The Work Control Center is designated as the Operational Support Center (OSC). The OSC is not designed to remain habitable under all projected emergency conditions

however , implementing procedures make provisions for relocating the OSC as needed , based on ongoing assessments of plant conditions and facility habitability. The Maintenance Building, 3r d Floor , and the Unit One Emergency Switchgear Room are designated as Alternate OSCs. Augmenting Station operations personnel will report to the primary OSC until instructed by the Shift Manager/SEM to perform a required emergency function.

The OSC is also the designated reporting location for the Fire Brigade , the First Aid Team, the Damage Control Team , and the Search and Rescue Team. 7.1.3 Technical Support Center The Technical Support Center is located adjacent to Unit 1 Control Room , and its alternate location is the Control Room. Emergency response personnel will assemble at the primary TSC unless otherwise instructed by the Station Emergency Manager. The primary location contains controlled copies of selected manuals, procedures , drawings, and other documents as approved by the Facility Safety Review Committee.

Information about plant conditions is available via real time data displays from the Plant Computer System (PCS). Dedicated phone line communications would also be established with the Control Room to keep TSC personnel knowledgeable on current operating evolutions and to provide consultation and recommendations to the Control Room staff.

NAEP Page 7.4 Revis i on # TBD The construct i on of the faci l i t y walls and design of the ven ti lat i on sys t em are such t hat the whole body and thyroid doses received by occupants of t he TSC are below General Des i gn Cr i teria 19 l im i ts. Radiat i on mon i toring equipment for making airborne particulate and direct radiation measurements is installed in the TSC. 7 .1.4 Corporate Emergency Response Center The CERC is the consolidated emergency operat i ons facility (EOF) fo r North Anna Power Station and Surry Power Station. The CERC is located at the Innsbrook Technical Center in Glen Allen , Virginia.

The facility provides work stations for Corporate , Federal and State officials who may be assembled at this location. This facility is the designated central collect i on point for the receipt and analys i s of all field monitoring data and the coordination of sample media. Plant data i s available from the PCS. The Meteorological Information and Dose Assessment System (MIDAS) is used to estimate offsite doses. 7.1.5 Joint Information Center and Local Media Center Official company statements to the med i a will be made from Joint Information Center (JIC) by the Chief Technical Spokesperson. The pr i mary JIC is located at the Virginia State Police Administrative Headquarters in Chesterfield , Virginia. These company statements are prepared at the CERC. A Local Media Center (LMC) may be act i vated as an ad j unct to the JIG. The Local Media Center for North Anna Power Station is located at the end of Route 700 on company property. The facility is designated as the North Anna Nuclear Information Center in normal operation.

There are dedicated rooms fo r Dominion , NRG , FEMA , State , and media r epresentatives as well as an auditorium that will accommodate 200 people. Provisions have been made to accommodate TV cameras , copying machines , typewriters , and other equipment needed for press conferences. Should the Local Med i a Center become un i nhabitable , small groups of the Media , no more than 20 , can be accommodated in the CERC with the approval of the Corporate Response Manager. 7.1.6 Alternate Facility When Under Threat or Experiencing Hostile Action The Louisa Fire Training Center functions as a staging area for augmentat i on of emergency response staff if the site is under threat of or experiencing host i le action. Th i s location has the capab i l i ty to communicate w i th the CERC , control room , and plant security. The CERC has the capability to perform offs i te notifications. The staff at the staging area , working with CERC organization , provides capability for engineering assessment activities , including damage control team planning and preparation. 7.1.7 Near-Site Location For Offsite Agency Coordination The North Anna Nuclear Information Center is the location fo r the NRC and other offsite agency staff to interact face-to-face with emergency response pe r sonnel entering and leaving the nuclear power reactor site. This area provides a conference area with whiteboards , separate areas suitable for briefing and debriefing response personnel , telephones , site contact lists , computers with internet access , access to a copier and office supplies , and access to plant data and radiological information.

These p r ovisions exist because the CERC is located more than 25 miles from the TSC.

7.2 COMMUNICATIONS

SYSTEMS NAEP Page 7.5 Revision # TBD The station communications system is designed to provide redundant means to communicate with all essential areas of the station associated with North Anna Units 1 and 2 and to essential locations remote from the station during normal operation and under accident conditions.

Communication systems vital to Units 1 and 2 operation and safety are designed so that failure of one component would not impair the reliability of the total communications system. This is accomplished within the Station by using diverse systems and designated personnel.

7.2.1 Communications

Systems Within the Station The systems which provide for communications within the Station are discussed below. 7.2.1.1 Public Address and Intercom System A five channel public address and intercom system (Gai-Tronics System) is installed in the Station. The system power is supplied from a power supply which will maintain the system in an operational condition in the event of a normal station service power failure. Zones are provided within that Station to insure operability of a major portion of the system should equipment in a zone become inoperative.

Loudspeaker and paging phone stations are located throughout the Station. The coverage of the loudspeakers permits broadcasts to be heard throughout the station. A visual indicator has been installed in those areas where evaluation of NRC Bulletin 79-18, Audibility Problems Encountered on Evacuation of Personnel from High-Noise Areas , identified noise levels which might exceed the volume of the loudspeakers. In the event of an emergency, the system is used to alert Station personnel of any emergency situation and to direct emergency response actions required of on-site personnel.

7.2.1.2 Radio Communications System (Onsite) An Ultra-High Frequency (UHF) two-way radio trunking system is provided at the Station consisting of base stations/repeaters, mobile units installed in emergency vehicles , and hand-held portable radios. The radio trunking system provides redundancy and independent emergency backup equipment for designated station functions.

7.2.1.3 Private Branch Telephone Exchange (PBX) A Private Branch Telephone Exchange (PBX) is installed at the Station. The PBX switching equipment is physically located in the PBX Build i ng and is connected to a commercial telephone exchange in Mineral, Virginia.

Backup battery power is provided to maintain the system operable 6 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following the loss of A.C. power. 7.2.1.4 Sound Powered Telephone System A sound powered telephone communications system is installed which serves North Anna Units 1 and 2. This system is a multiple channel system connect i ng selected operating areas of the plant. Headsets consisting of an earphone and microphone are connected to a two wire channel for direct communication between persons in different areas. Operation of this system is not dependent on the availability of the electrical power system. During an emergency , the system would provide an alternate means of relaying messages.

7.2.2 Offsite

Communications Systems NAEP Page 7.6 Revision # TBD Those systems provided fo r commun i cat i on between the Station and offsite are descr i bed below: 7.2.2.1 Commercial Telephone Commercial telephone lines are provided between the Stat i on and a commercial telephone exchange in Mineral , Virginia. These lines are connected into the Station PBX. In addition , lines are provided for communications between the Station and the commercial telephone network which are independent of the Station PBX. 7.2.2.2 Synchronous Optical Network (SONET) Ring The SONET ring provides Wide Area Network (WAN) connectivity , voice/Automatic Ring Down (ARD) phone and radio control circuits between stat i on emergency response facilities and the CERC , and the Commonwealth of Virginia Emergency Operations Center (VEOC). The VEOC is linked to the SONET ring via a dedicated microwave facility.

The SONET ring and associated microwave facility provide the communication link from the VEOC to the Early Warning System (EWS) transmitter located at North Anna. The SON ET ring and associated microwave facility are DC powered with either battery back up o r generator back up at each location for extended operat i on upon loss of AC powe r. 7.2.2.3 Radio Communications System (Offsite)

The same UHF two-way radio trunking system that prov i des onsite commun i cations also prov i des for communications within a ten mile rad i us of the Stat i on. During an emergency , this system will allow direct contact with Radiation Monitoring Teams , Secur i ty veh i cles , and a separate channel (T alk Group) between the Secur i ty Central Alarm Stat i on and the Louisa County Sheriff's Department.

7.2.2.4 Dedicated NRC Communications Separate telephone lines are dedicated to the NRG and include the following:

• Emergency Not i fication System (ENS): The ENS is t he system on which ini t ial notifications , as well as ongoing information about plant systems , status and parameters , a r e provided to the NRG. ENS lines are located in the Control Room , TSC and CERC.

• Health Physics Network (HPN): Provides for communications regarding radiological and meteorological conditions , assessments , trends , and protect i ve measures. HPN lines are located in the TSC and CERC.

• Reactor Safety Counterpart Link (RSCL): Allows for internal NRG d i scuss i ons r egarding plant and equipment conditions. RSCL lines are located in the TSC and CERC.

• Protective Measures Counterpart Link (PMCL): Allows for the conduct of internal NRG d i scussions on radiological releases , meteorological condit i ons , and protective measures. PMCL lines are located in the TSC and CERC.

• Emergency Response Data System (EROS) Channel: Allows transmittal of reactor parametr i c data from the site to the NRG. EROS data is transmitted from the PCS computer, via modem, to the NRG Operations Center. N OTE: R e pl ace m e n t of references t o a mo d em wi th a virt u al p rivate n e t work is b eyo nd th e scope of t hi s li ce n se a m e ndm e n t re qu est.

NAEP Page 7.7 Revision # TBD

• Management Counterpart Link (MCL): This system has been established for internal discussions between the NRG Executive Team Director/members and the NRG Director of Site Operations or licensee management.

MCL lines are located in the TSC and CERC.

• Local Area Network (LAN) Access: Provides access to the NRG local area network. Telephone jacks are provided in the TSC and CERC for NRG LAN access. 7.2.2.5 lnsta-Phone Loop A County and State Ringdown Loop (lnsta-Phone) has been installed that permits simultaneous telephone-speaker communications from the Station to the Counties of Louisa, Spotsylvania, Orange, Caroline , and Hanover and the VEOC on a 24-hour per day basis. This loop can be activated at the Station from the Control Room, TSC, or CERC. 7.2.3 Communications System Reliability A failure of one communication system will not affect the operation of other communications systems at the station. The communications systems within the Station have diverse power supplies. The public address system has an emergency backup, and the sound powered phone system does not rely on any station power system. Since the onsite communication systems normally will be in use , or periodically tested , equipment failure will not go unnoticed.

The multiplicity of onsite communications networks ensures the availability of adequate communications.

Equipment for these systems is located in different areas of the Station thus ensuring that an accident in one area of the Station would not incapacitate all communication systems. Failure of normal power supplies will not deprive the station of offsite communication capability since, in most cases, backup power is provided.

Dedicated telephone lines are checked according to specified schedules. 7.2.4 Emergency Response Facility Communications The communication systems discussed above are used extensively in the Emergency response facilities. A summary of the types of communications is provided in Table 7.1. 7.3 ASSESSMENT FACILITIES AVAILABLE ONSITE A number of instrumentation and monitoring systems are available onsite for emergency assessments. These systems are described below. 7.3.1 Seismic Monitoring The Seismic Monitoring System is designed to detect the occurrence of an earthquake at the North Anna site, to alert the Control Room via panel indications and annunciation, and to provide records of the intensity , duration , and frequency of the earthquake.

Detection devices are located in several locations , including the Unit 1 Containment , Auxiliary Building , and a free-field sensor at the meteorological tower. The system collects information related to the ground motion experienced which is used to promptly determine the response of those structures important to safety to permit comparison of such response with that used as the design basis.

7 .3.2 Radiological Monitoring NAEP Page 7.8 Revision # TBD The installed Radiation Monitoring System (RMS) consists of process monitors and area monitors which read out and record in the Control Room. The process system continuously monitors selected lines for radioactive effluents.

The system's function is to warn personnel of increasing radiation levels , to give early warning of a system malfunction , and to record and control discharges of radioactive liquids and gases to the environment.

High range process monitors are installed to provide accurate indication of plant releases during and following an accident.

The flow paths monitored include the ventilation vents , the process vent (part of the Gaseous Waste System), the main steam lines, and the turbine driven auxiliary feedwater pump exhaust. High range area monitors , located inside the containments, are installed to provide additional information on core integrity during and after a design basis accident.

In addition to the fixed radiation monitoring equipment , portable radiation monitoring equipment would be used to perform dose assessments. The equipment consists of low and high range instruments to measure gamma , alpha , beta , and neutron radiation.

This equipment is maintained by the Radiological Protection Department and is used on a routine basis. Portable gamma detection instrument are also dedicated for emergency kit use (See Appendix 10.5). The kits are set aside solely for emergency use and are inventoried and checked for calibration and operability on a quarterly basis. Portable equipment is also available to take low or high volume air samples. Battery operated air samplers can be used to collect low volume samples either onsite or offsite. Silver Zeolite cartridges would be used for sampling radioiodine with a minimum detectable activity capability of 5X1 o-8 microcuries per cc. Silver Zeolite has a low retention efficiency tor Xenon and therefore, interference should be minimal. Plastic bags and bottles are available to collect water , soil , foodstuffs or other samples. Emergency Plan Implementing Procedures provide the methodology for determining the magnitude of a release by three separate and independent methods: (1) using data or samples continuously obtained by the onsite Radiation Monitoring System , (2) using known inventory data for the system(s) affected and (3) obtaining offsite data from air samplers or dosimeters which are continuously in place , or taking radiation surveys and appropriate samples , and using this data to calculate releases.

Equipment designated for use in environmental surveillance such as air samplers and thermoluminescent dosimeters (TLDs) is used to obtain oftsite data. The radiological monitoring instrumentation and sampling devices used by the station meet the minimum requirements of the NRG Radiological Assessment Branch Technical Position for Environmental Radiological Monitoring Programs.

Two TLDs have been placed in each of the 16 sectors within an approximate 5 mile radius of the station for environmental monitoring. Eight (8) TLDs are located beyond five miles from the station and are used to establish normal background radiation levels. Further details can be found in VPAP-2103N , Offsite Dose Calculat i on Manual (North Anna). The State also has TLD monitoring points located around the Station used for verification purposes. Dosimetry and air sampler locations within the 10 mile EPZ are shown on Figures 7.1 and 7.2.

NAEP Page 7.9 Revision # TBD North Anna maintains fixed laborato r y equipmen t t o support samp l ing analys i s and monitoring.

The equ i pment i ncludes Multichannel Analyzers , proportional counters , a tritium analyzer , and whole body counters; arrangements are maintained for reading TLDs. 7.3.3 Meteorological Monitoring The station's Meteorological Monitoring System provides the capabil i ty for p r edicting atmospheric effluent transport and diffusion.

The sys t em consists of a primary and a backup tower , the locations of which were chosen so as to be representative of regional conditions. Instruments located at these towers prov i de data to MIDAS via the PCS. The data is also transmitted to the Control Room and to the company's Weather Center. Table 7.2 prov i des a listing of the parameters measured. The meteorological equipment was designed to meet the criteria of Regulatory Guide 1.23 , " On Site Meteorological Programs" , dated February 1972. 7.3.4 Plant Process Parameter Monitoring Installed i n the Control Room are the necessary instrumentation readouts to assess stat i on status under all conditions.

Information is available from meter displays , chart recorders , annunciators, and the plant process computers to assist the operator in contending w i th accident conditions. In order to support the data acquisitions need of the emergency r esponse facilities , the PCS has been installed. The PCS provides plant monitoring , data acquisition , and critical plant data in the form of real-time status displays for the purpose of making a rapid eva l uation of the reactor plant's safety status. The PCS includes the Safety Parameter Display System (SPDS), Emergency Response Guidelines (ERGs), process and instrument displays , and pressure-temperature plant displays.

Monitor disp l ays a r e cont i nuously updated by the computer systems as they collect and process parametr i c data from the various plant sensors. The PCS host computers are housed in the TSC. These units process inputs from plant sensors and distribute information via the station LAN and corporate Wide Area Network (WAN). The information is available any LAN/WAN-connected PC which has the appropriate software and secur i ty level for access, including the Control Room , TSC , and CERC. 7.3.5 Fire Detection The Station's Fire Protection System is designed to furn i sh water and other extinguishing agents with the capability of extinguishing any single or probable combinat i on of s i multaneous fires that might occur. Smoke and heat detectors are utilized for fire detection resulting i n automatic fire suppression initiation and/or alarming.

These systems are designed in accordance with the standards of the National Fire Protection Association.

7.3.6 Post Accident Sampling A contingency plan , controlled by normal Chemistry procedures , has been developed for obtaining and analyzing highly radioact i ve samples of reactor coolant , containment sump , and conta i nment atmosphere. (Reference NRC Letter , Subjec t: North Anna Power Stat i on , Un i ts 1 and 2 -Issuance of Amendments Re: Elimination of Post-Accident Sampl i ng System Requirements , dated December 19 , 2001 , Serial No.01-760)

7.4 ASSESSMENT

FACILITIES AVAILABLE OFFSITE NAEP Page 7.10 Revision # TBD The facilities and equipment located at the Surry Power Station may be utilized as applicable during emergency conditions at the North Anna Station. Additional seismic and meteorological data would be available.

Respiratory protection , portable radiation detection instrumentation , and count room and sample analysis facilities would also be made available. Seismic data may be obtained from the National Earthquake Information Service. Meteorological data can be obtained from the following sources: DISTANCE FROM LOCATION ORGANIZATION NORTH ANNA (MILES) Chesterfield Dominion 56 Wakefield, Virginia National Weather Service 82 Charlottesville Federal Aviation Administration 43 Dulles Airport National Weather Service 65 The State Health Department has equipped a mobile laboratory with radioassay equipment to respond to radiation emergencies.

This vehicle is equipped with a radio to facilitate coordination between the State and the company's offsite monitoring teams. 7.5 DAMAGE CONTROL EQUIPMENT AND SUPPLIES The Station maintains an adequate inventory of spare parts, equipment and supplies, and could rely on additional equipment and supplies from the Surry Power Station. Such equipment and supplies consist of full face respirators with proper filters or canisters, SCBA respirators, air supplied respirators, silver zeolite cartridges (radioiodine sampling), portable survey instruments , protective clothing and auxiliary apparel, portable sampling equipment , TLDs self-reading dosimeters , count room instrumentation , polyethylene bags and bottles, radiation signs and rope, radioactive waste containers , ion-exchange resin (liquid waste processing), portable hand-held 2-way radios , portable lighting equipment, and Company-owned vehicles.

This equipment is normally stored either in the Health Physics office and/or warehouse to facilitate transfer to the Operational Support Center as needed. Equipment specifically designated for emergency response is inspected and inventoried at least once a quarter. Portable survey instrumentation is calibrated in accordance with manufacturer's recommendations, and count room instrumentation is calibrated annually (source checked daily). 7.6 EARLY WARNING SYSTEM The company has installed and is responsible for maintaining and periodically testing an Early Warning System (EWS) consisting of sirens located throughout the 10 mile EPZ. The purpose of this system is to ensure that essentially 100% of the population within 5 miles of the site can be alerted within 15 minutes and that essentially 100% of the population from 5 to 1 O miles from the site who may not have received the initial notification can be alerted within 45 minutes. The Federal Emergency Management Agency (FEMA) has determined that the system satisfies the requirements of NUREG-0654/FEMA-REP-1 , Revision 1 , and FEMA-REP-10.

NAEP Page7.11 Revision # TBD The state and local governments have ultimate responsibility for warning the public. Should it be necessary , state and local authorities will alert the public within the 10 miles EPZ using alternative methods described in the COVEOP. Members of the public within the ten (10) mile EPZ shall be informed of what actions to take following activation of the EWS sirens. Upon hearing the alert , they have been instructed to turn on their radios or television sets to the Emergency Alert System (EAS) to receive further instructions.

Louisa and Spotsylvania counties and the State have 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day capability to activate the EWS system. Messages sent out over the EAS are prepared by VDEM.

TABLE 7.1 ERF COMMUNICATIONS Control Room 1. ARD to TSC , OSC , Security , System Operator , VEOC 2. lnsta-phone Loop to State and Country EOCs 3. Station PBX Phones 4. OPX Phone (General Office Network) 5. Radio System 6. NRC Emergency Notification System (ENS) 7. Commercial Phones (Independent of Station PBX) 8. Public Address/Intercom (Gai-tronics)

9. Sound Powered System 10. Emergency Response Data System (EROS) Channel Technical Support Center (TSC) NAEP Page 7.12 Revision # TBD 1. ARD to Control Room , OSC , CERC , Security , Prima r y Remote Assembly Area , VEOC 2. lnsta-Phone Loop to State and County EOCs 3. Commercial Phones (Independent of Station PBX) 4. Radio System 5. Station PBX Phones 6. OPX Phone (General Office Netwo r k) 7. NRC Emergency Notification System (ENS) 8. Public Address/Intercom (Gai-tronics)

9. Sound Powered System 10. NRC Health Physics Network (HPN) 11. NRC Reactor Safety Counterpart Link (RSCL) 12. NRC Protective Measures Counterpart Link (PMCL) 13. NRC Emergency Response Data System (EROS) Channel 14. NRC Management Counterpart Link (MCL) 15. NRC Local Area Network (LAN) Access Operational Support Center 1. Public Address/Intercom (Gai-Tronics)

2. Station PBX Phone 3. ARD to TSC , Control Room , HP Corporate Emergency Response Cente r (CERC) 1. ARD to TSC , LMC , and VEOC 2. lnsta-Phone Loop to State and County EOCs 3. Commercial Phones (Independent of Station PBX) 4. Radio System 5. Station PBX Phones 6. OPX Phone (General Office Network) 7. NRG Emergency Notification System (ENS) 8. NRG Health Physics Network (HPN) 9. NRG Reactor Safety Counterpart Link (RSCL) 10. NRG Protective Measures Counterpart Link (PMCL) 11. NRG Management Counterpart Link (MCL) 12. NRG Local Area Network (LAN) Access Local Media Center (Located in North Anna Nuclear Information Center) 1. Commercial Phones (Independent of Station PBX) 2. ARD to CERC News Room 3. NANIC PBX Phones 4. OPX Phones (Station PBX and General Office Network) 5. Media Conferencing Network 6. Central Office (CO) leased phone lines Legend ARD -Automatic Ringdown OPX -Off-Premises Exchange ENS -Emergency Notification System (NRG) PBX -Private Branch Exchange VEOC -Virginia Emergency Operations Center NAEP Page 7.13 Revision # TBD Measurement Wind Speed W i nd Direct i on Sigma-theta Temperature D i ffe r ential Temperature Dew Po i nt Temperature Precipitation (1) (2) TABLE 7.2 NAEP Page 7.14 Revision # TBD METEOROLOGICAL MONITORING SYSTEM PARAMETERS 11> Primary Tower Backug Tower Control Rm. 48.4 Meters. 1 O Meters Ground 10 Meters. Readout X X X X X X X X X X X x (2> X X X X X X X All data available via dial-up link at Meteorological Operations in R i chmond. Signal from Backup Tower only.

FIGURE 7.1 NORTH ANNA POWER STATION MONITORING LOCATION MAP NAEP Page 7.15 Revision # TBD NOTE: Specific locations are provided in Figure 7 .2. Locations within one-half mile not displayed.

NAEP Page 7.16 Revision # TBD FIGURE 7.2 NORTH ANNA POWER STATION MONITORING LOCATION LISTING Sam1;1le Media Location Station # Distance Direction Remarks (miles) Environmental Bearing Cooling Tower N-1/33 0.06 N On-Site (TLDs) Sturgeon's Creek Marina N-2/34 2.04 N Parking Lot " C" NNE-3/35 0.24 NNE On-Site Good Hope Church NNE-4/36 3.77 NNE NAPS Waste Treatment Plant , end of parking lot B NE-5/37 0.20 NE On-Site Boggs Drive NE-6/38 1.46 NE Weather Tower Fence ENE-7/39 0.36 ENE On-S ite Route 689 ENE-8/40 2.43 ENE Near Train ing Facility E-9/41 0.30 E On-Site " Morning Glory H ill" E-10/42 2.85 E Is land Dike ESE-11/43 0.12 ESE On-Site Route 622 ESE-12/44 4.7 0 ESE Biology Lab SE-13/45 0.64 SE On-Site Route 701 (Dam Entrance) SE-14/46 5.88 SE " Aspen Hills" SSE-15/47 0.93 SSE Site Boundary Elk Creek SSE-16/48 2.33 SSE NAPS Access Road S-17/49 0.36 s On-Site Elk Creek Church S-18/50 1.55 s NAPS Ac cess Road SSW-19/51 0.24 SSW On-Site Route 618 SSW-20/52 5.3 0 SSW 500KV Tower SW-21/53 0.60 SW On-Site Route 700 SW-2 2/54 3.96 SW At NAPS, on pole , SE of switchyard , entrance on Rt. 700 WSW-23/55 0.38 WSW On-Site Route 700 WSW-24/56 1.00 WSW Si te Boundary South Gate of Sw itchyard W-25/57 0.32 w On-Site Route 685 W-26/58 1.55 w End of Route 685 WNW-27/59 1.00 WNW Site Boundary Route 685 WNW-28/60 1.40 WNW Laydown Area North Gate NW-29/61 0.52 NW On-Site Lake Anna Campground NW-30/62 2.54 NW #1/#2 Intake NNW-31/63 0.07 NNW On-Site Route 208 NNW-32/64 2.21 NNW Bumpass Post Office C-1/2 7.30 SSE Orange , Va. C-3/4 22.00 NW Control Mineral, Va. C-5/6 7.10 WSW Louisa, Va. C-7/8 11.54 WSW Control Airborne NAPS Waste Treatment Plant , Part i culate and end of parking lot B 01 0.20 NE On-S i te Radioiod ine Biology Lab 01-A 0.64 SE On-S i te Freder ick's Ha l l 02 5.30 SSW Minera l, Va. 03 7.10 WSW Wares Crossroads 04 5.10 WNW Route 752 05 4.20 NNE Sturgeon's Creek Marina 05A 2.04 N Levy , Va. 06 4.70 ESE Bumpass , Va. 07 7.30 SSE End of Route 685 21 1.00 WNW Site Boundary Route 700 22 1.00 WSW Site Boundary " Aspen Hills" 23 0.93 SSE Site Boundary Orange , Va. 24 22.00 NW Control Source Document VPAP-2103N , Rev 27 , Atta chment 10 , Environmental Samp ling Locations.

Part 8.0 8.1 8.2 8.2.1 8.2.2 8.2.3 8.2.4 8.2.5 8.2.6 8.3 8.3.1 8.3.2 8.3.3 8.3.4 8.3.5 8.3.6 8.4 8.5 8.5.1 8.5.2 8.5.3 8.5.4 8.5.5 8.5.6 NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 8 MAINTAINING EMERGENCY PREPAREDNESS Subject Maintaining Emergency Preparedness Responsibility for Maintaining Emergency Preparedness Maintenance of the Emergency Plan , Emergency Plan Implementing Procedures , and Emergency Personnel Notification List Annual Review of the Emergency Plan and Emergency Plan Implementing Procedures Review of the Emergency Personnel Notification List Revision of the Emergency Plan Maintenance of Emergency Plan Implementing Procedures Distribution of Emergency Plans Review of Evacuation Time Estimates Training of Emergency Response Organization Personnel Responsibilities for Maintaining Emergency Preparedness Training Nuclear Employee and Visitor Training Emergency Response Personnel Training Cognitive Evaluations Task Performance Evaluations Training Records Training Offsite Support Personnel Emergency Drills Communications Drills Fire Drills Medical Emergency Drills Environmental Monitoring Drills Radiological Monitoring Drills Combined Functional Drills NAEP Page 8.1 Revision # TBD Page No. 8.3 8.3 8.4 8.4 8.4 8.4 8.4 8.5 8.5 8.5 8.6 8.6 8.7 8.7 8.7 8.7 8.8 8.8 8.9 8.10 8.10 8.10 8.10 8.10 Part 8.6 8.6.1 8.6.2 8.6.3 8.6.4 8.6.5 8.6.6 8.7 8.8 8.9 Table 8.1 Subject Emergency Exercises Scheduling of Emergency Exercises Emergency Exercise Content Emergency Exercise Scenarios Conduct of Emergency Exercises Emergency Exercise Evaluation and Corrective Action Records of Emergency Exerc i se Testing and Maintenance of Emergency Equipment Informing the Public Independent Review of the Emergency Preparedness Program Emergency Preparedness Training NAEP Page 8.2 Revision # TBD Page No. 8.10 8.11 8.11 8.11 8.12 8.12 8.12 8.12 8.13 8.14 8.15

8.0 MAINTAINING

EMERGENCY PREPAREDNESS NAEP Page 8.3 Revision # TBD Dominion has instituted an emergency preparedness program to support development , maintenance and coordination of the company's emergency response capability.

The Emergency Plan and associated Emergency Plan Implementing Procedures , which provide specific guidance to emergency response personnel , are revised as required and reviewed at least annually in accordance with this program. Personnel who may be required to fill emergency response positions receive initial and annual training in their functional responsibilities.

Training is also provided for various offsite groups that have agreed to support the station response to an emergency. Dedicated emergency equipment is kept operational through testing in accordance with an established periodic surveillance program. Periodic drills and a biennial exercise are conducted for training and to identify program strengths and weaknesses. Additionally , the emergency preparedness program provides for the issuance of public information material.

This material provides the public with a description of the emergency notification process , and guidelines used to protect public health and safety in an emergency.

Independent reviews of the emergency preparedness program are also conducted. 8.1 RESPONSIBILITIES FOR MAINTAINING EMERGENCY PREPAREDNESS The Senior Vice President and Chief Nuclear Officer , assigned the overall authority for maintaining emergency preparedness , has delegated the responsibility for maintaining emergency preparedness to the Vice President Engineering and to the Site Vice President.

The Vice President Engineering has delegated the responsibility to the Director Nuclear Regulatory Affairs. The Director Nuclear Regulatory Affairs has delegated the responsibility to the Manager Nuclear Fleet Emergency Preparedness. The Site Vice President has delegated the responsibility to the Director Safety and Licensing.

The Director Safety and Licensing has delegated the responsibility to the Manager Nuclear Emergency Preparedness.

The primary responsibilities for maintaining the emergency preparedness program include: a) Coordinating the Company emergency preparedness program with offsite emergency response organizations b) Coordinating Company emergency preparedness planning activities c) Conducting public information and media information activities d) Coordinating emergency drills and exercises between Company departments and offsite agencies , and ensuring that they are conducted as required; e) Coordinating emergency preparedness program reviews f) Coordinating emergency preparedness activities between the stations and other Company departments g) Providing support to the stations in the area of emergency preparedness h) Obtaining letters of agreement from appropriate offsite emergency response organizations i) Coordinating the annual review of Emergency Action Levels with State and local j) Performing the annual review of the emergency plan and implementing procedures NAEP Page 8.4 Revision # TBD k) Maintain i ng the Emergency Plan , Implementing Procedu r es , and other documents related to Emergency Preparedness I) Ensur i ng distribution of copies of the Emergency Plan and Implementing Procedures to persons or organizations with responsibility for implementation of the plan or procedures m) Coordinating emergency preparedness training and ensuring that it is performed n) Ensuring that requ i red testing and maintenance of emergency equipment is performed o) Ensuring that required emergency preparedness records are maintained and filed p) Coordinating the conduct of an augmentation capability assessment at least once per calendar quarter The hierarchy for program maintenance is further outlined in VPAP-2601 , "Maintaining Emergency Preparedness". 8.2 MAINTENANCE OF THE EMERGENCY PLAN , EMERGENCY PLAN IMPLEMENTING PROCEDURES, AND EMERGENCY PERSONNEL NOTIFICATION LIST Station documents which are required to ensure emergency preparedness include: a) The North Anna Emergency Plan b) The North Anna Emergency Plan Implementing Procedures c) The North Anna Emergency Personnel Notif i cation List 8.2.1 Annual Review of the Emergency Plan and Emergency Plan Implementing Procedures Nuclear Emergency Preparedness personnel shall review the North Anna Emergency Plan and associated Implementing Procedures at least annually , certifying that they are adequate and current. Nuclear Emergency Preparedness personnel shall also review the results of independent assessments of the emergency preparedness program and critiques of exercises and dr i lls to evaluate their impact on station emergency preparedness documents. The results of these reviews shall be reported to the Facility Safety Review Committee (FSRC) and the documentation filed by Records Management.

8.2.2 Review

of the Emergency Personnel Notification List Nuclear Emergency Preparedness personnel shall ensure a review of the Emergency Personnel Notification List is performed at least quarterly , and shall ensure required revisions are made. Documentation of this review shall be filed by Records Management.

8.2.3 Revision

of the Emergency Plan In accordance with 1 OCFR50.54(q)(3), proposed revisions to the North Anna Emergency Plan shall be screened/evaluated against 10CFR50.47(b) and 10CFR50 , Appendix E , to determine whether the proposed change is a reduction in effectiveness.

Any such changes shall be submitted to the NRG for approval prior to implementation in accordance with the requirements of 10CFR50.54(q)(4).

The FSRC shall review and approve proposed revisions to the North Anna Emergency Plan. 8.2.4 Maintenance of Emergency Plan Implementing Procedures Proposed revisions to EPIPs shall be reviewed to verify the effectiveness of the emergency plan i s maintained as required by 1 OCFR50.54(q)(2).

The Manager NEP shall review and approve proposed revisions to EPIPs.

8.2.5 Distribution

of Emergency Plans NAEP Page 8.5 Revision # TBD In accordance with 1 O CFR 50.54(q)(5) revisions to the Emergency Plan shall be submitted to the NRG within 30 days following the assigned effective date. Revisions to the NAEP will also be distributed to those offsite agencies requiring copies in order to perform their emergency response functions.

8.2.6 Review

of Evacuation Time Estimates Nuclear Emergency Preparedness personnel shall ensure evacuation time estimates (ETEs) are developed within 365 days of when U.S. Census Bureau decennial data becomes available. ETEs are a factor considered in the development of off-site protective action recommendations (see Section 6.3.1) and are provided to Commonwealth and local governmental authorities for use in developing off-site protective action strategies.

ETEs are reviewed against estimated EPZ permanent resident population changes at least once a year and within 365 days of the date of the previous ETE or its most recent review. Increases of ETEs greater than the limits detailed in 1 O CFR 50 Appendix E require the ETE analysis be updated. The decennial ETE and its updates are submitted to NRG as required by 10 CFR 50 Appendix E. 8.3 Training of Emergency Response Organization Personnel The effectiveness of a response to a station emergency relates directly to the level of emergency preparedness maintained by emergency response organization personnel.

Emergency preparedness is maintained through an integrated program that includes general orientation for all persons badged at the station and additional detailed training for persons assigned specific emergency response functions to supplement the general orientation and normal job related training. The primary objectives of this emergency preparedness training program are to: a) Ensure emergency response personnel maintain familiarity with the North Anna Emergency Plan , its implementing procedures and their functional responsibilities during an emergency b) Inform emergency response personnel of their functional role and responsibilities during an emergency c) Familiarize emergency response personnel with significant changes to the North Anna Emergency Plan and its implementing procedures NOTE: Update of references to TR-NA-TPG-2400 , w hich h as been s upe rsede d , is beyond the scope of thi s lic ense amendment req ue st. NAEP Page 8.6 Revision # TBD 1Jh:;l ,.rnc:~tor conducting emergency preparedness training are met , a training program guide has b en develop Responder Training Program Guide_, or TR-AA-PG-2400 , Erne Training Program (whe .. n-..="""" provided as follows: North Anna Nuclear a. The Site Vice President is responsible for ensurin station personnel are traine

• accordance with ir'AA-TPG-2400 or TR-AA-TPG-2400 ( when issue<!) b. Department directors , managers and supervisors training.

This includes designating individuals ho may serve as primary , interim emergency response personnel and ensuring they uccessfully complete the training specified by ir RNA-TPG-2400 or TR-AA-TPG-2400 (when issued). c. The Manager Nuclear Emergency Preparedness is r sponsible for developing and scheduling training programs that meet the requirements for this plan , an for maintaining records to document the training. d. Nuclear Emergency Preparedness personnel other th those designated to develop training programs will independently check that the training required by TR-NA-TPG-2400, o n TR-AA-TPG-2400 (when i ssueg), and this plan is accomplished.

8.3.2 Nuclear

Employee and Visitor Training All persons badged to enter the Protected Area unescorted receive , as part of Nuclear Employee Training , computer-based training (CBT) and annual retraining in the following subjects: a) Station Policies and Procedures including, in part: 1) Reporting abnormal conditions (e.g., fire, first aid event, etc.) 2) Fire and First Aid alarms and announcements

3) Response to Fire and First Aid emergencies b) Radiation Protection Training including basic principles of radiological safety c) Emergency Preparedness Training Overview including: 1) General scope and overview of the Emergency Plan 2) Station Emergency Alarm and announcements

3) Response to Station Emergency Alarm 4) Personnel accountability

5) Visitor control during an emergency

6) Site evacuation

7) Emergency Plan Implementing Procedures

8) Emergency Organization

9) Emergency Control Centers (Emergency Facilities) 1 O) Emergency Action Levels As appropriate , NOTE: Update of references to TR-NA-TPG-2400 , which h as been s up ersede d , is beyond the scope of thi s lic e n se amendme nt request. accordance w i th station administrative proced 8.3.3 .=.;.a.a.a;..a,......__;..a..;a..

..............

i.....;;;.;;.;.;;;;.;;;..;....;a.;..;;;...;;;;..;;...;..;..,.._.;;..;;;.;.;.;.;.;.;.;;&

Personnel designated to fill

• erim , primary or alternate emerge training in accordance with if R-NA-TPG-2400 o TR-AA-TPG-2400 NAEP Page 8.7 Revision # TBD se positions will receive Emergency department initial training and retraining requirements for all emergency response positions.

Table 8.1 provide of select emergency response positions along with an overview of the training provided. Revisions to NA-TPG-2400 , o n TR-AA-TPG-2400 Cwhen issue f!JJ, that affect those descriptions referenced in Table 8.1 will be reflected in the next scheduled revision of this Plan. Training exemptions and equivalent qualifications for required training sessions based on an i ndividual's knowledge of the subject matter may be approved by the training program owner. 8.3.4 Cognitive Evaluations Cognitive evaluations may include self-critiques , group discussions , and/or tests administered following completion of training.

Evaluations are normally administered by the course instructor and may be scheduled at the end of a workshop , learning activity , instructional unit , or a number of related units. A m i nimum score of 70% is considered passing on tests. For training incorporated into regularly scheduled continuing training programs, the passing criteria for that training program applies. Individuals failing to successfully complete the required training within the required time interval will be relieved of their emergency response assignments. 8.3.5 Task Performance Evaluations Task performance evaluations are prescribed for individuals who must perform tasks as responders which are outside of their normal day-to-day responsibilities and may be satisfied through completion of a Job Demonstration Guide (JOG), participation in an appropriate drill , Simulator Exercise , facility training activity or included in classroom learning activities as part of the training requirement.

JOG evaluations are conducted by the applicable primary responder , team leader or instructor and are scored on a pass/fail basis. 8.3.6 Training Records The Manager Nuclear Emergency Preparedness is responsible for ensuring that required emergency preparedness training records are maintained. These records are maintained by Records Management.

The required emergency preparedness training records include: a) Program Records: Attendance sheets , master copies of Job Demonstration Guides , master copies of tests and answer keys , copies of instructor guides, training rosters and extensions. b) Trainee Records: Completed tests and responder training records.

8.4 TRAINING

OF OFFSITE SUPPORT PERSONNEL NAEP Page 8.8 Revision # TBD The various offsite organizations which support the stat i on during an emergency receive training as part of their own emergency preparedness programs. For example the State and local governments conduct training for their personnel as part of their Radiological Emergency Response Plan program. However , in order to promote effective emergency response capability , the station offers site spec i fic emergency response training on an annual basis to local offsite emergency support organizations which have agreed to provide assistance. The organizations include the Commonwealth of Virginia Department of State Police and local county sheriffs departments , volunteer fire companies , and rescue squads. The annual training shall address the following: a) The basic scope of the North Anna Power Station Emergency Plan b) Emergency classifications c) Notification methods d) Basic radiation protection e) Station access procedures f) The individual , by title , in the station emergency response organization who will direct their activities onsite g) Definition of the i r support roles Training offered to local offsite support organizations will be coordinated with Stat i on Safety and Loss Prevention or Station Security , as appropriate.

Safety and Loss Prevention , Secur i ty , and/or Nuclear Training may assist in the conduc t of offsite training.

Training records shall be maintained and filed by Records Management.

These records shall include letters of invitation (or record of telephone invitation), attendance sheets, and the curriculum outline. 8.5 EMERGENCY DRILLS As a part of maintaining emergency p r eparedness , periodic dr i lls shall be conducted.

The pr i mary objectives of drills are to: a) that facilities , equipment , and communication systems function as required b) Demonstrate the adequacy of station procedures used during an emergency c) Familiarize station emergency response personnel with planned emergency response actions d) Disclose deficiencies which may requ i re corrective action Drills may be conducted independently, in conjunction with another drill or conducted as part of an exercise. The individual responsible for the drill shall ensure that all necessary documentation is maintained.

A scenario will be developed to support the conduct of each drill. The scenario should be designed to allow for open decision-making (free-play). If a drill is conducted in conjunction w i th another drill or as part of an exe r cise , the drill scenario , objectives and narrative shall be incorporated into the overall drill/exercise package. Drill packages shall include: a) Objectives of the drill b) Evaluation criteria c) Date and time period of the drill d) Participating personnel or organizations NAEP Page 8.9 Revision # TBD e) A narrative summary describing the overall integration of scenario events (e.g., simulated casualties, offsite assistance , rescue of personnel , simulated activity levels , and deployment of monitoring teams) f) A time schedule of the real and simulated events It is not required that all emergency response personnel assigned a particular emergency function participate in a drill covering that function.

State and local governments will be allowed to participate in drills at their request. Participation by offsite organizations may be simulated. At least once every eight-year exercise cycle , at least one drill shall be conducted involving CERC response to simultaneous events at North Anna Power Station and Surry Power Station. Drills shall be controlled and obseNed by individuals qualified to conduct and evaluate the drill. Critiques will be used to document evaluation of the drill. Deficiencies identified as a result of the drill evaluation will be presented to Station Management , and corrective act i ons will be coordinated through NEP. Records of each drill will be maintained by Records Management and include the drill scenario package and the post-drill critique. Records of drills held in conjunction with an exercise may be integrated into the emergency exercise package (i.e. scope , objectives , critique , etc.). The types and frequencies of drills conducted at the station are designated below. Provisions for conducting post accident sampling drills , previously addressed herein , became obsolete upon imp l ementation of contingency plans for obtaining and analyzing highly radioactive samples of reactor coolant , containment sump , and containment atmosphere. Although these contingency plans must be available during an accident , they do not have to be carried out in emergency plan drills or exercises. (Reference NRC Letter ,

Subject:

North Anna Power Station , Units 1 and 2 -Issuance of Amendments Re: Elimination of Post-Accident Sampling System Requirements, dated December 19, 2001 , Serial No.01-760) In addition to the following drills , an augmentation capability assessment shall be performed once per calendar quarter. This activity shall assess the elements involved in notification processes for augmenting the emergency response organization.

8.5.1 Communications

Drills Communications drills shall be conducted at least once per calendar year and shall include: a) Use of emergency communications systems between the Control Room , the TSC , the CERC , the OSC , the NRC Operations Center , the Virginia EOC , the county EOCs , and the Onsite and Offsite Monitoring Teams b) Sending , receiving , and verification of message content 8.5.2 Fire Drills NAEP Page 8.10 Revision # TBD Fire drills shall be conducted in accordance with the requirements of the North Anna Fire Protection Program. 8.5.3 Medical Emergency Drills Medical Emergency drills shall be conducted at least once per calendar year and shall include: a) A simulated contaminated injured individual b) Participation by a local rescue squad c) Transport to an offsite medical facility d) Participation by the offsite medical facility 8.5.4 Environmental Monitoring Drills Environmental Monitoring drills shall be conducted at least once per calendar year and shall include: a) Collection of water, vegetation , soil , and air samples both onsite and offsite, as appropriate b) Analysis of the above samples c) Use of communications with the monitoring teams d) Use of the appropriate procedures for collecting and analyzing samples and recording results 8.5.5 Radiological Monitoring Drills Radiological Monitoring drills shall be conducted semi-annually with a maximum allowable grace period not to exceed 25%, and shall include: a) Response to simulated elevated airborne and/or liquid activity levels , as appropriate b) Response to simulated elevated area radiation levels c) Analysis of the simulated radiological situation using the appropriate procedures.

8.5.6 Combined

Functional Drills Combined Functional drills shall be conducted at least once during the interval between biennial exercises and involve a combination of some of the principal functional areas of onsite emergency response capabilities , such as: a) Management and coordination of emergency response b) Accident assessment c) Protective action decision making d) Plant system repair and corrective actions 8.6 EMERGENCY EXERCISES An emergency exercise shall be conducted with a stated scope and objectives. The primary objectives of an emergency exercise are to: a) Check the integrated capability of the various emergency response organizations to respond to an emergency b) Test a major portion of the basic elements existing within the emergency response plans and organizations c) Demonstrate the adequacy of procedures used during an emergency NAEP Page 8.11 Revision # TBD d) Provide an opportunity for emergency response personnel to demonstrate their ability to perform planned emergency response actions e) Disclose deficiencies which may require corrective action 8.6.1 Scheduling of Emergency Exercises An emergency exercise shall be conducted at North Anna Power Station at least once per biennium , normally on even numbered years. All biennial exercises must include demonstration of response to at least the Site Area Emergency classification level. At least once in every eight-year exercise cycle , a drill or exercise should be initiated between 6:00 pm and 4: 00 am. Unannounced exercises or drills are conducted on a periodic basis to the extent such exercises can be supported by affected internal and external organizations.

8.6.2 Emergency

Exercise Content Exercises are conducted on a periodic basis. The exercises allow demonstration of the key skills specific to emergency response duties in the Control Room , TSC, OSC , CERC, and Joint Information Center in order to implement the principal functional areas of emergency response. The exercises:

a) Test the adequacy of timing and content of implementing procedures and methods b) Test emergency equipment and communications networks c) Test the public notification system d) Test the familiarity of emergency organization personnel with their duties Scenarios are varied so major elements of the state , local and station plans and preparedness organizations are tested, including , at least once during the 8-year exercise cycle , the following:

a) Hostile action directed at the plant site b) No radiological release or an unplanned minimal radiological release that does not require public protective actions c) An initial classification of or rapid escalation to a Site Area Emergency or General Emergency d) Implementation of strategies, procedures , and guidance developed under §50.54(hh)(2) e) Integration of offsite resources with onsite response 8.6.3 Emergency Exercise Scenarios Each emergency exercise shall be based on a pre-planned written scenario.

The overall exercise package shall address , but not be limited to: a) Basic performance objectives of the exercise b) Evaluation criteria used to check demonstration of performance objectives c) Date, initiation time , and exercise duration d) Participating organizations e) Simulated events f) Time schedule of the real and simulated events NAEP Page 8.12 Revision # TBD g) A narrative summary describing the overall integration of scenario events such as simulated causalities , offsite assistance , rescue of personnel , use of protective equipment , simulated activity and radiation levels, and deployment of monitoring teams h) A description of the number, location , and basic duties of the controllers i) A description of the arrangements made for , and advance materials to be provided to, the controllers. Advance knowledge of the scenario shall be minimized to ensure realistic participation by those involved.

8.6.4 Conduct

of Emergency Exercises The emergency exercise will be initiated and supervised by designated controllers.

These controllers shall ensure that: a) The information supplied to the participants is of sufficient detail to allow realistic analysis of the simulated events and to provide a basis for rational decision making b) The information is supplied on a real time basis c) The exercise is not so structured as to prevent free play and independent decision making on the part of the participants

8.6.5 Emergency

Exercise Evaluation and Corrective Action Emergency exercises shall be evaluated by qualified controllers. Controllers shall be selected based on expertise , knowledge of the areas to be evaluated, and familiarity with emergency response requirements.

Personnel from federal, state , or local governments may observe the exercise.

Specific areas to be evaluated by the controllers will be defined in the form of pre-printed critique sheets. Critiques will be held as soon as practicable after the exercise.

Critiques should be attended by exercise controllers and key participants.

Notes of critique comments shall be recorded.

Controllers shall complete critique sheets documenting their observations. Critique sheets shall be submitted in accordance with the schedule established for the exercise.

Within 60 days of the exercise , a Post-Exercise Critique Report shall be issued, including suggested corrective actions. Identified corrective actions will then be assigned for implementation. 8.6.6 Records of Emergency Exercises The exercise scenario package and Post-Exercise Critique are filed by Records Management.

8.7 TESTING

AND MAINTENANCE OF EMERGENCY EQUIPMENT Emergency equipment shall be periodically tested to identify and correct deficiencies.

The specific scope and responsibilities for performing these tests are provided in administrative procedures.

For inventory purposes, an item-by-item count is not required if a mechanism is in place to assure the container has not been compromised since the previous satisfactory check. The testing shall include: a) The contents of the emergency kits dedicated for emergency use shall be inventoried quarterly and following each use.

NAEP Page 8.13 Revision # TBD b) Dedicated emergency suNey instrumentation shall be i nventoried and operationally checked quarterly and following each use. Calibration of dedicated emergency suNey instrumentation shall be performed in accordance with manufacturer's recommendations.

c) Self-contained breathing apparatus shall be inspected and operationally checked monthly and following use during an emergency.

d) State and local ringdown loop (lnsta-phone) extensions and the ringdown phone to the Virginia EOC located at the station and CERC shall be operationally checked on a monthly basis. In addition , NRC Emergency Notification System extensions and NRC Health Physics Network extensions located at the station and CERC shall be operationally checked monthly. e) A daily operability check of the Safety Parameter Display System (SPDS) f) Every 18 months , functional and performance testing of the TSC Ventilation system g) Operability testing in accordance with manufacture's recommendations and biennial calibrations of TSC radiation monitors h) Semimonthly functional polling testing and quarterly full cycle activation and/or growl testing of the Early Warning System (EWS) 8.8 INFORMING THE PUBLIC Information describing the emergency notification process as well as actions that should be taken in the event of an emergency shall be provided to the public on an annual basis. Information provided to the public shall include: a) Educational information on radiation b) Contact points for additional information c) Special needs of the handicapped d) Initial actions following Early Warning System Activation e) Protective actions , such as sheltering or evacuation f) Evacuation routes The company will coordinate its efforts with State and local authorities to ensure the public is informed by using the best means available. These means may include: a) Information in telephone books b) Utility bill inserts c) Newspaper ads d) Postings in public areas e) Information in calendars distributed to residents The information will be distributed to ensure coverage within the 1 O mile emergency planning zone. The company shall also establish a telephone system for dealing with rumors. The telephone numbers will be announced over the Emergency Alert System and individuals within the 10 mile emergency planning zone will be invited to call collect.

NAEP Page 8.14 Revision # TBD The Manager Nuclear Fleet Emergency Preparedness shall ensure that a program to acquaint the news media with the following information is offered on an annual basis: a) Emergency plans b) Information concerning radiation c) Points of contact for release of public information in an emergency

8.9 INDEPENDENT

REVIEW OF THE EMERGENCY PREPAREDNESS PROGRAM An independent review of the emergency preparedness program shall be conducted either: a) at intervals not to exceed 12 months or b) as necessary , based on an assessment against performance indicators , and as soon as reasonably practicable after a change occurs in personnel , procedures , equipment , or facilities that potentially could affect emergency preparedness , but no longer than 12 months after the change. In any case , all elements of the emergency preparedness program shall be reviewed every 24 months. This review shall be conducted in accordance with 10 CFR 50.54 (t). This review shall include: a) The North Anna Emergency Plan and Implementing Procedures b) Emergency Plan training c) Emergency drills d) Emergency exercises e) Emergency equipment f) Interfaces with State and local governments g) Required records and documentation This review shall be conducted by an internal company organization or outside consultant which has no direct responsibility for emergency preparedness.

The results of the review and recommendations for improvements shall be documented and reported to company management.

The results regarding adequacy of interface between Dominion and State and local governments shall be made available to the cognizant offsite authority. Recommendat i ons for improvement shall be evaluated and , when appropriate , assigned for corrective action. The following records shall be filed by Records Management and maintained for 5 years: a) The review results and recommended improvements b) The answers to the recommended improvements c) A description of the corrective actions taken TABLE 8.1 NAEP Page 8.15 Revision # TBD EMERGENCY PREPAREDNESS TRAINING* EMERGENCY RESPONSE POSITION Stat i on Emergency Manager Emergency Communicator Emergency Procedures Coordinator Emergency Operations D i rector Emergency Maintenance Director Emergency Technical Director Shift Technical Adv i sor Emergency Administrative D i rector Radiological Assessment Director Radiation Protection Supervisor Operational Support Center Directo r OSC Support T earn Techn i cal Support T earn Chemistry Team Administrative Support Team Team Leade r Clerical Personnel Loss Prevention

/Safety Personnel Security Team Dose Assessment Team Sample Analysis and Monitoring Teams Fire Brigade First Aid T earn Damage Control T earn Search and Rescue T earn Corporate Response Manager and Technical Support Manager Nuclear News Manager and News Team Chief Technical Spokesperson and JIG Support Team Executive Lia i son Operations Support Coordinator and Operations Support Team Radiological Assessment Coordinator Accident Assessment T earn dose assessors HPN Communicator State & Local Emergency Communicator (CERC) CERC positions not l isted above Information Center Coordinators SCOPE OF TRAINING (See Footnotes , next page) 1 , 2 , 7 , 13 , 15 1 , 3 , 13 1 , 2 , 13 1 , 2 , 13 , 15 1 , 4 , 6 , 13 1 , 6 , 13 , 15 1 , 2 , 13 , 15 1 , 6 , 7 , 13 1 , 9 , 10 , 11 , 13 , 15 1 , 10 , 11 , 13 1 , 4 , 5 , 13 1 , 4 , 6 , 13 1 , 6 , 13 , 15 1 , 12 , 13 1 , 6 , 8 , 13 1, 6 , 13 1 , 13 , 14 1 , 8 , 13 1 , 9 , 13 1, 11 , 13 1 , 13 , 14 1 , 13 , 14 1 , 4 , 13 1 , 13 , 14 1 , 13 , 16 , 17 1 , 13 , 17 , 18 1 , 13 , 17 , 18 1 , 13 , 16 , 17 1 , 13 , 15 , 17 1 , 9 , 10 , 13 , 15 , 17 1 , 9 , 13 , 17 1 , 3 , 13 , 17 1 , 3 , 13 , 17 1, 13 , 17 1 , 13 , 19 SCOPE OF TRAINING FOOTNOTES: NAEP Page 8.16 Revision # TBD 1. Training provided to all emergency response personnel emphas i zes an overview of: Emergency organization , emergency classificat i on system , personnel accountability , emergency exposure limits , emergency response fac i l i ties , security acces s control and site evacuation process , and exposure control techniques. Station badged responders will rece i ve this training as part of Nuclear Employee Training. 2. Training provided emphasizes

Assessing emergencies , classifying emergencies , notificat i on systems , contaminated injured personnel actions , site evacuation , emergency radiation exposu r e authorization , offsite support group capabilities , and recovery.

3. Training provided emphasizes

Notificat i ons and reports to offsite authorities and commun i cat i on systems as appropr i ate for individual position assignments. 4. Train i ng provided emphas i zes: Eme r gency Plan Damage Control organization , communication systems , and plann i ng and coordination of damage control tasks. 5. Training provided emphasizes

Activation and administration of the Operational Support Cen t er. 6. Training provided emphasizes

Activation and administration of the Technical Support Center. 7. Training provided emphas i zes: Site evacuation procedure.

8. Training provided emphasizes:

Notification of station personnel , personnel accountability

/evacuation , and station access control during an emergency.

The Security Department is responsible for the conduct of this training and for ensuring that documentation i s properly mainta i ned for Security Department personnel.

9. Training provided emphasizes

Dose Assessment.

10. Training provided emphasizes:

Control of emergency Health Physics organization , emergency exposure evaluation , and protect i ve measures.

NAEP Page 8.17 Revision # TBD 11. Training provided emphasizes:

Respiratory protection, personnel decontamination , inplant monitoring , offsite monitoring , monitoring of emergency centers and remote assembly areas , contaminated injuries, and radio communications as appropriate for individual position assignments. 12. Training provided emphasizes

Chemistry sampling and high level activity sample analysis under emergency conditions. 13. Training provided emphasizes:

Organizational interfaces and responsibilities appropriate for individual position assignments.

14. Training provided emphasizes

Emergency organizational interfaces , search and rescue procedures , and communications systems. Fire Brigade members shall also receive Fire Brigade training as required by the North Anna Power Station Fire Protection Program. First Aid Team Members shall also receive training as required by station administrative procedures, which meet the requirements of the Accident Prevention Manual. 15. Training provided emphasizes

Use of the Plant Computer System appropriate for individual position assignments.

16. Training provided emphasizes:

Protective measures, notification systems and processes , offsite support group capabilities and interface, press release review, and recovery.

17. Training provided emphasizes

Activation and administration of the Corporate Emergency Response Center. 18. Training provided emphasizes:

Activation and administration of the Joint Information Center appropriate for individual position assignments.

19. Training provided emphasizes

Activation and administration of the Local Media Center appropriate for individual position assignments.

Part 9.0 9.1 9.2 F i gure 9.1 NORTH ANNA POWER STATION EMERGENCY PLAN SECTION 9 RECOVERY Subject Recovery Recovery Methodology Population Exposure Example Recovery O r ganization NAEP Page 9.1 R ev i s i o n # TBD Page No. 9.2 9.2 9.3 9.4

9.0 RECOVERY

NAEP Page 9.2 R ev i s i o n# TBD The recovery process will be managed by a spec i al , designated organization composed of Dominion personnel.

The recovery organization is described in F i gure 9.1. The basic organization may be modified , as required , to address the needs of the given situation. The Technical Support Manager assumes control and direction of the recovery operation with the authority and responsibilities for implementating and admin i stering the recovery plan and organization.

Responsibilities of the recovery organization include defining recovery objectives , developing a plan to accomplish these objectives , establishing controls and anticipating potential complications , monitoring the recovery effort and adjusting the plan accordingly , and evaluating accomplishments against the designated objectives.

The recovery process is implemented when the Corporate Response Manager , Technical Support Manager and the Station Emergency Manager , with concurrence of State and Federal agencies , have determined the station to be in a stable and controlled condition. Upon the determination , the NRG Operations Center , the Virginia Emergency Operations Center , and the local Emergency Operations Centers will be notified that the emergency has been terminated and any requ i red recovery has commenced.

9.1 RECOVERY

METHODOLOGY The Recovery organization will develop plans and procedures designed to address both immediate and long term actions. The necessity to mainta i n protective measures implemented during the emergency will be evaluated and , if deemed appropriate , the Recovery organization will recommend relaxat i on of the protective measures.

The following conditions shall be considered appropriate for the recommendation to relax protection measures.

a. Station parameters of operation no longer indicate a potential or actual emergency exists. b. The release of radioactivity from the Station is controllable , no longer exceeds permissible levels and does not p r esent a credible danger to the public. c. The Station is capable of sustaining itself in a long term shutdown condition.

Because it is not possible to foresee all of the consequences of an event , specific recove r y procedures may need to be written to address specialized requirements. Normal practices will be followed to the furthest extent possible with regard to maintenance , repair , modification , decontamination , and radiat i on exposure control activities.

Where possible , existing station procedures w i ll be utilized in the areas of operations , maintenance and radiological controls.

Any special recovery procedures will requi r e the same review and approval process accorded other station procedures and , as such , will require the approval of the Facility Safety Review Committee (FSRC). Recovery plan objectives and associated schedules will be per i odically evaluated and modified , if necessary , to accommodate changing circumstances.

Provisions to review , priorit i ze , coord i nate and proceduralize recovery activ i ties (e.g., repair , maintenance , modification , and decontamination) w i ll also be addressed.

The recovery organization addresses planning and coordination of the recovery effort (in cooperation w i th governmental officials , when NAEP Page 9.3 R e vision # TBD required). Federal and state agencies may augment the recovery organization and participate in establishing recovery objectives. 9.2 POPULATION EXPOSURE Total population doses shall be periodically estimated in the affected sectors and zones utilizing population distribution data from within the emergency planning zones. Station personnel initially determine Total Effective Dose Equivalent (TEDE) due to external exposure from airborne material , external exposure from ground deposition , and internal exposure due to inhalation.

Initial calculations are also performed for determination of Thyroid Committed Dose Equivalent (COE) resulting from inhalation of radioiodines. The methodology used is consistent with that presented in EPA-400-R-92-001, MANUAL OF PROTECTIVE ACTION GUIDES AND PROTECTIVE ACTIONS FOR NUCLEAR INCIDENTS. Determination of total population doses will be performed utilizing the Meteorological Information and Dose Assessment System (MIDAS) computer code or equivalent , and will include assessments of exposure received from (but not necessarily limited to) immersion , inhalation, ground shine , and ingestion of radioactive materials.

Pub li c Affa i rs Interface Cost Administrative Support NRC Interface Eng i neering EXAMPLE RECOVERY ORGANIZATION FIGURE 9.1 Senior VP Recovery Manager StateA..oca l ._ IN PO/Industry

~FEMA Affected Unit Admin i strat i ve S u pport Operat i ons Maintenance I NAEP Page 9.4 R ev i sio n # TBD Operat i ng Units I Affected Station Unaffected Unit Unaffected Station I Corporate Coordination I Plann i ng Safety & Licensing Radiolog i cal Protect i on EXAMPLE RECOVERY ORGANIZATION Graph i c No: N B4 7 NORTH ANNA POWER STATION EMERGENCY PLAN Lette r s of Ag r eement Deleted SECTION 10 APPENDICES Subject NAEP Page 10.1 Revision # TB D 10.1 10.2 10.3 Maps of Exclusion Area , Low Population and Emergency Planning Zone Boundar i es 10.4 Listings of EPIPs 10.5 Protective Equipment and Supplies 10.6 Deleted 10. 7 Supporting Plan Contact 10.8 Estimation of Evacuat i on Times 10.9 Radiation Emergency Plan , MCVHNCU -Dominion Power 10.10 Federal Rad i ological Monitoring and Assessment Center (FRMAC) Operations Plan 10.11 Initiating Conditions

/Emergency Action Levels Letters of Agreement Federal Agencies:

State Agencies: Local Agencies:

U. S. Department of Energy -F i eld Office , Oak Ridge Commonwealth of Virginia Department of Emergency Management Commonwealth of Virginia Department of Health Commonwealth of Virginia Department of State Police Commonwealth of Virginia Department of Game and Inland Fisheries Virginia Commonwealth University Medical Center Lou i sa County Adm i nistrator Lou i sa County Sheriff Louisa County Department of Fire and EMS Spotsylvania County Sheriff Spotsylvania Department of Fire , Rescue , and Emergency Management Orange County Sheriff Orange County Administrator Caroline County Department of Fire & Rescue Caroline County Sheriff Hanover County Administrator Hanover County Sheriff (Maintained under separate cover by Nuclear Emergency Preparedness Department.

Ava i lable upon request.) NAEP Page 10.1.1 Revision # TBD APPENDIX 10.2 (DELETED)

NAEP Page 10.2.1 Revision#

TBD APPENDIX 10.3 MAPS OF EXCLUSION AREA, LOW POPULATION AND EMERGENCY PLANNING ZONE BOUNDARIES NAEP Page 10.3.1 R evision # TBD

, SH e Boundary *, , (_Ex du si cn Ar e a) NORTH ANNA POWER STATION EXCLUSION AREA ----------.. ---.... Lake Anna NAEP Pag e 1 0.3.2 R ev i s i o n # TBD ' ' G ra ph ics No: 6 Ve44J NORTH ANNA POWER STATION LOW POPULATION ZONE 10 MILE EMERGENCY PLANNING ZONE NAEP Page 10.3.3 Revision # TBD Grophcr No.S8121J

/ w __ _, _,_ ; / '-j / 1 J--~iNW /*.../ ' . ) / . I / I <--.'l. NORTH ANNA POWER STATION 50 MILE RADIUS NAEP Page 10.3.4 Revi s ion # TBD A lex andr l a iml'~ Queen (,.'\ ~-* ") <., I:..) ,,--. <"";* ..:.J v.j\ New Kent *-"'--.. ""v,__,.l y;J_h Charles City <-'? J~mes ;,

APPENDIX 10.4 LISTING OF EPIPs NAEP Page 10.4.1 Revision # TBD LIST OF EMERGENCY PLAN IMPLEMENTING PROCEDURES Emergency Control Procedures 1.01 Emergency Manager Controlling Procedure 1.02 Response to Notification of Unusual Event 1.03 Response to Alert 1.04 Response to Site Area Emergency 1.05 Response to General Emergency 1.06 Protective Action Recommendations

2. Notification Procedures 2.01 Notification of State and Local Governments 2.02 Notification of NRG 3. Augmentation Procedures 3.02 Activation of Technical Support Center 3.03 Activation of Operational Support Center 3.05 Augmentation of Emergency Response Organization 3.06 Augmentation of Corporate Emergency Response Center 4. Radiological Monitoring and Dose Assessment Procedures 4.01 Radiological Assessment D i rector Controlling Procedure 4.02 Radiation Protection Supervisor Controlling Procedure 4.03 Dose Assessment Controlling Procedure 4.04 Emergency Personnel Radiation Exposu r e 4.05 Respiratory Protection and Kl Assessment 4.06 Personnel Monitoring and Decontamination 4.07 Protective Measures 4.09 Source Term Assessment 4.14 lnplant Monitoring 4.15 Onsite Monitoring 4.16 Offsite Monitoring 4.17 Monitoring of Emergency Response Facilities 4.21 Evacuation and Remote Assembly Area Monitoring 4.24 Gaseous Effluent Sampling During an Emergency 4.26 High Level Activity Sample Analysis 4.28 TSC Radiation Monitor i ng System 4.33 Health Physics Network Communications 4.34 Field Team Radio Operator Instructions 4.35 Chemistry Sampling NAEP Page 10.4.2 Revi s ion # TED List of Emergency Plan Implementing Procedures (Cont.) 5. Protective Action Procedures 5.01 Transportation of Contaminated Injured Personnel 5.03 Personnel Accountab i l i ty 5.04 Access Control 5.05 Site Evacuation or Company Dismissal 5.07 Administration of Rad i oprotective Drugs 5.08 Damage Control Guideline 5.09 Secu r ity Team Leader Controlling Procedure

6. Recovery and Restoration Procedures 6.0 1 Re-entry/Recovery Guideline NAEP Page 10.4.3 Revi sio n # TBD NAEP-EPIP CROSS REFERENCE' NAEP Page 10.4.4 R ev i s i o n # TBD NAEP SECTION NUMBER IMPLEMENTED BY EPIP NUMBER 4.1 4.2 4.4 5.0 5.2 5.3 5.4 6.1 6.2 6.3 6.4 6.5 9.0 9.2 1.01-1.05 1.04-1.05 1.04-1.05 1.01 , 3.05 1.01 , 3.02 , 3.03 , 3.06 , 5.08 , 5.09 2.01 , 2.02 , 5.09 2.01 1.01 , 2.01 , 2.02 , 3.05 , 4.34 1.01 , 4.01-4.03 , 4.09 , 4.14-4.18 , 4.24 , 4.26 , 4.28 , 4.33-4.35 1.01 ,-1.05 , 4.05 , 4.07 , 4.21 , 5.01 , 5.03-5.05 , 5.07 4.04 , 4.06 , 5.01 1.02-1.05 , 5.09 6.01 4.03 , 4.09 , 4.14 , 4.16 Because the Emergency Plan provides a broad overview of the guidelines that must be considered in mitigating an emergency situation , a number of sections of the Plan do not appea r in the c r oss refe r ence , as they are not spec i fically act i vated by an EPIP.

APPENDIX 10.5 PROTECTIVE EQUIPMENT AND SUPPLIES NAEP Page 10.5.1 Revision # TBD NO TE: D escri pti o n of kit co nt e n ts t o b e upd a t e d to reflect c urr e nt in ve n to ri es. Thi s c h a n g e i s b e y o nd th e sco p e of t hi s l ice n se ame ndm e n t r e qu es t. NAEP Page 10.5.2 R ev i sion # T B D Emergency Kits for Offsite Monitoring Teams NOTE: 1 1 6 1 1 1 1 2 2 2 10 2 2 1 1 1 1 1 1 1 3 1 1 2 2 1 6 1 2 4 Description Hand Trowel Forceps Silver Zeolite Filter Map of Orange Map of TLD Location Preselect Monitor Location Map Map of Site Exclusion Boundary Pads of paper Full-face Respirators , e.g., Ultravue or equivalent Pair Rubber Boots Envelopes Pencils Smears Flashlight Map of Louisa Map of Spotsylvania Map of Lake Anna Dosimeter Charger Package or Box of wipes , e.g., Kimwipes Qt. Plastic Container Gallon Plastic Container Package of Cotton Inserts Bag (15 pair) of Rubber Gloves Hoods Sets of P.C.s Bag assorted Bags "D" Cell Batteries Pk. Air Particulate Patches Digital Alarming Dosimeters (DADs)

• Caution Envelopes with Bag of assorted signs and barrier rope.

• 2 (each) 1 OOR Dosimeters and 1 R Dosimeters may be in the kit in lieu of 2 DADs.

NOT E: D esc ription of kit co nt ents to be upd ated to r eflect curre nt inv e ntorie s. Thi s change is bey o nd the sco p e of thi s li ce n se ame ndm ent request. Emergency Kits TSC, OSC, and ALT OSC NAEP Page 10.5.3 Revision#

TBD NOTE: in at least the following items: Quantity 2 2 2 1 1 5 2 2 1 1 2 2 Sets Description Full-face Respirators , e.g., Ultravue or equivalent Pair Rubber Boots Boxes Smears Dosimeter Charger (Not required if DADs used) Package Cotton Inserts Pairs of Rubber Gloves Hoods Sets of PCs E520 with 177 (or equal) RM-14 with 210 (or equal) Flashlights Replacement Batteries for flashlight Emergency Kit EVACUATION NOTE: The kit shall contain at least the following items: Quantity 2 8 25 Feet 6 Various 10 10 1 2 3 1 5 2 2 1 3 30 4 1 1 Description Cans of waterless soap Paper coverall suits Radiation barrier rope Radiation placards Radiation inserts for placards Radioactive material stickers Radioactive material tags Package of smears Pads of paper Pencils Box of surgical gloves Trash bags Boxes of cotton swabs Black marking pens Red marking pen Miscellaneous size plastic bags Pairs of shoe covers (disposable or launderable)

Packages of diapers Box of heavy-duty cleanser Roll of tape APPENDIX 10.6 {DELETED)

NAEP Page 10.6.1 Revi sio n # TBD APPENDIX 10.7 SUPPORTING PLAN CONT ACT NAEP Page 10.7.1 Revision # TBD NAEP Page 10.7.2 Revision#

TBD SUPPORTING PLAN CONT ACT ORGANIZATION State Plan (Commonwealth of Virginia Emergency Operations Plan -Specific Annex #1 -Radiological Emergency Response)

Louisa County Plan Spotsylvania County Plan Orange County Plan Caroline County Plan Hanover County Plan Medical College of Virginia Plan Department of Energy -FRMAP CONTACT Virginia Department of Emergency Management , Emergency Operations Center Sheriff's Dispatcher Sheriff's Dispatcher Sheriff's Dispatcher Sheriff's Dispatcher Sheriff's Dispatcher Hospital Superintendent Oak Ridge Operations APPENDIX 10.8 ESTIMATION OF EVACUATION TIMES (Maintained on file by Nuclear Emergency Preparedness Department.

Available on request.)

NAEP Page 10.8.1 Revision # TBD APPENDIX 10.9 RADIATION EMERGENCY PLAN MCVHNCU -DOMINION POWER (Maintained on file by Nuclear Eme r gency Preparedness Department.

Available on request.)

NAEP Page 10.9.1 R ev i s i o n# TBD APPENDIX 10.10 NAEP Page 10.10.1 Revis i on # TBD FEDERAL RADIOLOGICAL MONITORING AND ASSESSMENT CENTER (FRMAC) OPERATIONS PLAN (Maintained on file by Nuclear Emergency Preparedness Department.

Available on request.)

APPENDIX 10.11 INITIATING CONDITIONS EMERGENCY ACTION LEVELS NAEP Page 10.11.1 Revision#

TBD This information is presented in the Emergency Action Level Matrix and Emergency Action Leve l Technical Bases Document.

These documents are subject to the same review and approval process as the North Anna Emergency Plan and incorporated by reference.