Nuclear Regulatory Commission Public Documents Mail ... · Mail Station P1-137 Washington, DC 20555 Manual: EP Manual No.: 65 ... 16. EP Appendix F, Manitowoc County Radiological

November 30, 1999

Nuclear Regulatory CommissionPublic DocumentsMail Station P1-137Washington, DC 20555

Manual: EPManual No.: 65Issue Date: November 30, 1999

The following changes have been made to the Emergency Plan Manual. Please remove the previous revision(s) and replacethem IMMEDL4 TELYwith the current revision(s) that are attached.

I. EP Index, Revision 14.2. EP 2.0, Emergency Plan Acronyms and Definitions, Revision 36.3. EP 4.0, Emergency Conditions, Revision 36.4. EP 5.0, Organizational Control of Emergencies, Revision 43.S. EP 6.0, Emergency Measures, Revision 41.6. EP 7.0, Emergency Facilities and Equipment, Revision 42.7. EP 8.0, Maintaining Emergency Preparedness, Revision 42.8. EP 9.0, Recovery, Revision 34.9. EP Appendix A, Emergency Response Organization Personnel Function and Responsibility, Revision 19.

10. EP Appendix B, Emergency Classifications, Revision IS.11. EP Appendix C, Maps, Revision 11.12. EP Appendix 1, List of EPIP Categories and Cross-References to the Emergency Plan, Revision 14.

In accordance with procedure NP 1.1.5, the following procedures have been PERIODICALLY REVIEWED only. There is nochange to the procedure and it need not be updated. The only change will be indicated on the index in the Periodic Review Datecolnun.

13. EP 1.0, Introduction, Revision 24, dated 03/13/96.14. EP 3.0, Summary of Emergency Plan, Revision 22, dated 03/13/96.15. EP Appendix E, State of Wisconsin Peacetime Radiological Incident Response Plan (IRP), Revision 4,

dated 03/13/96.16. EP Appendix F, Manitowoc County Radiological Incident Response Plan, Revision 7, dated 10128/98.17. EP Appendix G, Kewaunee County Radiological Incident Response Plan, Revision 7, dated 10/28/98.18. EP Appendix H, Typical Equipment Lists, Revision 8, dated 03/13/96.19. EP Appendix J, Evacuation Time Estimates for the Area Surrounding the Point Beach Nuclear Plant, Revision 11,

dated 10128/98.20. EP CR Index, Emergency Plan Cross Reference Index, Revision 8, dated 12128198.

AFTER UPDATING YOUR MANUAL, PLEASE SIGN AND RETURN THIS RECEIPT ACKNOWLEDGMENTWITHIN 30 DAYS TO: POINT BEACH NUCLEAR PLANT, DISTRIBUTION CENTER, 6590 NUCLEAR ROAD,TWO RIVERS, WI 54241.

Submit PBF-0095 for any controlled manual changes or cancellations. If you have any questions, please call the DistributionCenter at Extension 6244, 6625, 6998, or 7462.

********Special Distribution Notes********

Enclose a self-addressed envelope for the return of the receipt

Distribution Center - PBNPC. L. Braun/T. M. Nuhlicek/L. D. MalleyN. L. Liimatainen

Date_

C) 57 c) All%

NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL

INDEX

EP INDEXRevision 14November 30, 1999

PROCEDURENUMBER

REVISIONPROCEDURE TITLE NUMBER

EFFECTIVEDATE

PERIODICREVIEW/

CANCELEDDATE

TABLE OF CONTENTS

EP 1.0EP 2.0EP 3.0EP 4.0EP 5.0EP 6.0EP 7.0EP 8.0EP 9.0

Introduction ...... 24Emergency Plan Acronyms & Definitions .36Summary of Emergency Plan .22Emergency Conditions .36Organizational Control of Emergencies .43Emergency Measures .41Emergency Facilities and Equipment .42Maintaining Emergency Preparedness .42Recovery.................................................................... 34

IIIIIIIII

03/13/9611/30/9903/13/9611/30/9911/30/9911/30/9911/30/9911/30/9911/30/99

11/30/9911/30/9911/30/9911/30/9911/30/9911/30/9911/30/9911/30/9911/30/99

APPENDICES

APPENDIX A

APPENDIX BAPPENDIX CAPPENDIX DAPPENDIX E

APPENDIX F

APPENDIX G

APPENDIX HAPPENDIX I

APPENDIX J

Emergency Response Organization PersonnelFunction and Responsibility ................................. 19

Emergency Classifications ............................... 18Maps ................................ 1.1Letters of Agreementd') ............................... 17State of Wisconsin Peacetime Radiological

Incident Response Plan (IRP) ................................ 4Manitowoc County Radiological Incident

Response Plan ................................. 7Kewaunee County Radiological Incident

Response Plan ................................. 7Typical Equipment Lists ..................... 8..........8List of EPIP Categories and Cross-References

to the Emergency Plan ................................ 14Evacuation Time Estimates for the Area

Surrounding the Point Beach Nuclear Plant ......... 11

IIII

11/30/9911/30/9911/30/9912/28/98

I 03/13/96

I 10/28/98

11/30/9911/30/9911/30/9912/28/98

11/30/99

11/30/99

11/30/9911/30/99

11/30/99

11/30/99

II

10/28/9803/13/96

I 11/30/99

I 10/28/98

CROSS-REFERENCE INDEX

I EP CR INDEX Emergency Plan Cross-Reference Index .................. 8 12/28/98 11/30/99

(T = Temporary Change) Page 1 of IC = Continuous UseR = Reference UseI = Information Use


EMERGENCY PLAN ACRONYMS & DEFINITIONS

EP2.0Revision 36November 30, 1999

1.0 KEY ABBREVIATIONS

The following key and readily recognizable abbreviations are used throughout the plan:

ABVNTACADCAEOFAgZAHUALALIALARAAMSANALYZ

IANIAOTAOVASIPAT&TA&E

BAST

CAECASCBOCC

ICCR-CCWHXCDECEDECFMCFRCMCOMB AEcpmCPRCRCRTCTCTHCVCSCW

Auxiliary Building Vent1) Alternating Current; 2) Air ConditioningAnalog to Digital Converter

..Alternate Emergency Operations Facility..Silver ZeoliteAir Handling UnitAlertAnnual Limit on IntakeAs Low As Reasonably AchievableAir Monitoring System-AnalyzerAmerican Nuclear InsurersAuxiliary Operator TraineeAir Operated ValveAuxiliary Safeguards Instrumentation PanelAmerican Telephone & TelegraphArchitect/Engineer

Boric Acid Storage Tank

Combined Air EjectorCentral Alarm StationContained Breathing OxygenCursor ChannelCommunications and Community RelationsComponent Cooling Water Heat ExchangerCommitted Dose EquivalentCommitted Effective Dose EquivalentCubic Feet per MinuteCode of Federal RegulationsCommon MultiplierCombined Air Ejector (or CAE)Counts Per MinuteCardiopulmonary ResuscitationControl RoomCathode Ray TubeComputer TerminalCounty Trunk HighwayChemical Volume & Control SystemCirculating Water

-Page I of 16 INFORMATION USE




DADACDAMDAVNTDBADC

IDEMDIFSDIDMADNBDNBR

IDNRDOEDOHDOS

IDOTDPMDSS

EALEASEBSECECCSEDEDGENSEOCEOFEOPEPEPAEPIPEPMPEPPEPZERDERDS

IERFESIV

IETD

Digital to AnalogDerived Air ConcentrationData Acquisition ModuleDrumming Area VentDesign Basis Accident1) Dose Commitment; 2) Direct CurrentDivision of Emergency ManagementDepartment of Health & Family ServicesDe-ionized; DemineralizedDepartment of Military AffairsDeparture from Nucleate BoilingDeparture from Nucleate Boiling RatioDepartment of Natural ResourcesDepartment of EnergyDivision of HealthDuty Operating SupervisorDepartment of TransportationDisintegrations Per MinuteDuty Shift Superintendent

Emergency Action LevelEmergency Alerting SystemEmergency Broadcast SystemEnergy CenterEmergency Core Cooling SystemEmergency DirectorEmergency Diesel GeneratorEmergency Notification System (Red Phone)Emergency Operations CenterEmergency Operations FacilityEmergency Operating ProcedureEmergency PlanEnvironmental Protection AgencyEmergency Plan Implementation ProcedureEmergency Plan Maintenance ProcedureEmergency Preparedness ProgramEmergency Planning ZoneEstimated Release DurationEmergency Response Data SystemEmergency Response FacilityEstimated Safety Injection VolumeEmergency Telephone Directory

Page 2 of 16 INFORMATION USE




FCCFEMAFIFMFMTFRERP

. FRMACFSARFTSFX

GCGEGMgpmGSBVNTGTE

HPCALHPIPHPNHVAC

IBM-PCID

| 11TINPOIRPI&CI/0IPZ

Federal Communications CommissionFederal Emergency Management AgencyFlow IndicatorFrequency ModulationField Monitoring TeamFederal Radiological Emergency Response PlanFederal Radiological Monitoring & Assessment CenterFinal Safety Analysis Report

.. Federal Telecommunications SystemForeign Exchange (RE: Telephone Circuitry)

Gas ChromatographGeneral EmergencyGeiger MuellerGallons Per MinuteGas Stripper Building VentGeneral Telephone and Electronics

Health Physics Calibration ProcedureHealth Physics Implementation ProcedureHealth Physics NetworkHeating Ventilation and Air Conditioning

International Business Machines Personal ComputerIdentificationIncident Investigation Team (NRC)Institute for Nuclear Power OperationsIncident Response PlanInstrumentation & ControlInput/OutputIngestion Pathway Zone

JPIC

KNPPkV

LCDLCOLILINLLDLOCALPZ

Joint Public Information Center

Kewaunee Nuclear Power PlantKilovolt

Liquid Crystal DiodeLimiting Condition for OperationLevel IndicatorLocation Identification NumberLower Limit of DetectionLoss of Coolant AccidentLow Population Zone



EMERGENCY PLAN ACRONYMS & DEFINITIONS-

EP 2.0Revision 36November 30, 1999

MAD-CRMASPMCAMPCMPDMPHmRmRemMSA.MSIV_MSLBMSRMW

NANESNGSDNLRNNSRNPASSNRCNRRNSRNSSSNUREGNWS

OA0IOP.OPTOSCOSHAOSRCOSRPF

PAPABPACPAGPARPASSPBNPPBSPPBXPDPpH

Meteorology and Dose Assessment Program-Control RoomModified Amended Security PlanMulti-Channel AnalyzerMaximum Permissible ConcentrationMaximum Permissible DoseMile Per HourMilli-RoentgenMilliRem. = 1/1000 of a Rem.Mine Safety ApplianceMain Steam Isolation ValveMain Steam Line BreakMoisture Separator ReheaterMegawattt

Not ApplicableNuclear Engineering SectionNoble Gas Skin DoseNo License RequiredNon-Nuclear Safety RelatedNuclear Planning, Systems and Support SectionNuclear Regulatory CommissionNuclear Reactor Regulation (Office of)Nuclear Safety RelatedNuclear Steam Supply SystemNuclear Regulatory Commission ReportNational Weather Service

Outside AirOperating InstructionOperating ProcedureOptionalOperations Support CenterOccupational Safety and Health AdministrationOffsite Review CommitteeOffsite Radiation Protection Facility

Public Address, Protected Area, Public AffairsPrimary Auxiliary BuildingPortable Alpha CounterProtective Action GuidesProtective Action RecommendationPost Accident Sampling SystemPoint Beach Nuclear PlantPoint Beach Security ProceduresPrivate Branch ExchangePortable Data Processor (Digital Equipment Corporation)Hydrogen Ion Concentration

-Page 4 of 16 INFORMATION USE




PHAPIPICPIMPIMSPORVppmPSBpsiapsigPWR

Pulse Height AnalysisPressure IndicatorPressurized Ion ChamberPosition Instruction ManualsPooled Inventory Management SystemsPower Operated Relief ValveParts Per MillionPublic. Service Building

_-Pounds Per Square-Inch (Absolute)Pounds Per Square Inch (Gauge)Pressurized Water Reactor

QuartQuality AssuranceQuality Assurance DivisionQuality Assurance SectionQuality Factor

I

QQAQADQASQF

RRAPRASRATRCA

IRCPRCSRCTRDWREDSREMRESRHRRMRMSRMSASRBRORP

IRPSRPTRPURTDRWPRWST

IRx

SASSAMGsSBCC

RoentgenRegulated Air PumpRegulated Air SamplerRadiological Assistance TeamRadiation Control AreaReactor Coolant PumpReactor Coolant SystemRadio Chemistry TechnicianRadioactive WasteRemote EOF Datalink SystemRoentgen Equivalent ManRegulatory ServicesResidual Heat RemovalRadiation MonitorRadiation Monitoring SystemRadiation Monitoring System Alarm Setpoint Response Book1) Reactor Operator; 2) Eberline brand name Radiation Survey InstrumentRadiation ProtectionReactor Protection SystemRadiation Protection TechnologistRadiation Protection UnitResistance Temperature DetectorRadiation Work PermitRefueling Water Storage TankReactor

Secondary Alarm StationSevere Accident Management GuidelinesSite Boundary Control Center


NUCLEAR POWER BUSINESS UNIT EP 2.0EMERGENCY PLAN MANUAL Revision 36

November 30, 1999EMERGENCY PLAN ACRONYMS & DEFINITIONS

SBF Site Boundary Facility (Kewaunee Nuclear Plant)SCBA Self Contained Breathing ApparatusSE Site EmergencySFP Spent Fuel PoolSG Steam GeneratorSGBD Steam Generator BlowdownSGTR Steam Generator Tube RuptureSI Safety InjectionSOP 1) Standard Operating.Pxrocedure; _2) Step OffPadSP State PatrolSPING System Particulate Iodine and Noble GasSRC State Radiological CoordinatorSRD Self Reading DosimeterSRO Senior Reactor OperatorSTA Shift Technical AdvisorSTH State HighwaySTP Standard Temperature and Pressure

Tc Temperature, cold legTC Thermocouple, Team CoordinatorTEDE Total Effective Dose EquivalentTh Temperature, hot legTI Temperature IndicatorTID Temperature Indicating DeviceTLD Thermoluminescent DosimeterTR Temperature RecorderTS Technical SpecificationTSC Technical Support CenterTSO Time Sharing Option

UE Unusual EventULD Upper Level of DetectionUSCG United States Coast GuardUSEPA United States Environmental Protection AgencyUSNRC United States Nuclear Regulatory Commission

V VoltVac Volts, Alternating CurrentVAMP Victoreen Area Monitor PackageVdc Volts, Direct Current

WB Whole BodyWE Wisconsin ElectricWEDAP Wisconsin Electric Dose Assessment ProgramWEM Wisconsin Emergency ManagementWEPCO Wisconsin Electric Power CompanyWIS STATS Wisconsin Statutes





WOGWPS

I WPSCWT

IX/Q

Westinghouse Owners GroupWisconsin Public ServiceWisconsin Public Service CommissionWater Treatment

Wind Dispersion Factor




2.0 DEFINITIONS

This section provides definitions of terms applicable to the PBNP Emergency Plan.

2.1 Accident

An unforeseen and/or unintentional event and its consequences that may result in anemergency.

2.2 Accountability

The process used at the plant to account for the whereabouts of all people at the plantwithin the protected area (Security fence).

2.3 Admin Building

This three-story building houses the TSC proper, the OSC, TSC satellite file system, andoffices areas. The entire building is within the TSC post-accident ventilation systemenvelope.

2.4 Assembly

The orderly gathering in pre-designated locations of partial or all personnel from areaswithin the protected area and exclusion area.

2.5 Assessment Actions

Those actions taken during or after an accident to obtain and process informationnecessary to make decisions to implement specific emergency measures.

2.6 Background Radiation

The radioactivity that occurs naturally in our environment.

2.7 Clean Area

That area within the protected area excluding the radiation control area(s).

2.8 Containment Building

Houses the reactor, pressurizer, reactor coolant pumps, steam generator, and otherequipment or piping containing reactor coolant. The containment building is an airtightstructure which is made of 3',2 foot thick steel-reinforced concrete with an inside steelliner.




2.9 Control Room (CR)

The Control Room is operated under the direction of the Duty Shift Superintendent. It isthe primary place where conditions are monitored and corrective actions for both unitsare taken to mitigate any abnormal occurrence. It is the location where primaryassessment and classification of an accident begins. It's purpose is to monitor theconditions of both units and provide the main communications link between the plant andthe TSC concerning analysis of reactor system problems, as well as long - and short-termguidance on corrective actions.

2.10 Corporate Office (WE)

Wisconsin Electric Power Company (WE) corporate headquarters located at 231 WestMichigan Street, Milwaukee, Wisconsin, 53201. Examples of support provided bycorporate offices are, risk management, legal, insurance, and purchasing.

2.11 Corrective Actions

Those emergency measures taken to improve or terminate an emergency situation at ornear the source of the problem, to prevent or mitigate any release of radioactive material,or to reduce the magnitude of the emergency situation, (e.g., shutting down equipment,fire fighting, repair, and damage control).

2.12 Emergency

The situation or condition which may result in damage to property or risk to the healthand safety of the general public or plant personnel.

2.13 Emergency Actions

Those steps taken, as a result of exceeding an emergency action level in a plantemergency operating procedure or in this Emergency Plan, to assess the situation andensure that the proper corrective and/or protective actions are taken.

2.14 Emergency Action Level (EAL)

A predetermined set of initiating conditions which places the plant in a given emergencyclass. An EAL can be an instrument reading, equipment status, measurable parametereither on or offsite, an observable event or other phenomenon which, if it occurs,indicates entry into a particular emergency class.

2.15 Emergency Alert System

A set of predetermined local radio stations which will broadcast emergency messagesadvising area residents of Protective Actions to be taken.




2.16 Emergency Classification System

A classification system that arranges accidents according to their severity. Fouremergency classifications are defined under this system. They are, in order of increasingseverity:

- Unusual Event

- Alert

- Site Emergency

- General Emergency

2.17 Emergency Director

A designated person of WE responsible for the overall management of the emergencyresponse and recovery operation for WE.

2.18 Emergency Operations Center (EOC)

The headquarters for emergency response by the county and state governments. The stateand each county has its own EOC, located at the state capitol or county seat.

2.19 Emergency Operations Facility (EOF)

Following its activation, this facility is located in the Site Boundary Control Center at thesouth exclusion area boundary, approximately one mile southwest of the plant. Thisfacility is operated by the EOF manager for evaluating and controlling emergencysituations that may affect the public. For example, radiological dose projections andverifications will be performed at the EOF and results will be provided to local, state, andfederal agencies as required for implementation of offsite emergency plans. The EOFalso serves as the command center for direction of recovery operations. It becomes acenter for offsite environmental monitoring by Radiation Protection personnel. It servesas a clearing center for evacuated plant, company, contractor personnel and publicvisitors, and is a Radiation Protection control point for individuals entering or leaving thesite.

2.20 Emergency Plan Implementing Procedures (EPIPs)

Specific procedures providing actions to implement this Emergency Plan in order tomitigate or terminate an emergency situation.




2.21 Emergency Plan Maintenance Procedure (EPMPs)

Specific procedures providing information and actions designed to maintain equipmentand facilities prepared to respond to an emergency situation.

2.22 Emergency Planning Zone (EPZ)

Offsite area surrounding PBNP for which planning is conducted to ensure that prompt..and effective.actions can be taken.to protectthe .public inthe.event of an accident. Forthe plume exposure pathway, the EPZ has a radius of approximately 10 miles; and for theingestion exposure pathway, the EPZ has a radius of approximately 50 miles (seeAppendix C and Appendix J).

2.23 Emergency Response Organization (ERO)

Specific personnel who are trained in various positions to respond to the emergency.

2.24 Evacuation

The process implemented where radiological or other hazards require additional actionssuch as radiological monitoring, in conjunction with the release of personnel.

2.25 Exclusion Area

The area within the site boundary surrounding PBNP in which the plant personnel havethe authority to determine all activities including exclusion or removal of personnel andproperty from the area. At PBNP, the outer boundary of the exclusion area is coincidentwith the site boundary (see Appendix C).

2.26 Federal Emergency Management Agency (FEMA)

The lead federal agency with responsibility for off-site federal response to a nuclearpower plant incident.

2.27 Federal Response Center (FRC)

The central location to be used as the command center for all federal agencies.

2.28 Federal Radiological Monitoring and Assessment Center (FRMAC)

Where the Department of Energy will establish a center to coordinate radiologicalanalysis of the event.

Page I11 of 16 INFORMATION USE



2.29 Gatehouse

A building at the perimeter of the protected area manned by security force personnel andused for normal access to and egress from the protected area. There are two gatehouses,one to the north of the plant, the other to the south.

2.30 Incident

This term .is often used interchangeably with the term faccident" and, therefore, shall beconsidered to have the same definition.

2.31 Ingestion Exposure Pathway

The principal exposure from this pathway would be from ingestion of contaminated wateror foods such as milk, livestock feed, or vegetables. Depending on the magnitude andnature of the radiological emergency, the time of potential exposure may range induration from hours to months.

2.32 Joint Public Information Center (JPIC)

This facility is under the direction of the JPIC Manager and functions as a coordinatingpoint and common working area for local, county, state and federal agencies involvedwith a public information role in the emergency response. It is also a contact point fordisseminating information to the public through the news media during severeemergencies.

2.33 Evacuation

The orderly withdrawal of personnel from area(s) onsite. This may be a limited plantevacuation of a room, plant area, or building. It may also be a full evacuation of allnon-essential personnel from the site, both exclusion and protected areas.

2.34 Low Population Zone (LPZ)

The area immediately surrounding the exclusion area which includes a residentialpopulation of which the total number and density are such that appropriate protectiveactions can be readily taken in the event of a serious radiological accident (seeAppendix C and Appendix J).

2.35 Non-Essential Personnel

Those not needed to respond to the accident. In public communications, these peopleshould be called "workers without emergency response duties."




2.36 Nuclear Regulatory Commission (NRC)

The federal governmental agency that is responsible for the licensing and regulation of allactivities related to the commercial use of radioactive materials, including the regulationand inspection of nuclear power plants.

2.37 Offsite

The area beyond the exclusion area of PBNP.

2.38 Offsite Radiation Protection Facility (OSRPF)

Following its activation, this facility is located across from the EOF in the Site BoundaryControl Center. The facility is equipped with emergency radiation monitoring andsampling equipment, Radiation Protection supplies, protective and all-weather clothing,and other miscellaneous supplies for use during an emergency situation. Full monitoringteams are dispatched from this facility to monitor radiological conditions around PBNPand within the 10-mile EPZ.

2.39 Onsite

All areas at PBNP within the exclusion and protected area.

2.40 Operations Support Center (OSC) (Staging Area) (El. 8' of the TSC building)

This facility is an area for preparation and deployment of reentry teams.Communications are provided to the TSC and CR.

2.41 Plant Evacuation

The orderly withdrawal of all personnel from areas within the fenced protected area,except those immediately involved in the emergency organization.

2.42 Plume

A cloud of radioactive material that could be released from a nuclear plant in an accident.

2.43 Plume Exposure Pathway

The principal exposures from this pathway are whole body external exposure to gammaradiation from the plume and from deposited material, and internal exposure frominhalation of radioactive gas from the passing radioactive plume. Depending on thenature of the meteorological and radiological conditions, the time of potential exposurecould range from hours to days.




2.44 Point Beach Nuclear Plant (PBNP)

A two-unit [515 Megawatts (designed electrical rating net) each] pressurized waternuclear power plant located on a 1,260 acre site in the town of Two Creeks, Wisconsin.

2.45 Population-at-Risk

Those persons for whom protective actions are being, or would be, taken.

2.46 Projected Dose

The estimated dose that would be received by individuals if no protective actions weretaken following a release of radioactive material.

2.47 Protected Area

The area within the PBNP security fence. This is sometimes referred to as "onsite" by theutility industry. However in this plan, "onsite" is a defined term.

2.48 Protective Actions

Those measures taken in anticipation of or after an inadvertent release of radioactivematerial for the purpose of preventing or minimizing radiological exposures to personsthat potentially could occur if the actions were not taken.

2.49 Protective Action Guides (PAGs)

The projected radiological dose (including dose commitment values) at or above whichprotective actions may be warranted.

2.50 Protective Action Recommendation (PAR)

Protective Action Recommendation of evacuation is made by the utility to the state andcounty governments in order to protect the health and safety of the public. The state andcounty government may implement a PAR of evacuate or shelter in place at theirdiscretion.

2.51 Radiation Control Area (Controlled Zone)

The area within the protected area in which radioactive materials and radiation arepresent or could normally be expected to be present in sufficient quantities to requireprotective measures. This area typically includes the containments, facades, auxiliarybuilding, the area surrounding these buildings, and parts of the service building. Thisarea is controlled by administrative means.




2.52 Radiological Emergency

A radiological emergency is defined as an accident that may result in some loss of controlof radioactive materials or may involve a hazard or potential hazard to the health andsafety of people, or to the safety of property or environment.

2.53 Recovery Operations

- Those operations taken after the emergency-to restorethe plant as nearly as possible to itspre-emergency condition.

2.54 Release of Personnel

The orderly dismissal of nonessential personnel not immediately needed for response tothe event.

2.55 Security Building (Extension Building)

The building inside the protected area containing the Central Alarm Station, the SecurityCoordinator's office, and the Fitness for Duty testing area. Office areas unrelated tosecurity are also in the building.

2.56 Severe Accident Management Guidelines (SAMG)

Guidance documents developed to assist in the management of accidents significantlybeyond that for which the plant was designed. Goal is to mitigate core damage andmaintain the containment of fission products.

2.57 Site Boundary Control Center (SBCC)

This building is located approximately one mile southwest of PBNP at the south entranceto the plant site. During normal operations, it may function as a training center. Duringan emergency, the building houses the EOF and OSRPF and functions as aningress/egress point to the site and assembly area for ERO personnel assigned to the EOFduring a plant evacuation.

2.58 Siren Warning System

A set of sirens installed in a (approximately) 10 mile radius around the plant. Whensirens are sounded by county officials, residents should listen to Emergency Alert Systemradio stations for information/instructions.




2.59 Technical Support Center (TSC)

This facility is within two minutes walking distance of the Control Room and operatesunder the direction of the TSC Manager. The facility has the capability to supply anddisplay technical information for use by technical and designated management personnelin support of reactor operations and Control Room functions during emergency andrecovery operations. The TSC has its own emergency ventilation system.

2.60 TSC Satellite-Fie le

These supporting documents are located on El 26' of the Admin Building, consisting ofprocedures for all disciplines, component instruction manuals for major systems andcomponents, and a complete set of permanent drawing aperture cards with areader/printer.

2.61 Wisconsin Emergency Management (WEM)

A division of the State of Wisconsin Department of Military Affairs. The WEMcoordinates the state's expertise required to deal with a given emergency. The types ofemergencies to which they may respond include: chemical spills, fires, tornadoes,flooding, public employee strikes and nuclear plant accidents. The WEM Directorreports to the Governor. The WEM makes recommendations to the governor regardingevacuation and other protective actions.



November 30, 1999EMERGENCY CONDITIONS

1.0 EMERGENCY CLASSIFICATION SYSTEM

The Emergency Plan is based on potential situations ranging from incidents where effects on theplant status are negligible to highly unlikely major releases of radioactivity which could affectmembers of the offsite public. Each classification incorporates a specific emergencyorganization alerting and mobilization procedure and a set of actions to be taken by emergencyorganization personnel. Each classification is given a designation to indicate immediate requiredresponse of plant personnel when an emergency is announced over the public address(Gai-tronics) system.

Prompt notification of offsite authorities (federal, state, and local) is required and will beprovided for any and all emergency declarations. Periodic updates also will be provided tooffsite authorities while a classification remains in effect.

The following emergency classification system is based on NRC NUREG-0654, Revision 1,Appendix 1, Emergency Action Level Guidelines for Nuclear Power Plants, issuedNovember 1980. Within each classification is a description of immediate plant actions as well asrecommended state and local government actions.

1.1 Unusual Event

An Unusual Event is declared as required by the initiating conditions and EALs given inAppendix B to this document.

This classification applies to an unusual plant condition which has occurred or isimpending. This plant condition could eventually lead to a potential degradation inoverall safety. Inherently, however, this is a situation in which time is available to takeprecautionary and constructive steps to prevent a more serious event or to mitigate anyconsequences that may occur.

The Unusual Event status places the plant in a readiness condition where there is apossible cessation of routine activities and possible need of shift personnel augmentation.No significant release of radioactive material is expected and, therefore, offsite responseto a radiological release is not necessary. Onsite protective actions may include a limitedplant assembly.

The Unusual Event status will be maintained until an escalation in emergencyclassification is initiated or a termination of the event is made. Offsite authorities will beinformed with the completion of the necessary documentation as specified in the EPIPs.

It should be noted that this classification is equivalent to Notification of Unusual Event inNUREG-0654, Revision 1, Appendix 1.

Page I of 5 INFORMATION USE



1.2 Alert

An Alert is declared as required by the initiating conditions and EALs given inAppendix B to this document.

An Alert classification is declared when events are in progress or have occurred whichinvolve an actual or potential degradation of the level of plant safety. For example, theloss of one train of safety systems may reduce the capability of the plant t6 maintain.cooling to the. core during an emergencysituation. Although the potential for limitedreleases of radioactivity in excess of Technical Specification limits may exist, the initialassessment leading to this classification indicates that it is unlikely that an offsite hazardwill be created.

The plant emergency response will be augmented by the activation of the TSC, OSC,EOF, OSRPF and supporting-emergency response organization personnel. There will bea provision for the Emergency Director at the EOF to provide updates to offsiteauthorities.

Onsite protective actions of a plant and exclusion area assembly and evacuation wouldnot be necessary in an Alert, although a limited plant assembly and evacuation may benecessary.

The Alert status will be maintained until an escalation or reduction in emergencyclassification occurs or the status is terminated. Offsite authorities will be informed,which includes completion of the necessary documentation as specified in the EPIPs.

1.3 Site Emergency

A Site Emergency is declared as required by the initiating conditions and EALs given inAppendix B to this document.

The Site Emergency classification is declared when events are in progress or haveoccurred which involve actual or impending major failures of plant functions. Theseplant functions may include safety systems which control the capability to cool the coreor prevent release of radioactive material to the environment. In these events, there is apotential for offsite releases which could have an impact on the public to the extent thatprotective actions are imminent. Therefore, if not already accomplished, activation of theTSC, OSC, EOF, OSRPF, JPIC, and supporting emergency response personnel willcommence.

Onsite protective actions of a plant and exclusion area assembly and evacuation will beinitiated. There may be a deployment of onsite and offsite radiological field monitoringteams to assess radiation levels, with communication systems to transmit informationback to the EOF.




There will be a provision for the Emergency Director at the EOF to provide updates tooffsite authorities. These updates will be composed of meteorological information,projected dose estimates based on both actual and projected long-term release (calculatedon foreseeable unit conditions), and current plant status. The JPIC Manager willestablish and maintain communications with the EOF to provide information to the newsmedia on the status of the incident.

The declaration of a Site Emergency requires prompt notification to state and localauthorities so they may activate their emergency Dperations centers (EOCs) and dispatchkey emergency personnel, such as state and/or local monitoring teams, to assess offsiteconsequences.

This Site Emergency status will be maintained until an escalation or reduction inemergency classification occurs or the status is terminated. Offsite authorities will beinformed, which includes completion of the necessary documentation as specified in theEPIPs. It should be noted that this classification is equivalent to Site Area Emergency inNUREG-0654, Revision 1, Appendix 1.

1.4 General Emergency

A General Emergency is declared as required by the initiating conditions and EALs givenin Appendix B to this document.

The General Emergency classification indicates that events are in progress or haveoccurred which involve actual or imminent substantial core degradation/melting and apotential for loss of containment integrity.

If not already initiated, activation of the TSC, OSC, EOF, OSRPF, JPIC and supportingemergency response organization personnel will commence. Onsite protective actions ofa plant and exclusion area assembly and evacuation will be initiated. The onsite andoffsite radiological field monitoring teams will be dispatched. The Emergency Directorat the EOF will provide updates to appropriate offsite authorities. These updates will becomposed of current plant status, radiological release status, meteorological information,radiological dose projections, and affected EPZ areas. At the JPIC, the JPIC Managerwill establish and maintain communication with the EOF to provide information to thenews media on the incident status.




A General Emergency involves the potential or actual release of airborne radioactivitywhich is likely to result in offsite projected doses that would exceed the limits of theUnited States Environmental Protection Agency (USEPA) Protective Action Guides forplume exposure pathway. Therefore, recommendation to state and local authoritieswould be to activate full-scale emergency operations and to evacuate the public in theaffected areas. State and local authorities may implement protective actions as set forthin Table 4-1.

-The General Emergency status will be maintained until aneduction in the emergencyclassification occurs or the status is terminated. Offsite authorities will be informed,which includes completion of the necessary documentation as specified in the EPIPs.

2.0 SPECTRUM OF POSTULATED ACCIDENTS

The accidents that could occur at all commercial nuclear power plants have been classified bythe United States Nuclear Regulatory Commission (USNRC) (Appendix E 10 CFR 50)according to their severity of consequences and probability of occurrence. These accidentsapplicable to a pressurized water reactor like PBNP are addressed from the viewpoint ofinitiating events, alarm actuations, and/or associated readings.

The inclusion of Attachment A of EPIP 1.2, Emergency Classification, as Appendix B to thisdocument in no way concedes that all the listed scenarios are likely or even possible. This tableis to be used by the plant operators as an emergency classification guide. Since some accidentscenarios can be very complex, it is recognized that, with information available, knowledge andskill acquired, and years of operator training and experience, the swift classification of thoseaccidents can be aided with a simplified table.

Specific emergency operating procedures are not written for all the included accidents. In orderto deal with unlikely and complex scenarios, the EPIPs provide for sequenced actions indicatingclear direction to be followed by PBNP operators and emergency response personnel.Attachment A of EPIP 1.2 provides guidance for EPIP response to varying accident situationsand conditions.




TABLE 4-1

SEVERE CORE DAMAGE OR LOSS OF CONTROL OF FACILITYPUBLIC PROTECTIVE ACTIONS

< coredamage' or loss of- controlof facility.

YES

Evacuate 2-mile aus and5 miles downwind unless

conditions make evacuationdangerous and advise remainder

of plume EPZ to go indoors tomonitor EAS broadcasts.

(See Notes 2. 3.4.5. 7)

IContinue assessment based on

all available plant and field Z

monitoring information.

IModify protective actions6 as

necessary. Locate and evacuatehot spots. Do not relax protective

actions until the source of thethreat is dearly under control.

Severe core damage is indicated by (1) loss of critical functions required for core protection (e.g., loss of injectioncombined with a LOCA); (2) high core temperatures (PWR) or partially covered cored (BWR); (3) very high radiationlevels in area or process monitors.

2 Distances are approximate - actual distances will be determined by the size of the preplanned sub-areas that are based onlocal geopolitical boundaries.If there are very dangerous travel conditions initially shelter rather than evacuate the population until conditionsimprove.

4 Transit-dependent persons should be advised to remain indoors until transportation resources arrive if possible.Shelter may be the appropriate action for controlled releases of radioactive material from the containment if there isassurance that the release is short term (puff release) and the area near the plant cannot be evacuated before plumearrives.

6 Consider EPA PAGs in modifying initial protective actions.7 State of Wisconsin shall determine if sheltering is appropriate. The utility's only recommendation is evacuation.

Reference: Abstracted from NUREG-0654, Rev. 1, Supp. 3, Criteria for Preparation and Evaluation of RadiologicalEmergency Response Plans and Preparedness in Support of Nuclear Power Plants. Criteria for ProtectiveActive Recommendations for Severe Accidents.



November 30, 1999ORGANIZATIONAL CONTROL OF EMERGENCIES

1.0 DISCUSSION

This section of the Emergency Plan describes the organizational controls available to respond toan emergency. Authorities and responsibilities of key individuals and groups are delineated.Communication links for notifying, alerting, and mobilizing emergency personnel are described.

2.0 NORMAL PLANT ORGANIZATION

If both units are in a condition other than cold shutdown or refueling shutdown, each operatingshift consists of 10 or 11 qualified individuals as shown in Figure 5-1.

2.1 The Duty Shift Superintendent, who holds a Senior Reactor Operator (SRO) license, is indirect charge of all plant operations during his assigned shift and is directly responsiblefor actions of the crew.

2.2 Two Operating Supervisors hold Senior Reactor Operator (SRO) licenses.

2.3 Three Control Operators (COs) hold reactor operator licenses. (COs can also serve asAOs, if required.)

2.4 Three or four Auxiliary Operators (AOs) with no license required.

2.5 One Auxiliary Operator (AO) or Auxiliary Operator Trainee (AOT) for fire brigademanning.

2.6 There is at least one qualified Radiation Protection Technologist on each shift.

2.7 There will be a Radiochemical Technician on duty 88 hours per week.

2.8 One Shift Technical Advisor (STA) is available (within 10 minutes of the Control Room)to assist the Duty Shift Superintendent in evaluation and assessment.

2.9 A Security Shift Commander is available to serve as a communicator.

If the Duty Shift Superintendent, determines that an Alert or higher emergency exists, the normalshift organization shall be shifted into an emergency mode of operation and additional personnelwill be called in to augment the onsite organization in accordance with Figure 5-4 or 5-5. Thisaugmentation will take place such that an Emergency Response Organization (ERO) adequate torespond to the situation will be in place within one hour.

The Duty Shift Superintendent will direct plant response, assess and control the emergency, andinitiate the required plant and offsite notifications in accordance with Figures 5-6 and 5-7. If theDuty Shift Superintendent is incapacitated, the Operating Supervisor will assume theresponsibility and authority of the Duty Shift Superintendent (until relieved by a qualifiedindividual) and coordinate the plant response, including the initiation of offsite notifications.




3.0 ONSITE EMERGENCY RESPONSE ORGANIZATION (ERO)

This section of the Emergency Plan describes the responsibilities of the onsite personnel duringan event classified to be an Unusual Event or higher.

3.1 Direction and Coordination

The Duty Shift Superintendent will be in the Control Room and maintain responsibilityfor operation ofplant equipment and controls.during emergency conditions other thanfires. The Duty Shift Superintendents emergency classification will be determined by theEALs (Appendix B). The Duty Shift Superintendent will assume the responsibility of theEmergency Director (ED) and continue to assess the emergency until relieved of thisresponsibility by a qualified Emergency Director. If the incident is classified as an Alertor higher, the appropriate emergency response facilities as shown in Figures 5-4 through5-5 will be activated.

Upon activation of the TSC, the TSC Manager will assume responsibility for all onsiteactivities and personnel not directly related to plant operation. He will report to theControl Room initially for a briefing then transfer to and activate the TSC. The TSCManager will coordinate activities involving the Control Room, TSC, OSC, and SecurityBuilding. The TSC will assume parallel emergency assessment responsibility with theControl Room and will evaluate plant conditions and onsite radiological conditions.Based upon this evaluation, the TSC Manager will recommend classification changes tothe Emergency Director.

3.2 Plant Staff Emergency Assignments

Personnel are selected and assigned to fill ERO positions based on background trainingand experience. The organization for each emergency classification is shown inFigures 5-3 through 5-5. Appendix A lists a general summary of the emergencyassignments, by title, responsibilities, and principle, working relationships. A briefdescription of the emergency organization at different emergency classes:

3.2.1 Unusual Event (Figure 5-3)

This emergency organization consists of normal shift personnel. Additionalcommunications may be assigned as required. Appropriate proceduresassigned to the Control Room will be accomplished under the direction of theDuty Shift Superintendent. Staff augmentation for additional support willtake place on a case-by-case basis.




3.2.2 Alert (Figure 5-4)

Upon activation of the emergency response facilities, responsibility forclassification, assessment, evaluation, and recovery will be transferred fromthe Duty Shift Superintendent. The Operations Coordinator will assumeresponsibility for assessment and evaluation of the plant condition. Onsiteradiation surveys and monitoring will be conducted under the direction of theRad/Chem Coordinator. The Operations Support Center Coordinator willassume responsibilities for maintenance and repair coordination and searchand rescue. Management personnel will coordinate any limited plantevacuation and ensure accountability of their personnel. The TSC and EOFwill be activated in one hour. Offsite radiation surveys will be initiated asnecessary from the OSRPF under the coordination of the Offsite RadiationProtection Coordinator. These surveys will be under the direction of theDose/PAR Coordinator in the EOF. Upon activation of the EOF, theEmergency Director will assume overall responsibility for the emergencyresponse and recovery. A liaison will be provided to state and localgovernment agencies EOCs to assist in communications.

Other personnel also report to the TSC and EOF to assist in the emergencyresponse operations. Additional personnel will provide logistic,administrative, and scheduling support. These personnel will ensure 24-hourcontinuity for minimum staff positions.

3.2.3 Site and General Emergency (Figure 5-5)

In addition to actions taken at the Alert, a Site Emergency will requireactivation of the JPIC to provide periodic updates to the media. To ensureaccountability of personnel, a protected area assembly and accountability andexclusion area assembly will be initiated. Non-essential personnel will bereleased.

In addition to actions taken for a Site Emergency, a General Emergency mayrequire extensive amounts of external resources. To ensure this, the WEheadquarters may be contacted to provide or assist with offsite technicalsupport. An evacuation of non-essential personnel to offsite assembly areasmay be initiated if radiological or other hazards require additional actions.




4.0 OFFSITE EMERGENCY RESPONSE

This section describes offsite supporting assistance available to the onsite staff emergencyresponse organization.

4.1 W. E. Headquarters Support

The PBNP normal operations as shown in Figure 5-2 has available the technical and-administrative support services of the WE headquarters management and supportorganization. This organization can and will respond, as necessary, to emergencies atPBNP. The Emergency Director will identify situations where offsite assistance isneeded and will relay emergency information to the WE Executive Spokesperson forevaluation.

The WE headquarters organization will provide to, or obtain assistance for, the onsiteemergency organization as required. These responsibilities include, but are not limitedto:

4.1.1 Providing senior company management support to the plantemergency organization.

4.1.2 Providing public relations coordination-and making newsreleases prior to JPIC activation.

4.1.3 Providing funds necessary to implement the PBNP Emergency Plan.

4.1.4 Providing contract security management direction and support for offsitefacilitates.

4.1.5 Coordinating the restoration and/or operation of all generation, transmission,and distribution facilities.

4.1.6 Monitoring reentry and/or recovery operations, post-accident planning, andassisting as requested.

4.1.7 Assisting with post-accident investigation and review responsibilities.

4.1.8 Providing general assistance for environmental monitoring.

The WE emergency organization for PBNP and associated functions and responsibilitiesare included in the organization described herein.

A full-time occupational health nurse is assigned to PBNP and is available for assistancein an emergency, if required.




4.2 Local Services Support

During the operation of PBNP, it may become necessary to request and utilize assistanceprovided by local organizations and agencies. Since it is essential that support from theseorganizations and agencies be available, the following agreements and understandingshave been made. (Letters of Agreement are referenced in Appendix D.)

4.2.1 Two Creeks Volunteer Fire Department

When requested, the Two Creeks Volunteer Fire Department will provide firefighting assistance at PBNP.

4.2.2 Town of Two Creeks

The Township of Two Creeks will make available to WE, the Two CreeksTown Hall to be used as required during an emergency at PBNP.

4.2.3 Two Rivers Community Hospital

The Two Rivers Community Hospital will provide medical assistance toPBNP personnel. The agreement provides for the treatment of personnel whosuffer injuries complicated by radioactive contamination or radiation.Individuals may be transferred to the University Hospital and Clinics inMadison, Wisconsin, should the treatment required extend beyond thecapabilities of the Two Rivers Community Hospital. The Two RiversCommunity Hospital will maintain the capability and facilities to providedecontamination, first aid, and emergency stabilization medical treatment toinjured personnel from PBNP. These services and facilities are available24 hours a day.

4.2.4 City of Two Rivers

The City of Two Rivers will provide ambulance service to transport injuredpersons from PBNP.

4.2.5 University of Wisconsin Hospital and Clinics

The University of Wisconsin Hospital and Clinics will accept and providetreatment to personnel -with injuries beyond the capabilities of the Two RiversCommunity Hospital, even if complicated by radioactive contamination. TheUniversity of Wisconsin Hospital and Clinics are available 24 hours a day fortreatment or consultation.




4.2.6 Two Rivers Clinic, Ltd.

At least two licensed physicians of the Two Rivers Clinic, Ltd.,Two Rivers, Wisconsin, will provide medical supervision and care foremployees of PBNP who have medical conditions complicated by exposure toradiation. Both doctors have received training qualifying them to care for thistype of patient.

4.2.7 Manitowoc County Sheriffs Department

When alerted, the Manitowoc County Sheriffs Department will respondwithin 10-20 minutes and will:

a. Assist in controlling traffic for the duration of the emergency.

b. Assist WE in keeping members of the general public from entering thePBNP exclusion area.

c. Provide assistance in security-related matters.

d. Implement protective actions as directed by Wisconsin EmergencyManagement (WEM).

e. Provide augmented notification capability.

f. Provide for dispatch of ambulance services.

4.2.8 Wisconsin Public Service Corporation

The Kewaunee Nuclear Power Plant (KNPP) laboratory facility will provideassistance for radiological and chemical sample analysis for air, water andother needed samples during a radiological emergency at PBNP. KNPP willprovide the use of their site boundary facility (SBF) located about one milewest of KNPP if the PBNP SBCC is unavailable.

WPS and WE have an agreement to jointly use the facilities located at theWPS Green Bay Division Office, 700 North Adams Street, Green Bay, WI, asa Joint Public Information Center.



ORGANIZATIONAL CONTROL OF EMERGENCIES


0

4.2.9 Kewaunee County Sheriffs Department

When alerted, the Kewaunee County Sheriffs Department will respond within10-20 minutes, and will:

a. Assist in controlling traffic for the duration of the emergency.

b. Assist WE in keeping members of the general public from entering thePBNP exclusion area.

c. Provide assistance in security-related matters.

d. Implement protective actions as directed by Wisconsin EmergencyManagement (WEM).

4.2.10 Mishicot Area Ambulance Service

Mishicot Area Ambulance Service will provide ambulance service to transportinjured persons from PBNP.

4.2.11 National Weather Service

The National Weather Service will provide backup meteorological data forPBNP should our instrumentation become inaccessible or inoperable.

4.2.12 Westinghouse Electric Corporation

Upon request by WE, Westinghouse will provide emergency technicalassistance, including equipment and/or services, in support of PBNP in theunlikely event of an emergency.

4.2.13 INPO

In the event of an emergency, INPO will provide resources to assist inacquiring the help of other industry organizations.

4.2.14 Bechtel Power Corporation

Upon request by WE, Bechtel will provide technical assistance to PBNP.




5.0 COORDINATION WITH PARTICIPATING AGENCIES

This section identifies the principal state agency (designated state authority) and othergovernmental agencies (local, state, and federal) having planning and/or implementationresponsibilities for emergencies in the PBNP emergency planning zone.

5.1 State and Local Agencies

5.1.1 Wisconsin Department of Military Affairs, Wisconsin EmergencyManagement (WEM)

The Administrator of the WEM, Department of Military Affairs, has beendesignated by the Governor of the State of Wisconsin as the state officer toassume the primary responsibility and authority for radiological emergencyresponse planning.--The WEM is to exercise principal supportive roles, inaddition to other state agencies, whose involvement will be coordinated by theWEM. The WEM will brief the governor as to the situation and actions takenby the federal, state, and local agencies and activate the state emergencyoperating center (EOC) in the Department of Military Affairs Office Buildingin Madison, if necessary.

5.1.2 Wisconsin Department of Health and Family Services, Radiation ProtectionUnit (RPU)

The Radiation Protection Unit (RPU), Department of Health and FamilyServices, under the Radiation Protection Act, WIS STATS 140.50 to 140.60,is responsible to prevent exposure to ionizing radiation in amounts which aredetrimental to health according to nationally accepted standards. The statedesignates a State Radiological Coordinator (SRC) of the State RadiologicalResponse Team for peacetime radiological emergencies. The SRC isexperienced in the area of radiological health and is a staff member of theRadiation Protection Unit. Team members are personnel of the unit asdesignated by the SRC, augmented by selected personnel from the WEM andother state agencies trained specifically for radiological incidents. They willdo the following: conduct an initial survey to determine direct radiation levelsand/or the severity and extent of the contaminated area, including soil, foodand crop samples by taking readings and samples for analysis and makingfood chain dose estimates; advise how decontamination of the area should beaccomplished; and assist in checking the evacuees of an involved area forcontamination or exposure.




5.1.3 Wisconsin Department of Transportation, Division of State Patrol (SP)

The Wisconsin State Patrol supports the Division of Highways and local lawenforcement services directing vehicular and pedestrian movement out of andaround the area of the incident, controlling access into the area and providingsecurity at the site. All of the SP field cars have standard civil preparednessradiation monitoring survey meters and all troopers have been trained in theiruse. Some troopers have been trained as radiological defense officers. Alltroopers are trained in handling vehicular accidents involving hazardousmaterials. The SP academy also conducts courses available to local lawenforcement officers for their training in these techniques. Besides mobileradios in all Division of Enforcement and Inspection vehicles, the Office ofTransportation Safety has a communication van which can serve as a forwardcommand post at the site. Each district has a supply of walkie-talkies on adedicated frequency that is available through emergency police services forlocal and state emergency communications at the site of an incident. The SPis available for courier service, by motor vehicle, for taking the stateradiological response team to the site, and delivering samples to the StateLaboratory of Hygiene for analysis, if necessary, to expedite the response.

5.1.4 Wisconsin Department of Natural Resources, Division of Enforcement

The conservation wardens of the Division of Enforcement, Department ofNatural Resources, can support the local law enforcement services as does theSP. There are standard civil preparedness radiation monitoring survey metersdistributed among the wardens. About 6 to 12 wardens in each district receivesome training in survey instrument use. The wardens have mobile radios intheir cars on the SP frequency. The Department can provide courier service,by motor vehicles and plane, to take the State Radiological Response Team tothe site if necessary to expedite the response.

5.1.5 Wisconsin Department of Transportation, Division of Highways

The Division of Highways, Department of Transportation, is responsible,when so ordered by the Administrator of WEM , for implementing theEmergency Highway Traffic Regulation Plan when, as a result of aradiological incident, a large area is cordoned off by the law enforcementservices and vehicular traffic is directed to other roads.




5.1.6 Wisconsin Department of Agriculture

The Department of Agriculture has standard civil preparedness radiationmonitoring survey meters and personnel trained in survey instrument use.Trained personnel are based in Madison, Barron, Green Bay, and Burlington.Under the Hazardous Substances Act, 100.37, the Department can ban the saleof foods which have harmful levels of radioactivity. The Department canadvise the use, sale, or disposal of animal feeds containing harmful levels ofradioactive contamination. The Department can gather samples of milk andcrops to determine radionuclide and related stable element concentrations, andcan advise dairies as to the disposition of milk, farmers as to the feeding oftheir cows, and growers as to restoring land to productivity. Arrangementscan be made by the Department with respect to handling of animals exposedto radioactive contamination.

5.1.7 Wisconsin Department of Military Affairs

Section 21.11 of the Wisconsin Statutes contains the authority for thegovernor to order all or any part of the Wisconsin National Guard personneland/or equipment into active State service for public emergencies,disturbances or disasters. Because of the relatively short duration and reactiontime needed in a radiological incident, the National Guard, under theDepartment of Military Affairs, will be involved in such incidents only if thesize of the area involved requires their support. The National Guard couldprovide additional traffic control, communications, emergency provisions offood, radiological monitoring and decontamination services. The ArmyNational Guard has helicopters stationed in Madison and West Bend. If soordered by the governor, these can provide aerial reconnaissance andsurveillance, insertion of personnel and equipment, aerial evacuation, aerialsupply, illumination, communications, and command and control. The AirNational Guard has fixed wing aircraft at Madison and Milwaukee and, if soordered by the governor, could provide services similar to the helicopters withthe exception of take-off and landing capabilities and providing illumination.Additional radiation monitoring equipment maintained and operated by theU.S. Army is available at armories throughout the state. Nearly every one ofthe 72 company-sized units has a 2-5 man team trained inchemical-radiological procedures. In addition, the Two Rivers NationalGuard Armory is available, if needed, for use as an alternate offsite assemblyarea for plant and support personnel.

Page IOof 20 INFORMATION USE



5.1.8 Manitowoc and Kewaunee County

Under the provisions of the Wisconsin Statutes 22.16 and the Manitowoc andKewaunee County Emergency Government Ordinances, authorities of bothcounties have the responsibility and authority to coordinate offsite emergencyactivities in the event of a radiological incident. Each county has prepared aCounty Radiological Incident Response Plan to carry out this responsibilitywhich is applicable to emergencies at PBNP. These plans are referenced inAppendices F and G.

Upon notification of an emergency at PBNP which requires participation oflocal or county agencies, each county will activate its emergency organization.Each emergency organization is under the direction of the county boardchairman and is composed of representatives from various participatingagencies which include, but are not limited to, the county sheriff, countyemergency government director, county highway commissioner, fire fightingorganizations, and school administrators. The Manitowoc and KewauneeCounty Emergency Organization will provide or assist the emergencyresponse activities by the following:

a. Provide notification to county and support agencies and local arearesidents that an incident has occurred at PBNP, if necessary.

b. Provide liaison and communication capabilities with the plant facility andappropriate federal, state and local organizations.

c. Assist in providing release of accurate public information concerning theoffsite consequences of the emergency through all available media. Inaddition, advise and instruct area residents on what protective actionsshould be taken.

d. Assist in providing for medical treatment, health and sanitation services,and mass care for members of the general public.

e. Assist in the evacuation of affected offsite locations, if such an actionshould be required.

5.1.9 Local Water Supply Utilities

In the unlikely event that an accidental discharge of liquid radioactive materialoccurs into Lake Michigan which exceeds prescribed limits, notification thatthe event has occurred will be made to the municipal water utilities of TwoRivers, Manitowoc and Green Bay, as well as the State of WisconsinEmergency Management. These notifications will be made as soon aspossible, but no later than 12 hours after the initial start of the release.




5.2 Federal Government

Should an emergency situation or accident occur at PBNP, notification, reports, orrequests for assistance may be made by WE to various federal agencies andorganizations. Details for notifying and making reports to these agencies, as well as forrequesting and obtaining assistance, are provided in the EPIPs. The following agenciesmay, as the situation warrants, require notification or reports, or provide assistance ifrequired:

5.2.1 NRC Operations Headquarters, Rockville, Maryland

The NRC requires notification as stated in EP 5.0.

5.2.2 Nuclear Regulatory Commission (NRC)

Region III Office

5.2.3 Department of Energy (DOE)

The DOE in Region 5 has agreed to provide radiological assistance uponrequest. This request can be made by the Wisconsin EmergencyManagement. The Radiological Assistance Team can be expected to respondwithin 6 hours as directed by the Chicago Operations Office of DOE.

5.2.4 United States Coast Guard

The U.S. Coast Guard can supply local weather information, if necessary.

The U.S. Coast Guard, when requested by the cognizant state or localemergency response agency, will make a marine broadcast and issue a Noticeto Mariners, warning all craft of the danger in the area. (Contents of thebroadcast to be supplied by the cognizant emergency response agency.)

The U.S. Coast Guard, if requested by the Federal Emergency ManagementAgency or its designated representative will consider additional assistance ona case-by-case basis. The decision to commit Coast Guard resources will bemade by the Commander, Ninth Coast Guard District.

6.0 NUCLEAR REGULATORY COMMISSION (NRC) NOTIFICATION

Telephone notification of the NRC Headquarters and NRC Region III shall be made as soon aspossible, for any significant event as listed in 10 CFR 50.72 and 10 CFR 73. Notification of theNRC under this section does not necessarily mean the Emergency Plan has been implemented.

Page 12of 20 INFORMATION USE

NUCLEAR POWER BUSINESS UNIT EP-5.0EMERGENCY PLAN MANUAL Revision 43


7.0 METHODS OF NOTIFICATION

7.1 Notification of Offsite Agencies

The methods used for notification of offsite agencies are described in the EPIPs. TheEPIPs provide for an established message authentication scheme for each emergencyclassification, guidance on assuring and verifying that each agency is notified, and anincident report form for each emergency classification. The incident report formprovides for message verification and information for the initial and follow-up messages.The initial messages contain information about the location of incident, name of caller,date/time of incident, class of emergency, whether a release is taking place potentiallyaffected population and areas, and whether protective actions may be necessary. Thefollow-up messages contain the basic information from the initial message with thefollowing additional information if it is known and appropriate: the type and form of anyactual or projected radiological release; meteorological conditions; estimate of quantity ofradioactive material released or being released; actual or projected doses in the affectedsector(s); surface contamination measurements; emergency response actions in progress;recommended emergency actions, including protective measures; request for any neededonsite support by offsite organizations; and prognosis for worsening or termination of theemergency.

State and County Emergency Management agencies shall be contacted within 15 minutesof the classification and notified of any of the four emergency classes. Figure 5-7describes the primary notification and coordination of offsite agencies duringemergencies. Communications capabilities are discussed in EP 7.0 of this EmergencyPlan.

7.2 Notification of the General Public

The general public will be notified through normal methods including press releases andnews conferences of the lesser emergency classifications where protective actions are notrequired of the general public. In emergencies which may require some protectiveactions to be taken by the general public, notification will be accomplished by theManitowoc and Kewaunee County Sheriffs Departments and the State of WisconsinEmergency Management. The primary method of notifying residents in the affected areawould be by a siren system as described in EP 7.0, Section 9.0, and police and emergencyvehicles driving in the area with high power or "yelp" sirens on, mobile public addresssystems, and door-to-door personal contact. This notification procedure will commencewith the population within the area of greatest risk and continue with the balance of thepopulation within the EPZ as required. The actual notification and protective actionmessage will be transmitted over local emergency alerting system.





I

FIGURE 5-1NORMAL PLANT OPERATING ORGANIZATION

---------

II_ I

I. (1) RPTECHNOLOG

I _ _ _ _ -IIIIIIIIIIIIIIIIII

I1IIIII

IIIIIIIIII

( )SHIFT COMPLEMENT____________------------ -

* AVAILABLE 88 HOURS PER WEEK

SRO - SENIOR REACTOR OPERATOR

RO - REACTOR OPERATORNLR - NO LICENSE REQUIRED


C NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL

. EP 5.0Revision 43November 30, 1999

CORGANIZATIONAL CONTROL OF EMERGENCIES

FIGURE 5-2PLANT ORGANIZATION - NORMAL OPERATIONS

SITE VICE PRESIDE........................... .. . POINT BEACH

NUCLEAR PLANT

.I

.. ........... r' 0..... .. MANAGER'S-

* SUPERVISORY ::.. wn^F....

~G R T O 1 P A TDIRECTOR 1(1)CONFI I OFMANAGE PROJECTS REGSVCSaMANAR ENGINEERING TA ING MANAGER I MANAGERi I

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TWO UNITS

)OPERATORTHREE PER SHIFT

ONE UNITFOUR PER SHIFT

TWO0 UNITS

| MAINTENANCE | PRDUCTION 1 PROCEDURES

MANAGER MANAGER PROGRAM

NOTES:.

1. THE OPERATING GROUP SHIFT MAKEUP IS THE MINIMUM SIZEFOR OPERATION IN ALL MODES EXCEPT WITH A UNIT DEFUELED.THE OPERATIONS GROUP SHIFT MAKEUP MAY BE LESS THAN THEREQUIREMENTS FOR A PERIOD dF TIME NOT TO EXCEED 2HOURS IN ORDER TO ACCOMMOIATE UNEXPECTED ABSENCE OFON-DUTY SHIFT CREW MEMBERS' PROVIDED IMMEDIATE ACTIONIS TAKEN TO RESTORE THE SHIFT MAKEUP TO WITHIN THEMINIMUM REQUIREMENTS.

2. SRO - NRC SENIOR REACTOR OPERATOR LICENSERO - NRC REACTOR OPERATOR LICENSE

3. AN UNEXPECTED ABSENCE OF A SHIFT TECHNICAL ADVISORSHALL BE TREATED SIMILARLY TO NOTE 1. THE SHIFT TECHNICALADVISOR IS LOCATED ON SITE ON TEN MINUTE CALL TO THECONTROL ROOM.


( NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL


(EPC5.0Revision 43November 30, 1999

C,

FIGURE 5-3EMERGENCY ORGANIZATION - UNUSUAL EVENT

------- I - -- -- - - 1----

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NUCLEAR POWER BUSINESS UNIT 7 EP5.0 (EMERGENCY PLAN MANUAL Revision 43


FIGURE 54EMERGENCY ORGANIZATION - ALERT

- ------------ ------------r--------|--- ---------|-----------------------------n----___________________

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(- NUCLEAR POWER BUSINESS UNIT EP 5.0EMERGENCY PLAN MANUAL Revision 43


FIGURE 5-5EMERGENCY ORGANIZATION - SITE EMERGENCY AND GENERAL EMERGENCY

---- ----- ;r-------- ----- -------- I------ r-----------------------n- I --------------- J-------------------------JPIC Security Control Technical Support Center Emergency uperations FacilityRoom Operations Support Center Offsite Radiation Protection Facility

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-

FIGURE 5-6EMERGENCY NOTIFICATION SEQUENCE

PaLye 19 of 20l1w INFORMATION USE




FIGURE 5-7PBNP OFFSITE NOTIFICATIONS

(1) 15-Minute Notification(2) 1-Hour Notification

. (3) 12-Hour Notification



November 30, 1999EMERGENCY MEASURES

1.0 DISCUSSION

Emergency measures begin with the identification and classification of an emergency and theactivation of the appropriate emergency organization. Emergencies are classified in four distinctclasses. Definitions for each class, criteria for classifying emergency situations, and examples ofemergencies-falling in each class are described in EP 4.0. The initial corrective and protectiveactions are recommended. The details of these various emergency measures are contained in theplant's EPIPs. A general outline of the method and format is presented here.

2.0 ACTIVATION OF EMERGENCY ORGANIZATION

The four classes of emergencies defined in EP 4.0, Sections 1.1 through 1.4 require a varyingdegree and scope of emergency response. The emergency organizations for each class aredepicted in Figures 5-3 through 5-5 of EP 5.0. These figures have been designed to show titlesof emergency personnel and the places to which they report during each classification ofemergency. The function and responsibilities of these personnel are more fully described inAppendix A.

The various emergency classifications can occur individually or in some order of progressionover a period of time. The onsite emergency organization will be activated when the emergencyis announced on the public address (Gai-tronics) system. The public address announcement willinclude the location and the classification of the emergency. Initially, the emergencyorganization will consist of the normal operating shift personnel who are qualified as emergencyteam members. Additional emergency team members and plant staff personnel are readilyavailable during normal working hours and on a call-in basis during other than normal workinghours. Activation of offsite emergency organizations will be accomplished in accordance withthe severity of the emergency class. EPIPs provide predetermined message formats fornotification of offsite agencies, in conjunction with an established message authenticationscheme for each emergency classification. The overall offsite notification of supporting groupsand agencies is shown in EP 5.0, Figure 5-7.




3.0 ASSESSMENT ACTIONS

3.1 Responsibility for Assessment

Effective coordination and direction of all elements of the emergency organizationrequire continuing assessment throughout the duration of the emergency situation. Theassessment of plant conditions, radiation levels, and offsite consequences is initiallycoordinated by the Duty Shift Superintendent (DSS). The Duty Shift Superintendent is indirect charge of all emergency operations.

The assessment of emergencies can usually be accomplished by the normal operatingshift under the direction of the Duty Shift Superintendent. However, other members ofthe plant staff, including the use of the emergency response organization as described inEP 5.0, Section 3.0, will be called upon as required. Technical services and support willbe obtained from the combination of WE corporate office personnel, plant staffpersonnel, and outside support organizations as necessary and appropriate.

The DSS shall conduct a formal turnover of all responsibilities to the Emergency Directorwho will assume the overall management of the event and all key non-delegableresponsibilities. The TSC Manager and EOF Manager are responsible for input to theclassification and Protective Action Recommendation process.

Should any emergency progress to core damage, Emergency Operating Procedures willbe exited and plant response will be in accordance with Severe Accident ManagementGuidelines (SAMG). Decision-making responsibilities for plant response will shift to theTSC. Several ERO positions have been designated as SAMG Evaluators orDecision-Makers. Operations personnel perform the SAMG function of Implementor.

3.2 Types of Assessment Actions

The different types of assessment actions are described in Table 6-1. The details of theassessment function are incorporated in the EPIPs for each emergency classification.Continued assessment will be performed as required, with updating of offsite responseagencies. In addition, the results may require additional notifications, emergency actions,or reclassification of the accident.




3.3 Methods of Assessment

Accidents involving releases of radioactive materials to the environment require specialmethods of assessment to ensure that responses are appropriate for the protection of thepopulation-at-risk as well as plant personnel. The plant has an extensive system formonitoring radioactive materials released to the environment (e.g., liquid process,containment purge exhaust and auxiliary building ventilation exhaust, air ejector ventmonitors). As a general requirement, the various process monitors are capable ofinitiating appropriate alarms or actuating control equipment to provide containment ofradioactive materials if pre-established limits are reached. These systems will allow formonitoring releases of radioactivity during accident conditions. In any accident conditionwhere releases are not monitored or able to be monitored, emergency procedures providethe basis for calculating theoretical worst case release rates corresponding to a designbasis accident described in the PBNP FSAR.

In addition, the site has a permanent meteorological installation so that wind speed anddirection, standard deviation of wind direction as well as change of temperature withheight, are recorded continuously in the Control Room. Wind speed and direction andstandard deviation of wind direction are also available from a backup tower on site andfrom an inland tower located several miles west of PBNP. The inland tower is used toidentify lake effect winds. In the event the above instrumentation is inaccessible orinoperative, such information can be obtained from Kewaunee Nuclear Power Plant, thelocal Coast Guard Station, or the National Weather Service in Green Bay.

The methodology and technique used to predict the offsite concentration of radioactivenoble gases and iodine are as follows:

- On determination of any emergency or potential emergency condition anticipated to havesignificant offsite dose consequences, a procedure is initiated to project doses. TheEmergency Director is responsible for ensuring that the appropriate EPIPs are performed.These concentration levels will be verified by offsite field monitoring teams deployedwith portable radiological measurement and communications equipment. Thisinformation will aid state and local authorities in evaluating emergency action responses.




4.0 CORRECTIVE ACTIONS

Plant procedures contain steps to take corrective actions in order to avoid or mitigate seriousconsequences. Operator training is a vital factor in ensuring that corrective actions are taken inan expeditious manner. The instrumentation, control system monitors, and radiation monitoringsystem provide indications used by the operators to regulate systems necessary for the safe andproper operation of the plant.

These systems provide the operator with the information and controls needed to start up, operateat power, and shut down the plant. The systems also provide the means to cope with abnormaloperating conditions should they occur. Control of systems and display of information fromthese various systems are centralized in the Control Room. This instrumentation provides a basisfor initiation of corrective actions.

When necessary, the following additional corrective actions can be implemented duringemergency situations:

4.1 Fire Fighting

Detailed procedures for responding to fire situations are defined in the PBNP FireProtection Manual. The Fire Protection Manual describes detailed instructions on fireprotection and fire fighting with the fire protection organization and individualresponsibilities. If outside assistance is needed, the Two Creeks Fire Department iscalled in to assist in extinguishing the fire.

4.2 Damage Control and Repair

For minor emergencies, the plant personnel will normally be able to handle the cleanup,repair, and damage control. For major emergencies, the support of other company

* personnel or specialized outside contractors may be required to assist in the damagecontrol, cleanup, and repair operation. Emergency response operations will be handledwith the assistance of agencies available for that purpose.

Exposure to personnel during corrective actions should be controlled as stipulated inEP 6.0, Section 6.1.




5.0 PROTECTIVE ACTIONS

The EPIP used in classifying emergencies has predetermined EALs that, when met or exceeded,will require protective actions to be taken. In addition, the Duty Shift Superintendent mayinitiate EPIPs when they are determined to be necessary. EPIPs include assessment actions,corrective actions, and protective actions as appropriate. Protective actions will ensure thatpersonnel, both on and offsite, will be notified and actions initiated for their protection in theevent radiation or airborne activity levels from a radiological emergency onsite exceed or arepredicted to exceed predetermined values, or when other situations threaten personnel safety.

Protective actions taken within the exclusion and protected area (onsite) are the responsibility ofthe DSS and TSC Manager with input from the Operations Coordinator, while those taken offsitefall under the jurisdiction of Wisconsin Emergency Management with the resources of the StateDivision of Health and Family Services, Radiation Protection Unit, and the Manitowoc andKewaunee County Emergency Managements. Recommendations of protective actions to betaken offsite will be made only by the Emergency Director. It is recognized that at the beginningof an emergency evolution, the Duty Shift Superintendent will have the responsibility andauthority of the Emergency Director.

5.1 Protective Actions, Evacuation, and Personnel Accountability

This subsection provides for the timely relocation of individuals to prevent or minimizeexposure to direct or airborne radiation hazards.

5.1.1 Exclusion Area

a. Exclusion Area Criteria

Protective actions for personnel onsite will be taken when a radiologicalemergency has occurred, or may occur, which will result in concentrationsof airborne activity or radiation levels that exceed normal limits for aspecific area or areas and cannot be readily controlled. In addition,protective actions will be taken for onsite personnel in such situations asfires, meteorological danger, etc., where personnel safety is threatened.




b. Notification and Response Time

The actuation of fire alarms, radiation alarms, plant evacuation alarm,telephone calls, paging system, and public address (Gai-tronics)announcements, as applicable, will alert onsite personnel to hazardousconditions and to actions they must take. Such actions may be to assemblein emergency teams, to report to assembly areas, to evacuate specific areaswithin the plant, or to evacuate the plant. Table 6-2 describes theassembly areas for onsite personnel (which could include plant personnel,contractor personnel, and visitors) to protect them from direct radiation orairborne hazards according to evacuation classification. The means andtime required to notify the above personnel are delineated as follows:approximately two minutes are required in the Control Room to determinethat an accident has occurred. In addition, it is conservatively estimatedthat eight minutes are required to determine local severity of the accident.Indications of importance for identification and assessment includepressurizer pressure, pressurizer level, containment pressure, andautomatic initiation of safety injection. Therefore, the best estimate forinitial notification of onsite personnel would be approximately 10 minutesor greater, depending on instrumentation response and assessmentcapability at the time of the incident. It is important to note that mostcredible accidents in a nuclear power plant develop slowly and"defense-in-depth" concepts delay the release of significant amounts ofradioactivity.

c. Security and Site Access Control

The security program at PBNP is designed to deter, detect, and delay anintruder. The plant protected area is enclosed by a standard security fence.Plant personnel reporting to the plant during an emergency will report viathe SBCC or the appropriate gatehouse. Security personnel will controlaccess, log incoming personnel, and provide assistance, as required orrequested. In the event these areas are uninhabitable, security control willbe performed at the site boundary.

Provisions to restrict access to areas of the site outside the fencedprotected area will be accomplished under the direction of the SecurityShift Commander. The Security Shift Commander will assign a securityforce to control access to the plant property by barricading and manningthe site roads with appropriate placement of lights, chains, traffic cones,padlocks, and gates. Access control will be performed with the aid andcooperation of the Manitowoc County Sheriffs Department, as well asassistance from the Wisconsin State Patrol.

Plant security procedures are found in the PBNP Security Plan.




d. Assembly, Release and Evacuation

Personnel assembly, release, and evacuation at PBNP will depend on thenature of the emergency and the extent of the area affected. The DutyShift Superintendent, or the TSC Manager if the TSC is activated, willinitiate any limited plant evacuation or full-site assembly, release, and/orevacuations. These protective actions will be made after carefulconsideration of the benefits and risks involved. The details of thisprocess for the responsibilities and functions of plant personnel andcontractors within the protected area and exclusion area are included in theEPIPs. In general, these protective actions will be in accordance with thefollowing guidelines:

1. A limited plant evacuation will be considered when any of thefollowing conditions exist:

(a) Unscheduled area radiation monitor high-level alarm.

(b) Conditions which indicate a valid containment alarm isnecessary.

(c) Unevaluated airborne radioactive concentrations in excess ofthe derived air concentrations (DACs) specified in Appendix Bto 10 CFR 20.

(d) Excessive radioactive surface contamination levels (RPpersonnel may require evacuation of rooms, areas, or theaffected portions thereof).

(e) Other emergency conditions, such as fire, that may endangerhuman life or health.

The criteria for these radiation. levels and alarms do not apply toanticipated increases or alarms resulting from planned operations.

When a limited plant evacuation is ordered, personnel in the room,area, or building will proceed in accordance with the EPIPs, or asdirected over the public address system. If evacuation is from areaswithin the controlled area, personnel will proceed to the RP stationfor accountability and radiation monitoring.




2. A plant and exclusion area assembly, release, or evacuation will beconsidered when the conditions that require a limited plantevacuation are not confined to a building of the plant, or whengeneral area radiation levels outside of the controlled area exceedprescribed limits. In addition, these protective actions could beinitiated following a limited plant evacuation if a hazard continues toincrease in severity or spreads to other areas and the Duty ShiftSuperintendent or TSC Manager deems it necessary to assemblepersonnel from the plant. An assembly and release or evacuationwill also be ordered upon the classification of a Site or GeneralEmergency. When a plant and exclusion area assembly, release orevacuation is ordered, personnel will proceed as follows:

(a) Public visitors on the beach, fishing pier, and Energy Centerwill proceed to the SBCC.

(b) Duty shift operations personnel will report immediately to theControl Room and remain there until instructed otherwise.

(c) Personnel with assigned emergency duties shall proceed totheir pre-assigned emergency response facility.

(d) Plant personnel, corporate personnel, contractors, temporaryemployees, and visitors who do not have an emergencyassignment will proceed to designated assembly areas(Table 6-2).

(e) Plant personnel, corporate personnel, contractors, temporaryemployees and visitors who are in the exclusion area butoutside the protected area should proceed to the nearestassembly area outside the protected area unless directedotherwise by Security personnel.

At the discretion of the TSC Manager, the assembled non-essentialpersonnel will be:

(a) Released from the site when no radiological conditions arepresent.

(b) Evacuated from the site when radiological conditions arepresent and additional actions, such as radiological monitoringand relocation, are required.

3. Evacuation of a specific emergency response facility (ERF) will beconsidered when habitability of that facility is questionable or thefacility is considered to be unfit to support its function.




e. Personnel Accountability

Personnel accountability will be conducted at a Site Emergency or higherand is the responsibility of plant supervision and Security with thecoordination of the Security Coordinator. During an emergency situationwhich requires personnel in the plant to assemble in the various assemblyareas, Management personnel should help assure that all their personnelare accounted for. This accountability should take no longer than 30minutes. The Security Supervisor will verify complete accountabilityusing the security computer or the manual accountability procedure, andwill forward this information to the TSC. If the TSC is not activated, thisinformation will be forwarded to the Duty Shift Superintendent. Ifpersonnel are unaccounted for, teams will be dispatched to locate and, ifnecessary, rescue the personnel. Personnel accountability procedures areincluded in the EPIPs.

f. Monitoring Personnel Evacuated From Site

All individuals within the protected area of the plant, who have controlledzone access, are required to have in their possession personnel monitoringdevices capable of measuring the dose received from external sources ofionizing radiation. These devices consist of thermoluminescentdosimeter (TLD) for permanent record and/or a self-reading dosimeter(SRD) or electronic personnel dosimeter (EPD) for day-to-day indicationof external radiation exposures. For personnel not routinely monitored byTLD/SRD/EPD, the potential for exposure to external sources of ionizingradiation within the protected area is monitored through the use of pairedTLDs located throughout the plant. Non-monitored plant personnel willbe issued radiation monitoring devices when their services are requiredduring an emergency. A combination of checking SRDs/EPDs andquestioning of evacuees will be used to determine if there were anysignificant external exposures involved in the emergency. For any knownor suspected overexposures, the TLDs will be read as soon as possible,and further investigation will be conducted to determine the amount ofexposure and the necessary action to be taken.

If normal contamination control is not possible, monitoring forcontamination and internal exposure at the OSRPF and OSC will beaccomplished by using portable instrumentation and questioning attitudes.Any persons suspected or known to have ingested or inhaled radioactivematerial will be whole body counted to assess internal exposure as soon asconditions permit.




5.1.2 Offsite Area

a. Action Criteria

Required protective actions for offsite areas are discussed in the state andlocal plans. As mentioned, the plant shall classify the accident (EP 4.0,Section 1.0 and Table 4-1) and notify the federal, state, and localauthorities. The state plan has adopted the U.S. Environmental ProtectionAgency's Protective Action Guides for initiating actions to protect publichealth and safety. The local communities and state agencies have detailedplans for activating their agencies, taking various protective actions, andperforming social services. Plant recommendations of protective actionsfor people offsite will come from the Emergency Director.

The criteria for recommending protective action strategies to be taken inareas beyond the plant exclusion area encompass a number of factors andconsiderations. The determination of what emergency protective actionsshould be implemented in any given accident situation must be based onthe actual plant conditions that exist or that are projected at the time of theaccident, with the consideration of weather conditions, local protectionfactors for typical residential units, evacuation times, release potential, andprojected or potential doses. Therefore, the effective means in utilizingand applying protective actions in the event of an accident is an importantconsideration to reduce radiation exposure to the general public.

Protective action recommendations in many cases would apply to ageographic area of some radius in all directions from the plant and to alarger radius in a 60 to 900 sector centered on the average downwinddirection.

There are various types of protective actions that can be implemented bythe state and counties which include the following:

1. Population sheltering

2. Evacuation

3. Controlling food, milk, and water distribution

4. Prophylaxis (e.g., thyroid protection)

Page IO of 33 INFORMATION USE



5. Individual protective actions (e.g., respiratory protection equipmentand protective clothing)

Table 6-3 lists protective actions that may be recommended forvarious accident phases and approximate time periods as a functionof exposure pathways following an initiation of an accident. Thisinformation should be useful for appropriate state and local agenciesin making value judgments that are necessary to plan actions in.limiting the radiation exposure to the general public during anemergency at PBNP.

(a) Sheltering and Evacuation

Protective actions such as sheltering and evacuation canprovide protection for the public against exposure to gaseousradioactive fission products released during an accident atPBNP. Evacuation of the population in the plume exposurepathway to minimize public exposure to a passing radioactivecloud could be potentially 100% effective. However, theprotective action of population sheltering may be moreappropriate at the time of the accident with the consideration ofsuch factors as weather conditions, wind direction, roadwayconditions, duration and type of exposure, and projected orpotential doses to the population. Although the State ofWisconsin and the counties could implement sheltering, andbecause sheltering has different meanings for NRC and FEMA,Point Beach Nuclear Plant will only recommend evacuation asa protective action for the public.

(b) Shielding

Shielding estimates for several distinct building types havebeen made by using currently available shielding technology.Table 64 through Table 6-6 present these estimates andindicate the wide range of potential shielding factors affordedby normally inhabited structures, and that basements of bothhomes and large buildings offer very effective shielding againstradiation. The shielding effectiveness of a structure isexpressed in terms of a shielding factor which is the ratio of thedose received inside the structure to the dose that would bereceived outside the structure. The benefits of populationsheltering can be maximized by recommending that windowsand doors of homes be closed and sealed, and ventilationsystems turned off to minimize the turnover rate of air within

*the building.

Page II of 33 INFORMATION USE



(c) Exposure Pathways

If there were an atmospheric release of radioactive materials,doses to the public could occur by external radiation as thecloud passes, by exposure to external radiation fromradionuclides deposited on the ground- and other surfaces, or byinternal exposure due to inhalation or ingestion ofradionuclides. Levels in excess of accepted protective actionguides would generally occur closer to the source so that the

-protective actions could be recommended-on a two-phasedapproach. The first phase would be to evacuate thoseindividuals in these closer areas (i.e., within a 2-mile radius),while the second phase could be a recommendation to takeshelter and institute food, water, and milk control since theneed for evacuation versus sheltering in the 2- to 10-mile areamay not be evident. However, beyond 10 miles there is littleapparent distinction between the effectiveness of evacuationand sheltering in terms of minimizing projected health effects.

The protective actions discussed above are only a few of thealternate courses of action which could be taken in aradiological emergency.

b. Company Responsibilities During an Offsite Emergency

The responsibilities of the Company during an offsite emergency includethe following:

1. To provide the best possible effort to resolve the emergency onsiteand thus alleviate the offsite conditions.

2. To notify participating agencies in accordance with EP 5.0,Figure 5-7. In addition, the Company will provide the best possibleinformation, protective action recommendations (PARs), and supportservices to these agencies.

3. To coordinate the Company's action with those of federal, state, andlocal agencies involved.

4. In some unlikely cases, it is possible for a radiological release toexceed the 10-mile EPZ. In such cases additional PARs could beissued and tracking support provided if the counties so desire.

Examination of Offsite Emergency Protective Measures for Core Melt Accidents. Aldrich, D. C., McGrath, P. E., Ericson,D. M., Jr., and Jones, R. B., of Sandia Laboratories, Albuquerque, New Mexico, and Rasmussen, N. C., Department ofNuclear Engineering, M. I. T., Cambridge, Massachusetts, as presented at the American Nuclear Society Topical Meeting onProbabilistic Analysis of Nuclear Reactor Safety, May 8-10, 1978.




c. Participating Agency Responsibilities

Participating agency responsibilities are denoted in EP 5.0, Section 5.0and are further explained in the letters of agreement referenced inAppendix D.

d. Notification and Response Time

Notification of businesses, property owners and tenants, schooladministrators, recreation facility operators, and the general public withinthe EPZs will be accomplished by local and state authorities as describedin their response plans. An integrated siren system and the EmergencyAlerting System (EAS) will be used to notify the general public of anemergency requiring protective action. The State of Wisconsin has theresponsibility of determining public protective actions and coordinatingthe activation of the integrated siren system with the local countyagencies.

The counties have the responsibility to activate the sirens at thepredetermined time and to disseminate EAS messages to the public whichare consistent with the protective action recommendations made by thestate of Wisconsin. These messages will include protective actioninstructions as well as general information concerning emergencies. Thesiren system controls are operated by the Sheriffs Dispatch of Manitowocand Kewaunee counties. The siren system operability is tested routinely.The details of the means and the times to evacuate the above persons arediscussed in Appendix J.

5.2 Onsite Protective Equipment and Supplies

Protective equipment and supplies, as presented in Table 6-7, will be used to minimizeexternal and internal radiological exposure and contamination to individuals on andoffsite. Typical emergency equipment lists are located in the EPMPs and referenced inAppendix H. Detailed procedures on the use of protective equipment and supplies areincorporated in the Radiation Protection Manuals and the EPIPs (see Appendix I).




5.3 Contamination Control Measures

5.3.1 Exclusion Area

Measures are taken on a continual basis to prevent or minimize directexposure to or ingestion of radioactive materials within the onsite areas of theexclusion area. The details of the contamination control measures for onsiteareas are contained in the Radiation Protection manuals at the plant. Thefollowing is a brief outline of these procedures:

a. Controls have been established at the plant to minimize and control thespread of contamination. Criteria for free release outside the RCA are lessthan detectable for removable contamination, and less than 100 netcpm/O00cm 2 for fixed contamination.

b. All tools and equipment used in the controlled area are checked forcontamination before being taken from the controlled area. If the item isfound to be contaminated and decontamination is not practical, the itemremains controlled. Equipment and tools are unconditionally released foruse outside the area if contamination levels are less than the allowablelimits stated above.

c. Removal of material and equipment from the controlled area withradiation and contamination levels in excess of the allowable limits mustbe approved for "conditional" release by Radiation Protection (RP)personnel. Any item approved for "conditional" release will be packaged,sealed, labeled, and handled in accordance with applicable regulations toprevent the release of any contamination.

d. Personnel working within a radiologically controlled area/zone aremonitored by RP personnel. Radiation work permits (RWPs) ate requiredfor all personnel working in high radiation areas or contaminated areas(posted as requiring an RWP for entry). Specific instructions, precautions,and limitations are listed on the RWP.

e. Individuals leaving a radiologically controlled area/zone are to monitorthemselves for contamination before entering the clean area of the plant.




f The accumulation of radionuclides in the body shall not exceed that whichwould result from exposure to the derived air concentrations (DACs) ofradionuclides in air or drinking water for occupational exposure asindicated in 10 CFR 20.1201. In general, exposure to airborneconcentrations higher than the DACs are prevented or avoided to theextent practicable. If exposures are necessary, the wearing of appropriate,properly fitted, respiratory protective equipment may be required asdetermined by an RP supervisor. Periodic air samples are taken inselected operational and work areas to ensure that DAC levels are notexceeded.

g. Decontamination following a radiological emergency will be conducted inaccordance with approved EPIPs or approved routine RP procedures orpractices.

5.3.2 Offsite

For areas beyond the exclusion area, Wisconsin Emergency Management andthe Division of Health and Family Services, Radiation Protection Unit, areresponsible for assessment and evaluation and will determine protectiveactions to be taken within the EPZs. The State of Wisconsin RadiologicalResponse Team(s) will identify levels and control access within the affectedarea. Other State agencies shall take actions, as necessary, under the directionof the Administrator of the Wisconsin Emergency Management, to assess andcontrol the dairy and agricultural products within the affected area. Inaddition, the Administrator of the Wisconsin Emergency Management, alongwith principal supportive State agencies, will provide advisory informationregarding the use of potentially affected home food and water suppliesthroughout the EPZ. These State agencies will also be responsible forensuring that contamination levels are below the established criteria beforenormal use is restored.

Table 6-8 provides guidelines and recommendations for use by appropriateState and local agencies involved with response planning. This includesradiation protection activities involving protection against ingestion ofcontamination from the release of radioactivity to the environment. This tabledescribes action levels and recommended protective actions for ground, food,milk, and water contamination control.

Pa~ge 15 of 33 INFORMATION USE



6.0 AID TO AFFECTED PERSONNEL

Provisions have been made to assist personnel who are injured or have received high radiationexposures. Many plant employees and some contractor personnel are trained in first aid andradiation protection procedures. First aid and decontamination facilities are available onsite andoffsite, and necessary transportation services are also available. The following subsectionsdescribe measures to be used to provide any necessary assistance.

6.1 Emergency Personnel Exposure Criteria

Personnel permanently employed at PBNP with access to the radiologically controlledarea are issued a thermoluminescent dosimeter (TLD) and a self-readingdosimeter (SRD) or electronic personnel dosimeter (EPD). Normal operating proceduresrequire that a TLD be worn within the protected area. An SRD or EPD is worn inaddition to the TLD when inside the radiologically controlled area. These requirementsand associated normal procedures ensure that plant personnel will have a monitoringdevice in the event of any plant emergency. For personnel not routinely monitored byTLD/SRD/EPD, the potential for exposure to external sources of ionizing radiationwithin the protected area is monitored through the use of paired TLDs located throughoutthe plant. It is the responsibility of RP personnel to ensure issuance of personnelmonitoring devices to personnel whose services may be utilized during an emergency.Personnel monitoring devices are available at the RP station, gatehouses, TSC/OSC, andthe EOF/OSRPF.

In all situations, every reasonable effort will be made to minimize exposure to emergencypersonnel. In the event of injuries, fires, or minor radiation incidents, the limits set forthin 10 CFR 20.1201 shall apply. In addition, the routine PBNP administrative radiationdose levels will be observed. These levels are summarized in Table 6-9. In the event ofmajor radiation emergencies, Radiation Protection supervision may authorize emergencyworkers to receive up to the limits outlined in 10 CFR 20.1201. The Rad/ChemCoordinator and respective OSC Leaders are responsible to carefully control exposure toemergency workers in excess of occupational limits.

In some situations, it is possible that certain activities or duties for the protection ofpersons or the substantial protection of property may result in doses in excess of10 CFR 20.1201. When circumstances do not allow time for planned actions, theEmergency Director (DSS) has the authority to take immediate actions as required.When circumstances allow for planned actions, the Emergency Director will authorizethe dose extension based on recommendations from the Rad/Chem Coordinator orDose/PAR Coordinator.




Decisions to accept doses in excess of occupational limits will be on a volunteer basisand approved by the Emergency Director, based on the recommendation of theRad/Chem Coordinator or Dose/PAR Coordinator. The prospective volunteer shall bemade aware of the risks. Whole body doses in the order of 100-200 rem may result inradiation sickness, and whole body doses in excess of 300 rem involve a risk of fatality to50% of those exposed, if medical treatment is not provided. Individuals exposed to morethan 25 rem to the whole body shall be removed from further emergency duty andreferred to a physician for evaluation.

The emergency exposure criteria for non-plant personnel and volunteers involved inproviding first aid, decontamination, ambulance service, and medical treatment to injuredpersons shall be limited to the following criteria:

6.1.1 In the event of injuries, fires, or minor radiation incidents:

a. Non-plant personnel (except medical and fire personnel) are evacuatedfrom the area and denied reentry.

b. Medical and fire personnel may be exposed to the administrative levelsspecified in Table 6-9 and, if warranted, the limits specified in 10 CFR 20.

6.1.2 In the event of a major radiation emergency such as some Site Emergencies,the provisions of emergency exposure criteria that were set for plant personnelshall be applied to assisting non-plant personnel in the emergency responseeffort. When an assisting agency, e.g., DOE Region V RadiologicalAssistance Team or State of Wisconsin Radiation Protection Unit, has its ownemergency plan, the provisions of that agency's plan shall apply to thatagency's personnel.

6.1.3 Emergency Exposure Criteria for Airborne Concentrations

In the event of an emergency, exposure to airborne concentrations ofradioactivity shall be limited by the following:

a. In the event of injuries, fires, or minor radiation incidents, routineadministrative dose levels apply. The accumulation of radionuclides inthe body should not exceed that which would result from exposure to theDACs of radionuclides in air for occupational exposure as indicated in10 CFR 20.1201.

Respiratory protection and stable iodine shall be used wheneverappropriate to control inhalation doses. (See Section 6.5 for details onadministering thyroid-blocking agents.)

Limits for exposure to Xe- 133 and other noble gases are based on betaplus gamma dose limits to the skin.




b. In the event of a major radiation emergency such as some SiteEmergencies, exposure to airborne concentrations of radioactivity shall belimited by the following:

1. Whenever practicable, the total exposure of any individual during anemergency should be limited to the limits allowed in10 CFR 20.1201. If external radiation fields are low, the totalexposure of any individual should be limited to 2000 DAC-hours.DAC-hours are calculated by-multiplying the concentration in termsof the number of DACs by the total time of exposure.

2. In the event emergency operations demand life-saving or rescueactions and external radiation fields are low, individuals may beallowed exposures of 10,000 DAC-hours. If external radiation fieldsare not minimal, the sum of the external and internal doses should belimited to 25 rem. One DAC-hour may be considered equivalent to2.5 millirem. Exposures above 2000 DAC-hours should be receivedonly with the approval of the Emergency Director.

3. Respiratory protection and stable iodine shall be used wheneverappropriate to control inhalation doses. (Also see Section 6.5 fordetails on administering thyroid-blocking agents.)

5. It is the responsibility of all plant personnel, the respective OSCLeaders and the Rad/Chem Coordinator to carefully control theexposure permitted by I and 2 above.

6. Personnel who have been exposed to more than 10,000 DAC-hoursshall be removed from further emergency duty and referred to aphysician for evaluation.

6.1.4 Exposure Records and Control

Exposure records and forms for emergency workers are maintained for plantpersonnel at the South Service Building, OSC and OSRPF. This informationwill be utilized to determine emergency team assignments. It is theresponsibility of the Rad/Chem Coordinator, Dose/PAR Coordinator, and theirdesignated personnel to establish and maintain the personnel monitoringprogram during emergency situations.

Provisions for establishing an emergency dosimeter service within 24 hoursare provided, as is distribution of self-reading dosimeters to determine dosesreceived by emergency personnel. Detailed procedures for personnelmonitoring are included in the EPIPs (see Appendix I).




6.2 Decontamination and First Aid

Facilities and supplies for decontaminating personnel are available at the RP station,OSC, and OSRPF. All personnel leaving the controlled area or leaving a contaminatedarea will be monitored for contamination. During emergencies, other onsite personnelwill be checked for contamination as necessary. Measures will be taken to minimize thespread of contamination.

Such measures may include isolating affected areas, placing contaminated personnel inclean protective clothing before moving, and decontaminating personnel, their clothing,and equipment prior to release. Personnel found to be contaminated will bedecontaminated under the direction of RP personnel.

Emergency first aid and medical treatment will be given to injured or ill personnel.Onshift personnel trained in first-aid are available onsite, 24 hour-per-day, and will assistinjured or ill personnel either at the scene of the accident or in the first-aid room. Ifpersonnel must be transported to medical facilities, measures will be taken to prevent thespread of contamination if present. Such measures may include the placing of affectedpersonnel in clean protective clothing or wrapping in blankets. Inform the organizationswho will provide the transportation and treatment. The plant maintains an onsite first-aidroom located in the Extension Building. The first-aid room is equipped with facilitiessuitable for the temporary care of a victim of an accident or illness until the services of aphysician or transport can be obtained. Additional first-aid supplies are available at thefollowing locations: gatehouses, turbine building, switchyard, Unit I and Unit 2 facades,EOF, TSC, RCA checkpoint, Control Room, Sewage Treatment Plant and RCAMaintenance Shop.

6.3 Medical Transportation

In the event that offsite emergency medical transportation is required, the ManitowocCounty Sheriffs dispatcher will be called. The dispatcher will determine who shouldrespond to the emergency. Normally, the Mishicot emergency vehicle will respond first.If the Mishicot emergency vehicle is unavailable, the City of Two Rivers FireDepartment emergency vehicle will respond.




6.4 Medical Treatment

Arrangements have been made with Two Rivers Community Hospital for treatment ofpersonnel working at PBNP. Hospital personnel have been instructed and trained withregard to treating potentially contaminated patients. In addition, at least two areaphysicians have taken radiological health instruction courses under the sponsorship of theCompany and are on the Two Rivers Community Hospital Staff. The University ofWisconsin Hospital and Clinics in Madison, Wisconsin, will provide backup services inthe event that the services of Two Rivers Community Hospital become unavailable orthat additional services are required. The University Hospital provides instruction andtraining on handling radiological accident patients. Letters or Agreements with respect toarrangements for both hospitals and medical services are referenced in Appendix D.

6.5 Iodine Prophylaxis (Thyroid Protection)

6.5.1 Background

A number of chemical compounds can be ingested before or shortly afterinhalation of radioactive material to inhibit the biological assimilation ofinhaled radionuclides. Of these, stable iodine has received more attention as achemical prophylactic agent than other elements because inhaled radioiodinepresents a radiological hazard under certain types of nuclear reactor accidents.

Radioiodine is quickly absorbed into the blood stream and concentratesprimarily in the thyroid gland. This can result in significant doses to thethyroid. Therefore, a protective action to be considered after an accidentinvolving the release containing radioactive iodine, is the use of stable iodineas a thyroid-blocking agent. This can reduce the accumulation of radioactiveiodine in the thyroid gland.




6.5.2 Criteria for Use

The criteria for administering a thyroid-blocking agent (Potassium Iodide) toemergency personnel depends on the projected absorbed dose to the thyroidbased on the severity and magnitude of the accident. If the initial estimate atthe plant indicates that thyroid total absorbed doses of 25 rem or more areprojected, a thyroid-blocking agent will be distributed to Company emergencyand support personnel. Prior to distribution, the Rad/Chem Coordinator orDose/PAR Coordinator will make this recommendation with final approval bythe Emergency Director.

For the greatest effectiveness, the thyroid-blocking agent should beadministered as soon as possible, preferably immediately before the exposureor within two hours of exposure. For most individuals the majority ofradioiodine uptake by the thyroid occurs within 12 hours after a short-termexposure. The initial administration of a blocking agent will be of some valueeven as long as 4-8 hours after the exposure period. The determination ofwhether the thyroid-blocking agent should be continued on a daily basis willbe made by the Medical Services Division after evaluation of the situation.


C*. NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL

C.EP6.0Revision 41November 30, 1999

EMERGENCY MEASURES

TABLE 6-1

ASSESSMENT ACTIONS*

Action Description

1. Surveillance of Control RoomInstrumentation

2. In-plant Radiological Surveys

3. Site Boundary Control CenterSurveys

4. Offsite Consequence Assessment

5. Environmental Monitoring

Radiation levels, pressures, temperatures, levels, flows, and meteorological data are monitored. The ControlRoom operators can assess plant status by observing sensor readout. Most sensors have visual and audioalarms. Primary and secondary system data will be provided to the Shift Technical Advisor as necessary fortheir assessment. Control Room operators will take corrective actions as necessary

The re-entry teams with RP personnel assigned, as necessary, will perform these surveys. The radiationlevels on the plant's fixed area and process monitoring systems will be obtained from the TSC or ControlRoom to assist in these evaluations. Surveys of equipment and personnel for contamination are done withportable equipment from the emergency lockers or other devices used routinely.

Handled in same fashion as in-plant surveys by the RP personnel teams.

The radiological assessment personnel will use effluent monitors and meteorological data to makeprojections of offsite consequences. Radiation Field Monitoring Teams will take direct readings (air, water,soil, vegetation).

Samples of various environmental media are collected and analyzed by either PBNP personnel or an outsidecontractor laboratory. Results will be evaluated by WE personnel.

*NOTE: Detailed assessment actions procedures are described in tie EPIPs.


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C.

TABLE 6-2

ASSEMBLY AND EVACUATION ACTIONS

I

EvacuationClassification

Public Visitors(Fishing Pier, Energy

Center, Beach)

EmergencyResponse

Organization

Plant Personnel, CorporatePersonnel, Contractors,

Temporary Employees andVisitors Not Assigned

Emergency Duties'

Limited Plant Evacuation

Plant and Exclusion AreaAssembly

Take Action as Directed

Report to SBCC, Two CreeksTown Hall or Two RiversNational Guard Armory asdirected.


Report to AssignedEmergency Respqnse Facility.


Report to NSB Cafeteria,Admin. Bldg. El. 26',NES Cafeteria, TrainingBuilding North Foyer, orWarehouse #4

Plant and Exclusion AreaEvacuation


Report to AssignedEmergency Response Facility.


1 Personnel working outside protected area should report to nearest exclusion area assembly area, SBCC, Two Creeks Town Hall, or Two Rivers National Guard Armory, asdirected.


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C,EMERGENCY MEASURES

TABLE 6-3

STATE AND LOCAL AGENCIES IMPLEMENTED PROTECTIVE ACTIONS

NOTE: Point Beach Nuclear Plant will only recommend evacuation as an offsite protective action.

ACCIDENT PHASE EXPOSURE PATHWAY EXAMPLES OF ACTIONS TO BE IMPLEMENTED

Emergency Phase 1(0.5 to 24 hours)*

Inhalation of gases, radioiodine, or particulate

Evacuation, access control, shelter, respiratory protection,thyroid protection

Direct whole body exposure Evacuation, access control, shelter

Intermediate Phase 2(24 hours to 30 days)*

Ingestion of milk Take cows off pasture, prevent cows from drinking surfacewater, discard contaminated milk or divert to storedproducts such as cheese.

Ingestion of fruits and produce

Ingestion of water

Whole body exposure and inhalation

Wash all produce or impnound produce, delay harvest untilapproved, substitute uncontaminated produce.

Isolate contaminated supplies, substitute from othersources, filter, demineralize.

Relocation, access control, decontamination


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C EP 6.0Revision 41November 3.0, 1999

C=

Table 6-3

ACCIDENT PHASE EXPOSURE PATHWAY EXAMPLES OF ACTIONS TO BE IMPLEMENTED

Long Term Phase 3(over 30 days)*

Ingestion of food and water contaminated fromthe soil either by resuspension or uptake throughroots

Decontamination, condemnation or destruction of food,deep plowing, condemnation or alternate use of land

Whole body exposure from deposition material orinhalation of resuspended material.

Relocation, access control, decontamination, deep plowing

IAssessment Reporting In the case of offsite consequences, the federal, state, and local agencies are-immediately notified in accordance

with the Emergency Plan. Predetermined criteria are used to recommend various protective actions for thepopulation at risk.

(1) Emergency phase - Time period of majority of release and subsequent plume exposure.

(2) Intermediate phase - Time period of moderate continuous release with plume exposure and contamination of environment.

(3) Long-Term Phase - Recovery period.

* "Typical" post-accident time periods.



EMERGENCY MEASURES


TABLE 6-4

REPRESENTATIVE SHIELDING FACTORS FROM GAMMA CLOUD SOURCE*

Shielding RepresentativeStructure or Location Factor (l) Range

Outside 1.0

Vehicles 1.0

Wood-frame house (2) 0.9(no basement)

Basement of wood house 0.6 0.1 to 0.7 (3)

Masonry House (no basement) 0.6 0.4 to 0.7 (3)

Basement of masonry house 0.4 0.1 to 0.5 (3)

Large office or industrial building 0.2 0.1 to 0.3 (3,4)

(1) The ratio of the dose received inside the structure to the dose that would be received outside thestructure.

(2) A wood frame house with brick or stone veneer is approximately equivalent to a masonry housefor shielding purposes.

(3) This range is mainly due to different wall materials and different geometries.

(4) The shielding factor depends on where the personnel are located within the building (e.g., thebasement or an inside room).

*Taken from SAND 77-1725 (Unlimited Release)




TABLE 6-5

SELECTED SHIELDING FACTORS FOR AIRBORNE RADIONUCLIDES*

Wood house, no basement 0.9

Wood house, basement 0.6

Brick house, no basement 0.6

Brick house, basement 0.4

Large office or industrial building 0.2

Outside 1.0




EMERGENCY MEASURES


TABLE 6-6

REPRESENTATIVE SHIELDING FACTORS FOR SURFACE DEPOSITED RADIONUCLIDES*

RepresentativeShieldingFactor (;Structure of Location

RepresentativeRange

1 m above an infinite smooth surface

I m above ordinary ground

1 m above center of 50' road-ways, 50%decontaminated

Cars on 50' road:Road fully contaminatedRoad 50% decontaminatedRoad fully decontaminated

Trains

One and two-story wood-framehouse (no basement)

1.00

0.70

0.55

0.50.5

0.25

0.40

0.4(2)

0.47-0.85

0.4-0.6

0.4-0.70.4-0.60.2-0.5

0.3-0.5

0.2-0.5

One and two-story blockhouse (no basement)

House basement, one or two wallsfully exposed:

One story, less than 2' ofbasement, walls exposed

Two stories, less than 2' ofbasement, walls exposed

0.1(2)

0.05(2)

0.03(2)

0.04-0.40

0.03-0.15

0.03-0.07

0.02-0.05

Three- or four-story structures,5,000 to 10,000 ft per floor:First and second floorsBasement

Multi-story structures>10,000 ft2 per floor:Upper floorsBasement

0.05(2)0.01(2)

0.01(2)

0.005(2)

0.01-0.080.001-0.07

0.001-0.020.001-0.015

(1) The ratio of dose received inside the structure to the dose that would be received outside thestructure.

(2) Away from doors and windows.



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V -EP 6.0Revision 41November 30, 1999

C

TABLE 6-7

USE OF PROTECTIVE EQUIPMENT AND SUPPLIES

Equipment Criteria for Issuance* Storage Location Means of Distribution

a. Respiratory Equipment:

1) Full-Face Respirator(Filter)**Protection Factor-50

2) Continuous FlowAir- Line (SuppliedAir, Full-FaceRespirator)ProtectionFactor - 2,000

3) Self-ContainedBreathing ApparatusProtectionFactor - 10,000

For areas of airborneparticulate activityonly (Notes 3 and 4).

For areas of airborne particulate, iodine,gas activity, or combinations of same(Notes 2 and 4).

(a) Inhalation hazard during fire fighting(b) For areas of air-borne particulate

iodine, gas activity, or combination ofsame (Notes 1, 2 and 4).

(a) Control Room(b) RP Station(c) Emergency Equipment

Lockers(d) Onsite OSC

(Staging Area)(e) EOF

(a) Control Room(b) RP Station(c) Emergency Equipment

Lockers

(a) Control Room(b) RP Station(c) TSC(d) Emergency Equipment

Lockers

(a) Used as needed by reentrypersonnel

(b) Issued under the control ofRadiation Protection





* Significance of qualifying notes must be recognized.

** The proper type of air-purifying filters, cartridges, and canisters with the respirator must be chosen for the hazard present in the atmosphere.


c NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL

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( EP 6.0Revisioni 41November 30, 1999

C

Table 6-7

Equipment Criteria for Issuance*

b. Protective Clothing As needed in areas of known(Coveralls, Hoods, Boots, contaminationGloves)

c.Potassium Iodide for Reduce accumulation of radi(Thyroid-Blocking iodine in the thyroid gland, u!

radiation emergency only

Location

(a) Various areas of the plant(b) EOF

Means of Distribution

Used as needed by reentrypersonnel

Issued as needed underdirection of RP personnel afterapproved by EmergencyDirector

)active (a) Control Roomsed during a (b) TSC/OSC

(c) SBCC

NOTES

(1) This type of respirator provides the greatest protection and is preferred emergency device in unknown or high airborne concentrations.

(2) Limitations on occupancy in gaseous atmospheres will typically be governed by external dose limits.

(3) Respirators with mechanical filters provide no protection against gaseous activity or in oxygen-deficient atmospheres.

(4) Where airborne tritium is involved, filter type respirators are not suitable for protection. Supplied air apparatus (air line or self-contained) arenot recognized as effective for concentrations greater than two times DAC.



EMERGENCY MEASURES


TABLE 6-8

GUIDELINES FOR PROTECTION AGAINST INGESTION OF CONTAMINATION

1.0 SURFACE CONTAMINATION

1.1 Action Levels

1.1.1

1.1.2

1.1.3

Projected gamma dose 22 rem.

Surface contamination levels >200 pCi/m2 one hour post-accident.

Exposure rate Ž1 mR/hr at 1 meter above the ground one hour post-accident.

1.2 Recommended Protective Actions

1.2.1 Evacuate the affected area.

1.2.2 Restrict entry to contaminated offsite areas until radiation levels havedecreased to state of Wisconsin approved levels.

2.0 FOOD AND WATER CONTAMINATION

2.1 Action Levels*

Nuclide*

Concentration inMilk or Water

Prev EmergLevel Level(11Ci/I) (,,Ci/A)

Total Intake via All Foodand Water PathwaysPrev Emerg

Level Level,(h~i) (phi)

Pasture Grass(Fresh Weight)

Prev EmergLevel Level

(pCi/kg) (pCi/kg)

1-131Cs-134Cs-137Sr-90Sr-89

0.0150.150.240.0090.14

0.151.52.40.091.4

0.09 0.94.0 40.07.0 70.00.2 2.02.6 26.0

Emerg = Emergency

0.05,0.81.3

0.183.0

0.58.0

13.01.8

30.0Prev = Preventive

* The preventive level corresponds to a 1.5 rem projected dose commitment to the thyroid or0.5 rem projected dose commitment to the whole body, bone marrow, or any other organ. Theemergency level corresponds to a 15 rem projected dose commitment to the thyroid or 5 remprojected dose commitment to the whole body, bone marrow, or any other organ.

** If other nuclides are present, Regulatory Guide 1.109 will be used to calculate the dose to thecritical organ. Infants are the critical segment of the population.

Reference: U.S. EPA Publication EPA 400-R-92-001, Manual of Protective Action Guides andProtective Actions for Nuclear Incidents, May 1992.



EMERGENCY MEASURES


Table 6-8

2.2 Recommended Protective Actions

Preventive

1. Removal of lactating cows fromcontaminated pasture andsubstitution of uncontaminatedfeed.

2. Substitute source ofuncontaminated water.

3. Withhold contaminated milk frommarket to allow radioactive decay

4. Divert fluid milk to production ofdry whole milk, butter, etc.

Emergency

Isolate food and water from itsintroduction into commerce afterconsidering:

a. Availability of other possible actions;

b. Importance of particular food innutrition;

c. Time and effort to take action;

d. Availability of other foods.



EMERGENCY MEASURES


TABLE 6-9

ADMINISTRATIVE DOSE LEVELS4

Category TEDE3

A. Daily Administrative Dose Level

B. Weekly Administrative Dose Level

400 millirem'

- -800 millirem2

C. Yearly Administrative Dose Level

1. Doses received only at PBNP

2. All doses received in current year.

3. The sum of the deep-dose equivalent and thecommitted dose equivalent to any organ otherthan the lens of the eye.

4. Eye dose equivalent

5. Skin shallow-dose equivalent

6. Extremity shallow-dose equivalent

2 rem

4 rem

40 rem

4 rem

40 rem

40 rem

Notes:

1. Exposure in excess of the 400 millirem level up to but not exceeding the individual's maximumallowed current year dose requires the approval of the employee's immediate supervisor orliaison. If the daily administrative dose level extension exceeds 800 millirem, the weekly doselevel will also need to be extended.

2. Exposure in excess of the 800 millirem level up to but not exceeding the individual's maximumallowed current year dose requires the approval of the employee's group head or designatedalternate.

3. Total effective dose equivalent (TEDE) is the sum of the deep-dose equivalent (for externalexposure) and the committed effective dose equivalent (for internal exposures).

4. Levels are derived from the Radiation Protection Manuals.



November 30, 1999EMERGENCY FACILITIES AND EQUIPMENT

1.0 DISCUSSION

This section of the Emergency Plan identifies, describes, and gives locations of emergencyoperation centers, support centers, communication systems, and first-aid and medical facilities.

2.0 CENTERS FOR EMERGENCY OPERATIONS

The emergency response facilities (ERFs) are coordinated centers, separated physically tominimize interference and confusion, and connected by dedicated communications lines toensure an uninterrupted flow of information. Figure 7-1 shows the emergency communicationsnetwork that will allow coordination of all phases of the emergency response operations.

2.1 Emergency Operations Facility (EOF) (See EP 2.0)

The EOF is located at the SBCC with an alternate location at WE Corporate Headquartersin Milwaukee, WI. Communications links will be maintained with the TSC, JPIC,OSRPF, corporate offices, designated offsite federal and state agencies, and offsite fieldmonitoring teams. Up to 700 sq. ft. can be made available to accommodate state andlocal agency personnel.

This facility, under the direction of the EOF Manager, is the focal point for overall PBNPemergency response and is the location of primary interface between PBNP and offsiteagencies. This facility will be activated by plant personnel within one hour of thedeclaration of a Alert or higher classification. Comprehensive coordination is achievedby:

2.1.1 The Emergency Director is located in this facility and responsible for theoverall management of the emergency response and recovery operations forWisconsin Electric.

2.1.2 Maintaining communication links with the other emergency response facilities(ERFs) and receiving periodic updates of the progress of the emergencyprocedures.

2.1.3 Providing a single contact point for state and local emergency responseagencies and providing timely, accurate information.

2.1.4 Coordinating the transfer of injured personnel who are radiologicallycontaminated and need treatment by a local health care personnel.

2.1.5 Providing for offsite radiological surveys including transportation, equipment,and personnel.

2.1.6 Act as focal point for security and traffic control.




2.1.7 Act as focal point for technical review of information released to the media.

2.1.8 Disseminating information to the Corporate Officers and company personnelfor interdepartmental support and necessary authorizations needed to facilitatesupport activities.

2.1.9. Managing recovery operations of an emergency (long-term staffing,scheduling, and expediting).

2.1.10 Implement Quality control program for construction and repair tasks that maybe necessary.

2.1.11 Primary interface between outside organizations, responding vendors andcontractors.

2.1.12 Monitor meteorological data, plant conditions and data.

2.2 Offsite Radiation Protection Facility (OSRPF) (See EP 2.0)

The radiation protection operation of the SBCC is the responsibility of the OffsiteRadiation Protection Coordinator who reports to the Dose/PAR Coordinator at the EOF.The facility will be activated by plant personnel within one hour of an Alert or higherclassification. This portion of the SBCC provides:

2.2.1 Personnel accountability, contamination monitoring, and a decontaminationpoint for evacuated visitors, plant and contractor personnel.

2.2.2 A Radiation Protection control point for individuals entering or leaving thesite.

2.2.3 A central point for offsite radiological field monitoring teams.

2.3 Technical Support Center (TSC) (See EP 2.0)

The TSC is located on El. 8' of the Admin Building. There are direct communicationsbetween the Control Room, OSC, and EOF.

This facility, under the direction of the TSC Manager coordinates all onsite emergencyresponse. This facility will be activated by plant personnel within one hour of thedeclaration of an Alert or higher classification. This facility provides as:

2.3.1 The primary communications link between the Control Room, OSC, and EOF.

2.3.2 Focal point for all onsite activities during emergency response.

2.3.3 Technical and management support of the Control Room.




2.3.4 Plant and computer system monitoring facility to provide real time data totechnical advisory personnel for the evaluation of plant conditions andrecommendation of response procedures.

2.3.5 Technical reference library with files containing appropriate drawings andsystem descriptions.

2.3.6 Onsite monitoring directed from the TSC to assist in radiological surveys,personnel monitoring, decontamination, reentry, and rescue procedures.

2.3.7 Current meteorological information can be obtained from the PPCS terminal.

2.3.8 Implementing recovery operations of an emergency.

2.3.9 Backup RP counting and sample analysis facility.

2.3.10 Providing independent engineering and technical support as requested.

2.4 Operations Support Center (OSC) (See EP 2.0)

The OSC is located on El. 8' of the Admin building. There are direct communicationsbetween the TSC and the Control Room.

This facility, under the direction of the Reentry Team Coordinator, coordinates incomingand outgoing personnel during emergency reentry operations. This facility will beactivated by plant personnel within one hour of the declaration of a Alert or higherclassification. The OSC provides:

2.4.1 Staging area to brief Control Room personnel of the emergency condition ofthe plant and thus minimize shift turnover time.

2.4.2 Coordination area for fire fighting activities.

2.4.3 Coordination area for mechanics, electricians and technicians to be dispatchedto areas requiring their support.

2.4.4 Coordination area for search and rescue searches of missing persons orsecurity breaches.

2.4.5 Functions as the dispatch center for all personnel reentering theplant.




2.5 Control Room (CR) (See EP 2.0, Section 2.5)

The Control Room is the primary operations center during events classified as UnusualEvent and prior to the activation of the other ERFs for more serious accidents. The DutyShift Superintendent is responsible for initiating and coordinating all appropriate EPIPsfrom the Control Room until other ERFs are activated to assume responsibilities. Allplant control manipulation is conducted from this area under the Duty ShiftSuperintendent's cognizance. Access to the Control Room is administratively controlled.

2.6 Security Building (Extension Building) (See EP 2.0)

This facility, located in the extension building, is under the supervision of the SecurityCoordinator in the TSC, who coordinates:

2.6.1 Primary access control at the gatehouse or Site Boundary Control Center tolimit both personnel and vehicular traffic to and from the site.

2.6.2 Control point for personnel accountability during plant assembly andevacuation procedures.

Site security personnel assist as required with the emergency response operations. Theyinitially report to the Security Shift Commander until the TSC Manager and/or SecurityCoordinator arrives. In the event that the security building is not radiologically habitable,the designated alternate location for security functions is the SBCC.

2.7 Joint Public Information Center (JPIC) (See EP 2.0)

The JPIC is located at the Wisconsin Public Service corporate office at 700 North AdamsStreet, Green Bay, WI. The JPIC will be activated at a Site Emergency or higher

. classification.

This facility, under the direction of the JPIC Manager, is responsible for providing thenews media with information concerning the emergency and ensuring that accurateinformation is provided to the public. This facility will provide periodic updates of theemergency situation and coordinate the public relations of offices for NRC, FEMA, state,and local agencies to ensure that consolidated official status reports are provided. TheJPIC will maintain communications links with the EOF and designated offsite newsmedia agencies. An emergency hotline telephone number will be available for the public.

-Paage 4 of 26 INFORMATION USE



3.0 COMMUNICATIONS SYSTEMS

The details of the onsite and offsite emergency communications networks are shown inFigure 7-1. The systems are designed to provide reliable communication links between thevarious emergency centers and offsite authorities. It consists of a combination of the plantpublic address system, plant telephone system, multiple telephone lines to outside exchanges,including dedicated telephone lines, utility communications and paging system, and radiocommunications facilities. A brief detailed description is as follows:

3.1 Internal plant five-channel multi-station public address system (Gai-tronics). Each publicaddress station has the capability of general announcement or party-line conversation viaany channel.

3.2 PBX telephone system with at least 1,200 telephone extensions, including locations at theTSC, OSC, EOF and OSRPF. A switchboard of the PBX system is located in theNuclear Engineering Building. The PBX system has a battery backup power supply withat least 8 hours of capacity. Eight in-plant extensions automatically take over eightMishicot, Wisconsin exchange lines upon loss of all in-plant PBX system power.Milwaukee and Appleton microwave lines are available in the Control Room, TSC, EOFand Security office of the Extension Building.

3.3 Telephone lines to outside exchanges include six Mishicot, Wisconsin exchange lines;there are thirteen Mishicot exchange lines in the TSC, 20 more in the SBCC, and four payphone lines: one inside the South Service Building, one inside the north gatehouse, oneinside the entrance to the radiation control area (RCA), and one in the North ServiceBuilding cafeteria. Also, the Control Room, TSC and EOF have FTS-2000 circuits usedfor the emergency response data system (ERDS), the emergency notificationsystem (ENS), the health physics network (HPN), and the counterpart links as defined bythe NRC. The JPIC has adequate telephones installed which are available for use during

* an emergency.

3.4 An internal sound-powered communications system with headset plug-in connectionsexists throughout the plant, including the Control Room.




3.5 The PBNP FM radio system has base station consoles in the Control Room, OSC, centralalarm station, secondary alarm station, and the SBCC. The radio system utilizes anautomatically actuated radio transmitter (repeater) which retransmits signals receivedfrom hand held units. This extends the hand held units' range and provides for betterreception throughout the plant. These hand held units are available in the Control Room,TSC, Radiation Protection station, SBCC, and from Security. The radio system is usedfor in-plant security, in-plant operations, in-plant maintenance and Radiation Protectionsurveys, and would be used during emergencies. Using this radio system, Control Roompersonnel can also communicate 24 hours a day with the Manitowoc County SheriffsDepartment. This allows indirect communications with the Two Rivers CommunityHospital. The radio system also provides a direct communications link with the securitybuilding or the TSC from the Control Room.

A more detailed description of the PBNP radio system is provided in the PBNP OperatingInstructions.

3.6 The Two-Digit Dial Select circuit is a unique, dedicated telephone network and is used asthe primary means of notifying the state and counties of events at PBNP. The systemallows for conference calling with any or all of the following locations: Manitowoc andKewaunee County EOCs and Sheriff Dispatch centers, Wisconsin EOC and State Patrolin Madison, Kewaunee Nuclear Power Plant CR, EOF and TSC, and Point Beach NuclearPlant TSC, EOF, AEOF and Control Room. Commercial telephones are used as theback-up means for notification if the Two-Digit Dial Select System becomesout-of-service.

3.7 Radios are available for communications between offsite field monitoring teams and theSBCC. These radios are part of the FM radio system discussed in Section 3.5. Twocellular telephones are also available for field team use.

3.8 An inter-plant trouble alarm exists in the Control Room for a link with other WisconsinElectric power plants and System Control.

4.0 ASSESSMENT FACILITIES

The monitoring instruments and laboratory facilities needed to initiate emergency measures aswell as those to be used for continuing assessment, are available both for onsite and offsite use.

4.1 The geophysical, radiological, process, and fire detection onsite equipment and facilitiesare listed on Table 7-1.

4.2 The geophysical, radiological, and fixed and mobile offsite equipment and facilities arelisted on Table 7-2.

4.3 Methods for detecting and measuring radioiodine concentrations in the field of5 x 10- pCi/cc using a single channel analyzer and silver zeolite filters have beenestablished. Kewaunee Nuclear Power Plant has agreed to count iodine samples at therequest of PBNP.




5.0 PROTECTIVE FACILITIES AND EQUIPMENT

The Control Room is intended to serve as the onsite protective facility. It is designed to behabitable under accident conditions. Emergency lighting, power, air filtration, ventilation-system, and shielding walls enable operators to remain in the Control Room to ensure the reactorcan be maintained in a safe condition. In addition, the operators will be able to evaluate plantconditions and relay pertinent information and data to the appropriate onsite and offsiteemergency centers, personnel and agencies during all emergencies. To ensure that operatingshift and other personnel can remain self-sufficient, portable radiation monitors, respiratory-equipment, portable lighting, and alternate communications systems are maintained in theControl Room. During extreme conditions, selected personnel from the TSC will evacuate to theControl Room.

The Technical Support Center and Emergency Operations Facility have similar systems to ensurefacility habitability is maintained.

6.0 FIRST-AID AND MEDICAL FACILITIES

6.1 Onsite

A permanent medical facility is provided onsite at PBNP and is located in the securitybuilding (extension building) on the first level. It contains the supplies needed forfirst-aid treatment. Stretcher baskets, first-aid, trauma and burn kits are at variouslocations throughout the plant. The first-aid treatment of injured personnel shall beadministered by trained personnel.

6.2 Offsite

Medical care beyond that available onsite may be obtained through local medicalemergency responders dispatched by the Manitowoc County Sheriffs Department.Subsequently, seriously ill or injured individuals may be transported to a hospital foradditional care in accordance with PBNP EPIPs.

Wisconsin Electric, in cooperation with Wisconsin Public Service Corporation and theTwo Rivers Community Hospital, maintains a facility equipped to provide first aid,emergency medical stabilization treatment, and decontamination for ill or injuredpersonnel from Point Beach Nuclear Plant. The Two Rivers Community Hospital, whichis available 24 hours a day, is equipped with a sink, decontamination supplies, protectiveclothing, signs and other necessary equipment.

6.3 Responsibilities

A full-time occupational health nurse is assigned to Point Beach and is responsible fordefining the requirements for the first-aid equipment throughout the plant. The PBNPSupervisor Emergency Preparedness is responsible for maintaining the supply inventory.Appendix H of this plan references lists of available first aid equipment and locations.




7.0 DAMAGE CONTROL EQUIPMENT AND SUPPLIES

Damage control equipment consisting of fire hose stations, fire extinguishers, fire hydrants, andportable lanterns are located throughout the plant to be used by the fire brigade teams in theevent of a fire. The PBNP Fire Protection Manual describes the specific details of fireprotection, fire fighting, damage control including equipment usage and location. In addition,self-contained breathing apparatus are located at strategic locations in the plant to be used asnecessary for fire fighting, entry into airborne radioactive areas or entry into toxic gas areas.Other damage control equipment and supplies will be used to effect repairs depending on thesituation at hand (e.g., steam suits and miscellaneous equipment at the plant).

8.0 METEOROLOGICAL EQUIPMENT

PBNP has a meteorological monitoring system with instrumentation at three stations. Theprimary and backup meteorological monitoring stations are located near-shore. The third stationis located about 8 miles inland and monitors for lake effect breezes. The system configurationsare described in Tables 7-1 and 7-2. Meteorological data is displayed on strip charts in theControl Room and on PPCS terminals in the Control Room, TSC and EOF.

In the event that data from the PBNP meteorological monitoring system is unavailable, data canbe obtained from the Kewaunee Nuclear Power Plant, local Coast Guard Station or the NationalWeather Service.

Maintenance and calibration of the meteorological system will be performed in accordance withEPMP 5.0 Post-TMI Meteorological Monitoring Program Design, Operations, and Maintenance.

9.0 PROMPT NOTIFICATION SYSTEM

Details of the PBNP prompt notification system are shown on Figure 7-2. Listing of theequipment can be found on Table 7-3.

The system is designed to provide notification of the public within 10 miles of PBNP. The-system as shown includes 27 sirens. Because PBNP essentially shares an EPZ with theKewaunee Nuclear Power Plant (KNPP), operated by Wisconsin Public Service Corporation, the14 sirens located in Manitowoc County are maintained by Wisconsin Electric; the 13 sirens inKewaunee County are maintained by Wisconsin Public Service Corporation. State and localresponse plans describe the use of this siren system and the associated provisions for use of localradio stations and the local Emergency Alerting System for message dissemination.

10.0 MANITOWOC AND KEWAUNEE COUNTY EMERGENCY OPERATIONS CENTERS

Manitowoc county has a permanent emergency operations center at the Manitowoc CountySheriffs Department. Kewaunee County has a permanent emergency operations center at theAlgoma Police Department. These centers are used for command and control of county agencyresponse to an emergency.



EMERGENCY FACILITIES AND EQUIPMENT

C EP 7.0Revision 42November 30, 1999

C..

TABLE 7-1ONSITE ASSESSMENT EQUIPMENT & FACILITIES

SYSTEM EQUIPMENT FUNCTIONGeophysical Monitors

Meteorological

Primary Tower 1 wind speed indicatorI wind direction indicatorAT sensorI wind speed indicator1 wind direction indicator withcaO calculator

Monitor wind speed at El. 45 metersMonitor wind direction at El. 45 metersMonitor temperature for AT at El. 45 metersMonitor wind speed at El. 10 metersMonitor wind direction. Monitorstandard deviation of wind directionat El. 10 meters.

AT sensor Monitor temperature for AT at El. 10 meters.

Backup Tower 1 wind speed indicatorI wind direction indicator1 aO calculator

Monitor wind speed at El. 10 metersMonitor wind direction at El. 10 metersMonitor standard deviation of wind directionat El. 10 meters

Seismic

Hydrological

4 strong -motion accelerographs

6 lake resistance temperaturedetectorsI surge chamber level indicatorI forebay level indicator

Record ground accelerations(Unit 1 facade, #3 warehouse, drummingarea and auxiliary feed pump room)

Monitor lake temperature 500 yds off shore

May function as a lake level indicatorMay function as a lake level indicator


c NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL


(7 cEP 7.0Revision 42November 30, 1999

Table 7-1

LISTING OF RMS AREA MONITORS BY PLANT LOCATION

Location IndicationMonitor

RE-IO1 Control Room

1(2)RE- 102 ContainmentLow Range

RE- 103 Chemistry Lab

1(2)RE- 104 Charging PumpRoom Low Range

RE- 105 Spent Fuel PoolLow Range

1(2)RE-106 Primary SideSample Room Low Range

1(2)RE-107 Seal Table

RE-108 Drumming Station

West wall of Control Room.

El. 66' near access hatch on eastside.

East wall of chemistry lab nearcounting room door.

Mounted on west side of shield walleast of cubicles on El. 8' of aux.building.

Mounted on railing just northeastof spent fuel pool on El. 66' of aux.building.

Mounted on west wall, towards northcorner of sample room on El. 26' ofaux. building.

Mounted on wall just above seal tableon El. 46' of containment.

Mounted inside the Atcor wasteprocessing cubicle.

Shifts Control Room ventilation to 100%recirculation.

Provides dose rates within containmentaround access hatch.

Provides indication of dose rates inchemistry lab and associated hallways.

Indicates dose rates in hallways east ofcharging pump cubicles.

Provides indication of dose rates in thevicinity of the spent fuel pool. Thismonitor is affected by high radiationlevels in containment.

When sampling system is in operation, itindicates dose rate inside sample room.

Provides an indication of general areadose rate near seal table.

Provides dose rate indication within thedrumming station.

Page IO of 26 INFORMATION USE




C

Table 7-1

Monitor Location Indication

1(2)RE- 109 Failed Fuel

RE-I IO SI Pump Room

RE- IlI C59 Panel

RE-1 12 Central PAB

RE-1 13 El. -19' AuxiliaryBuilding

RE-I 14 El. 26' AuxiliaryBuilding

RE- 116 Letdown ValveGallery

1(2)RM-126 U2 Containment1(2)RM-127 High Range1(2)RM-128

Mounted on south wall near eastcorner of primary side sample roomon El. 26' of aux. building.

Located on north wall just west ofpassageway in SI pump room.

Mounted on top of C59 instrumentpanel on El. 26' of aux. building.

Mounted on north wall just east ofpipeway No. 3 on El. 8' of aux.building.

Mounted in general area of El. -19'of aux. building.

Mounted east of CVCS holdup tanks onEl. 26'.

Mounted by north entrance to valvegallery on El. 26' of aux. building.

Mounted in containment along theperimeter on the El. 66'.

Provides an indication of failed fuel bymonitoring the primary coolant sampleactivity.

Provides an indication of the dose ratein general area of SI pumps.

Provides general area dose rate near C59panel.

Indicates general area dose rate on El. 8'of aux. building.

Provides an indication of the dose rate inaux. building sump and general area ofEl. -19'.

Indicates general area dose rate in cubicle.

Indicates general area dose rate in letdownvalve gallery.

Provides an indication of general area doserates under accident conditions.


(CNUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL



(7'

Table 7-1


1(2)RE-134 Charging PumpRoom High Range

RE-135 Spent Fuel PoolHigh Range

1(2)RE-136 Primary SideSample Room High Range

RE-140 SI Pump Room HighRange

Mounted next to 1(2)RE-104 on westside of shield wall, east of cubicleson El. 8' of aux. building.

Mounted next to 1(2)RE-105 on railingjust northeast of spent fuel pool onEl. 66' of aux. building.

Mounted next to 1(2)RE- 106 on westwall, towards north corner of sampleroom on El. 26' of aux. building.

Mounted next to RE-i 10 on northwall just west of passageway inSI pump room.

Provides an indication of general area doserates in the event low-range monitor pegsoffscale high.

Provides an indication of general areadose rates in the event low-rangemonitor pegs offscale high.




CNUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL


( EP 7.0Revision 42November 30, 1999

(7

Table 7-1

LISTING OF RMS PROCESS MONITORS BY PLANT LOCATION


The following process monitors may be used in evaluating potential airborne contamination levels within the plant. Whenever there areindications of high airborne activity being discharged through a vent stack, there is always the possibility of in-plant airborne contamination.

1(2)RE-211 ContainmentAir Particulate

1(2)RE-2 11 B ContainmentBackground

1(2)RE-212 ContainmentNoble Gas

RE-214 Aux. Building VentStack Noble Gas

1(2)RE-215 Condenser AirEjector Noble Gas

Located in cubicle on east side ofEl. 52' of containment facade.

Located next to 1 (2)RE-2 11 incubicle.

Located in series with 1(2)RE-21 Ion detector skid in the cubicle onEl. 52' of containment facade.

Mounted on aux. building exhauststack at about El. 80' in Unit 1facade just south of elevator.

Mounted on west wall of El. 46' inturbine hall between MSRs.

Indicates particulate activity inside containmentfacade or purge exhaust stack. There are no control functionsassociated with this monitor.

Provides background activity for both 1(2)RE-211and 1(2)RE-212 for background subtraction,if used.

Provides indication of containment noble gas activity.Isolates containment ventilation upon high activity.

Indicates any gaseous release from spent fuel pit areaand the drumming station. Indicative of potential aux.building airborne activity. Shuts the vent gas releasevalve and initiates aux. building exhaust filtration.

Indicative of steam generator primary-to-secondary leak.May be indicative of a potential airborne radiationexposure in turbine hall.


C-NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL



C

Table 7-1


1(2)RE-216 Containment FanCoolers SW Return LiquidProcess

1(2)RE-216B ContainmentFan Coolers Background

1(2)RE-217 ComponentCooling Water LiquidProcess

RE-218 Waste DisposalSystem Liquid Process

RE-218B Waste DisposalSystem Background

1(2)RE-219 Steam GeneratorBlowdown Liquid Process

1(2)RE-219B Steam GeneratorBlowdown Background

In Unit 1, located west and slightlysouth of C59 panel. In Unit 2, locatedwest and slightly north of C59 panel.

Located next to 1(2)RE-216 monitor.

In Unit 1, located in overhead just northof stairs going from El. 8'of aux. building to C59 panel area. InUnit 2, located in overhead just west ofUnit 2 component cooling water pumps.

Located on east wall of waste condensatecubicle across from component coolingwater pump on El. 8' of aux. building.

Located next to RE-218 monitor.

Located outside each primary sidesample room on El. 26' of aux.building.

Located next to 1(2)RE-219monitor.

Provides indication of potential contaminationof cooling water.

Provides background data for the 1(2)RE-216liquid process monitor, if used.

Provides indication of component coolingwater contamination. Shuts componentcooling water surge tank vent.

Monitors waste condensate activity being discharged.Upon exceeding high level setpoint, discharge of wastecondensate is secured.

Provides background activity level for RE-218liquid process monitor, if used.

Provides an indication of steam generatorblowdown activity. Secures steam generatorblowdown and blowdown tank outlet valves,and steam generator sample valves.

Provides background activity level for1(2)RE-219 liquid process monitor, if used.


C.NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL



(1

Table 7-1


RE-220 Spent Fuel Pool HeatExchanger Service WaterLiquid Process

RE-220B Spent Fuel Pool HeatExchanger Service WaterBackground

RE-221 Drumming Area VentStack Noble Gas

1(2)RE-222 Steam GeneratorBlowdown Tank OutletLiquid Process

RE-223 Waste DistillateDischarge Liquid Process

RE-223B Waste DistillateDischarge Background

RE-224 Gas Stripper VentStack Noble Gas

RE-225 Combined Air EjectorLow-Range Noble Gas

Located on El. 46' of aux. buildingon north wall just west of door toUnit 2 containment facade.


Located in exhaust ducting abovedrumming area SPING in northwestcorner of Unit I facade.

Located on El. 26' of aux. buildingon east side of steam generator blowdown tank.

Mounted on east side of C componentcooling water heat exchanger onEl. 46' of aux. building.


Located in northeast corner ofUnit 2, El. 26' containment facadeby exhaust duct.

Located ablove door on El. 46' ofturbine hall leading to I&C office.

Provides an indication of service water contamination froma spent fuel pool heat exchanger tube leak.

Provides background activity level forRE-220 liquid process monitor, if used.

Indicates noble gas activity released from spent fuelpit and drumming area. May be indicative of a potentialaux. building airborne release.

Provides an indication of activity level in blowdowntank. Secures blowdown of steam generators and closesblowdown tank outlet valves.

Monitors activity of waste distillate during discharge.Secures discharge valves upon exceeding setpoint.

Provides background activity level for RE-223liquid process monitor, if used.

Indicates activity of gaseous release fromletdown gas stripper building.

Indicative of primary-to-secondary leak insteam generators.


(f'NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL



C..

Table 7-1


RE-226 Combined Air EjectorHigh-Range Noble Gas

1(2)RE-229 Service WaterDischarge Process

1(2)RE-229B Service WaterDischarge Background

RE-230 Retention PondDischarge Liquid Process

RE-230B Retention PondDischarge Background

1 (2)RE-231 - Line AI (2)RE-232 - Line BSteam Line AtmosphericRelease

RE-234 Control Room lodines

RE-234B Control RoomBackground

Located adjacent to RE-225 low-rangenoble gas monitor.

For Unit 1, located on El. 8' ofaux. building in vent area. ForUnit 2, located in aux. feed pumproom on east side of tunnel.

Located adjacent to 1(2)RE-229 liquidprocess monitor.

Located on El. 8' of turbine halloutside entrance to water treatment.

Located adjacent to RE-230 liquidprocess monitor;

Located on El. 88' of containmentfacade in the area of atmosphericrelief valves - one per steamgenerator.

Located on top of Control Roombuilding on El. 46' of turbine hall.

Located adjacent to RE-234 iodinemonitor.

Provides an indication of the noble gas activityin combined air ejector discharge in the eventRE-225 monitor is pegged offscale high.

Monitors activity of service water discharge.

Provides background activity level for theI(2)RE-229 monitor, if used.

Monitors activity level in retention pond effluent.

Provides background activity level for RE-230liquid monitor.

Monitors activity of steam released.

Monitors iodine activity in Control Room.

Provides background activity level forRE-234 iodine monitor.


C. NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL



Ch.

Table 7-1


RE-235 Control Room NobleGas

RE-237 Technical SupportCenter lodines

RE-238 Technical SupportCenter Noble Gas

RE-239 TSC Area Monitor

RE-240 El. 18.5' Assembly AreaMonitor


Located in ductwork on El. 18.5'of TSC building, in northwest corner.


North Wall of TSC

North Wall of El. 18.5' of TSC

Monitors noble gas activity in Control Room. Initiates 100%recirculation (Mode 3) of Control Room ventilation uponexceeding setpoint.

Monitors iodine activity in the TSC air duct.

Monitors the noble gas activity in TSC air duct.

Indicates general area TSC dose rates.

Indicates general area TSC dose rates.

RE-241 SBCC Iodine Monitor

RE-242 SBCC Noble GasMonitor

SBCC Monitors for iodine activity in the SBCC.

SBCC Monitors for noble gas activity in the SBCC.

RE-243 EOF Area Monitor

1(2)RE-305 SPINGUnit ContainmentPurge ExhaustLow Range Gas

East wall of SBCC-EOF

Located in unit rod drive room.

Indicates general area EOF dose rates.

Monitors noble gas activity in unit containmentpurge exhaust.




C.- EP 7.0Revision 42November 30, 1999

(7

Table 7-1


1(2)RE-306 SPINGUnit ContainmentPurge Exhaust Area

1(2)RE-307 SPINGUnit ContainmentPurge ExhaustMid Range Gas

1(2)RE-309 SPINGUnit ContainmentPurge ExhaustHigh Range Gas

RE-3 15 SPINGAuxiliary Building

VentLow Range Gas

RE-316 SPINGAuxiliary Building

Exhaust Area


VentMid Range Gas




Unit I rod drive room.



Monitors noble gas activity in unitcontainment purge exhaust.

Monitors noble gas activity in unitcontainment purge exhaust.

Monitors Ooble gas activity in unitcontainment purge exhaust.

Monitors noble gas activity in theauxiliary building vent.

Monitors noble gas activity in theauxiliary building.





A- EP 7.0Revision 42November 30, 1999

(7

Table 7-1

SYSTEM EQUIPMENT FUNCTION


VentHigh Range Gas

RE-325 SPINGDrumming Area VentLow Range Gas

RE-326 SPINGDrumming AreaExhaust Area

RE-327 SPINGDrumming Area VentMid Range Gas


Drumming area vent fan area.

Top of drumming area..

Drumming area vent fan area.


Monitors noble gas activity in thedrumming area vent.




c7 NUCLEAR POWER BUSINESS UNITEMERGENCY PLAN MANUAL



c

Table 7-1

SYSTEM

Radiation Monitors &Sampling Equipment

EQUIPMENT

Gamma spectrometers (multichannelanalyzers)

Geiger-Mueller survey instruments(0-1,000 R/hr)

Ionization chambers(0-10,000 R/hr)

Contamination survey instruments

FUNCTION

Isotopic identification and analysis

Measures gamma & beta radiation count rate

Measures gamma & beta radiation dose rate

Count samples, equipment & personnel forgross alpha, gross beta & gamma activity

Air sampling equipment concentration

Measure neutron radiation dose rate

Measures personnel gamma dose

Determines internal radionuclide uptake

Detect products of combustion

Associated with sprinkler systems, detectquick rise of temperature

Neutron survey instruments

TLD/direct reading pocket ion chamber

Whole body counter

Smoke detectors

Rate of rise heat detectors

Fire Detection





C,

Table 7-1

SYSTEM

Facilities

EQUIPMENT

Chemistry laboratory & RP Stationanalyses (available 24 hours per day)

Backup chemistry laboratory andRP station analyses (available24 hours per day) located in theTSC building.

FUNCTION

Equipped for chemical & radiological analyses

Equipped for chemical & radiological analyses

78 TLD radiation monitoring stations




C, EP 7.0Revision 42November 30, 1999

(.

TABLE 7-2

OFFSITE ASSESSMENT EQUIPMENT & FACILITIES

System Equipment Function

Geophysical Monitors

Meteorological

Inland Tower(8 miles west of PBNP)

1 wind speed indicator1 wind direction indicator1 cr0 calculator

Monitor wind speed at El. 10 metersMonitor wind direction El. 10 metersMonitor standard deviation on wind direction

at El. 10 metersMeasures temperatureI temperature indicator

U.S. Coast GuardStation, Two Rivers

Manitowoc CountyAirport

Wind speed & directionLake TemperatureAir TemperatureBarometric Pressure

Wind speed & direction

Monitors wind speed & direction atapproximately El. 60'

Monitors wind speed & directionat approximately El. 20'

Surface temperature Measures temperature

National Weather ServiceAustin Straubel FieldGreen Bay

Wind speed & direction, temperatureweather forecast

Monitor wind speed & direction atapproximately El. 30'. Measurestemperature; dispatch weatherforecast.





C

Table 7-2

System

Radiological Monitors

EnvironmentalMonitoring

* Kewaunee NuclearPower Plant

Laboratory Facilities

Kewaunee NuclearPower Plant

Vendor

Equipment Function

(6) Fixed air sampling stations

(27) TLD radiation monitoring stations

Gamma spectrometer

Chemistry laboratory

Chemistry & counting laboratory

Collect particulate & iodines

Measure environmental radiation

Isotopic identification & analysis

Equipped for chemical & radiologicalanalyses (available 24 hours per day)

Equipped for chemical & radiologicalanalyses (available within 24 hours)




C EP7.0Revision 42November 30, 1999

C

Figure 7-1PBNP EMERGENCY RESPONSE COMMUNICATIONS NETWORK

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Figure 7-2PBNP SIREN SYSTEM

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I(EWAUNEE NUCLEARPOWER PLANT

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OUND CONTOUR MAPmergency Planning Zone

for theee Nuclear Power Plant

andBeach Nuclear Plant

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rURE 7-2

EN SYSTEM




TABLE 7-3

SIREN LOCATIONS

System Design

Siren - Location Sound Output (dBC)

Kewaunee County

KAA Third and Center Streets, Kewaunee 125KAB Mill Road, 0.25 miles south of Hwy-42 119KAC Hwy-29, 0.25 miles west of Birchwood Road 132KAD Hwy-29, 0.25 miles west of Townline Road 125KAE Hwy-163 0.2 miles north of Pine Grove Road 125KAF Church Road, 0.1 miles north of County Trunk J 125KAG Old Settler Road, 0.2 miles north of Townhall Road 125KAH Hwy-142, 0.25, miles north of Old Settler Road 126KAI Hwy-42, at Kewaunee County Nuclear Road 126KAJ Norman Road at Sandy Bay Road 125KAK Hwy-AB, 0.35 north of County Trunk KB 132KAL Harpt Lake Road, 0.25 miles south of Bolt Road 119KAM South Dodge and West Park in Kewaunee 125

Manitowoc County

MKB Stangel Road and Zander Road intersection 132MKC Hwy-42, 0.15 miles south of Two Creeks Road 121.5MKD County Trunk Q, 0.15 miles south of Factory Road 132MKE Nuclear Road, at Twin Elder Road 125MKF Saxonburg Road, 0.35 miles north of Assman Road 126MKG County Trunk V, 0.5 miles west of Hwy-42 119MKH Cherney Road, 0.1 miles south of Fisherville Road 132MKI County Trunk V at Ravine 125MKJ Division Drive at Rawley Road 125MKK Hillcrest Road, 0.75 miles east of Hwy-42 125MPA Crystal Spring Road, 0.15 miles west of County Trunk B 125MCA Forest View Cemetery in the City of Two Rivers 125MCB Washington High School in the City of Two Rivers 126MCC East of Koenig School in the City of Two Rivers 121.5

(See Figure 7-2 for siren locations)



November 30, 1999MAINTAINING EMERGENCY PREPAREDNESS

1.0 DISCUSSION

PBNP maintains, as three separate documents, this Emergency Plan, the Emergency PlanImplementing Procedures (EPIPs), and the Emergency Plan Maintenance Procedures (EPMPs).

It is intended that the Emergency Plan be maintained up to date by using established procedurescontained in the Nuclear Power Procedures Manual. The EPIPs contain detailed informationextracted from the Final Safety Analysis Report (FSAR), other pertinent documents, and detailedsite specific emergency procedures. The EPIPs are controlled by standard plant administrativeprocedures and are distributed and revised accordingly. The Emergency Plan and EPIPs will bereviewed on an annual basis and updated as necessary. Updates will take into account neededchanges identified by drills and exercises.

The EPMPs contain procedures for Emergency Plan equipment maintenance, offsite personnelEmergency Plan training, and for the Emergency Preparedness Program review. The EPMPsalso provide guidance for Emergency Plan drills and exercises.

Approved changes to the Emergency Plan, EPIPs, and EPMPs are forwarded to all organizationsand individuals responsible for their implementation. Revised procedures are dated and pagesmarked to show where changes have been made.

2.0 RESPONSIBILITIES

2.1 Site Vice President

The Site Vice President, also a designated Emergency Director, has the overallresponsibility for radiological emergency response planning, including the developmentand updating of emergency plans and coordination of these plans with otherorganizations, corporate policy and plans, the FSAR, and the agreements andunderstanding with federal, state, and local organizations. The Site Vice President maydesignate personnel to assist in meeting this responsibility.

2.2 Plant Manager

The Plant Manager is responsible for the coordination of efforts in planning, training,exercises, drills, and review and updating of the Emergency Plan and EPIPs includingagreements and understandings with outside agencies. The Plant Manager will receiveappropriate guidance on emergency planning and preparedness from the SiteVice President. The Plant Manager may designate personnel to assist in meeting thisresponsibility.




2.3 Manager - Nuclear Assessment

The Manager - Nuclear Assessment with the Supervisor - Emergency Preparedness willarrange for independent reviews of the emergency preparedness program annually. Thereview will include the Emergency Plan, the EPIPs, practices, training, exercises, drills,records, and equipment. Management controls will be implemented for evaluation andcorrection of review findings. The results of the review will be documented, reported tothe Offsite Review Committee, and retained for a period of at least five years.

2.4 Training Manager

The Training Manager is responsible for assuring that all personnel assigned to the PBNPEmergency Response Organization take part in appropriate training programs on theEmergency Plan and Emergency Plan Implementing Procedures.

2.5 Nuclear Power Business Unit Managers

Each manager is responsible for ensuring that personnel in his/her department receive theappropriate training and indoctrination on the Emergency Plan, and Emergency PlanImplementing Procedures.

2.6 Manager - Emergency Response

The Manager - Emergency Response is responsible for the overall emergency planningefforts and verifying that all emergency preparedness (10 CFR 350) requirements aremaintained to assure operability of the Point Beach Nuclear Plant. He will receiveappropriate guidance on emergency planning and preparedness from the Site VicePresident and the Plant Manager. The Manager - Emergency Response may designatethe Supervisor - Emergency Preparedness or other personnel to assist him in meeting thisresponsibility.




3.0 ORGANIZATIONAL PREPAREDNESS

3.1 Training - Corporate and Plant Personnel

3.1.1 Personnel with unescorted access to PBNP:

a. Personnel with unescorted access will be indoctrinated on the EmergencyPlan (EP) and Emergency Plan Implementing Procedures (EPIP) throughthe general employee training program. This training program hasprovisions for immediate indoctrination of new employees. Thereafter, allpersonnel with unescorted access meet this commitment during annualplant access qualification renewal.

b. Personnel with unescorted access shall receive, as a minimum, instructionsin the following-topics:

1. Emergency alarms and their meanings

2. Emergency assembly areas

3. Precautions and limitations during emergencies

4. Reasons for emergency plans

5. Worker responsibilities during emergencies

3.1.2 Personnel assigned to the PBNP Emergency Response Organization (ERO)

a. Plant and corporate personnel assigned specific duties associated with theEmergency Plan will receive initial and annual continuing training specificto the response role they are assigned, under the direction of theTraining Manager.

b. The objectives of initial and continuing training are to:

1. Prepare the ERO in the areas of emergency plan organization,facility organization, accident classification, emergency dataanalysis and problem solving.

2. Keep personnel in the ERO informed of substantivechanges in the Emergency Plan procedures.

3. Maintain a high degree of preparedness at all levelsof the emergency response organization.




c. The emergency response training program provides for annual continuingtraining using a systematic approach on portions of the Emergency Planand Emergency Plan Implementing Procedures which affect the trainee'srole in the Emergency Response Organization. Specific continuingtraining requirements include:

1. The Shift Superintendent, Operations Coordinator, and ShiftTechnical Advisor will receive specialized training in accidentassessment. The following are general topics that will be includedin this annual training:

(a) Accident assessment and classification

(b) Dose projections

(c) Protective action recommendations

(d) Notification of offsite agencies

2. Radiological Field Monitoring Teams (Chemistry and RadiationProtection) will receive training in the actions they will be expectedto perform during an emergency. The following general topics willbe included in the training:

(a) Personnel monitoring (reentry and medical assistance)

(b) Emergency exposure criteria

(c) Locations and use of radiological emergency equipment

(d) Post-accident sampling

3. Training of individuals-assigned to repair and damage control teams(reentry teams) will be conducted annually.

d. Individuals assigned to search and rescue teams shall maintainqualifications to meet the requirements of the supporting agency providingfirst aid and CPR training.

3.1.3 The conduct of all emergency response training will be critiqued anddocumented on appropriate Training forms.

3.1.4 Emergency Preparedness Staff

The Company will assure the Emergency Preparedness Staff maintainsfamiliarity with state-of-the-art emergency preparedness equipment andprocedures by attending seminars, workshops, and training as appropriate.




3.2 Training - Offsite

The Company will annually provide a training opportunity for offsite organizations andagencies as specified in respective agreements and understandings. In addition, thoseoffsite organizations and agencies that may provide onsite emergency assistance will beencouraged to become familiar with the general layout of PBNP facilities as it relates totheir responsibilities, and will be invited to attend appropriate Emergency Plan trainingand orientation courses conducted by or for the Company. The Company will providetraining for specific offsite organizations and agencies as follows:

3.2.1 The Company will ensure a training opportunity is provided annually forhospital personnel, ambulance/rescue personnel, police, and fire departments.The training shall include the procedures for notification, basic radiationprotection, and the organization's expected role.

3.2.2 The Company will provide training media on an annual basis for the generalpopulation in the EPZ.

This training program will include the following:

a. Educational material concerning radiation.

b. Identification of a contact point for further information.

c. Protective actions which can be taken for any radiological emergency.These actions would range from simple sheltering and respiratoryprotection to the more complex and serious steps such as evacuation.

3.2.3 Local news media personnel will be provided an opportunity to become morefamiliar with information pertaining to radiological emergency planning,nuclear power generation, Point Beach Nuclear Plant, radiation, and points ofcontact for release of public information in an emergency. Because PBNPand Kewaunee Nuclear Power Plant (KNPP) are served by a common mediacorps, the companies will provide information jointly each year.




3.3 Drills and Exercises

PBNP conducts a biennial exercise and additional periodic drills. A drill in this context isa supervised instruction period aimed at testing, developing, and maintaining skills in aparticular operation. It is often a component of an exercise which is an event that teststhe integrated capability and a major portion of the basic elements existing withinemergency preparedness plans and organizations.

Each drill or exercise is conducted to ensure that the participants are familiar with theirduties and responsibilities, to verify the adequacy of and methods used in EPIPs andother emergency procedures, to check the availability of emergency supplies andequipment, and to verify the operability of emergency equipment.

The Supervisor - Emergency Preparedness is responsible for planning, scheduling, andcoordinating all Emergency Plan drills and exercises. All Emergency Plan drills andexercises are subject to the approval of the Plant Manager. The Plant Manager willassign personnel to correct any deficiencies identified during the conduct of drills orexercises.

When a major drill or exercise is required, the Supervisor - Emergency Preparedness will:

3.3.1 Develop and prepare a scenario. This scenario shall include, but not belimited to, the basic objective(s) of the drill or exercise; the date(s), timeperiod, place(s) and participating organizations; the simulated events; atimeline of real and simulated initiating events; a narrative summarydescribing the conduct of the drill or exercise; and arrangements for qualifiedcontrollers.

3.3.2 Coordinate efforts with other appropriate emergency organizationsand agencies.

3.3.3 Schedule a date to conduct the drill or exercise arid assign qualifiedcontrollers.

3.3.4 Obtain the approval of the Plant Manager if the drill or exercise involves morethan one plant group.

3.3.5 Critique the results of the drill or exercise.

3.3.6 Retain critique results for review prior to future drills or exercise and guidancein developing Emergency Plan, EPIPs, or PIMs as appropriate.




3.4 Exercises

PBNP conducts an emergency response exercise to demonstrate the effectiveness of theEmergency Plan on a frequency determined by the NRC. Exercises may includemobilization of state and local personnel and resources, and are intended to verify theircapability to respond to an accident. Joint exercises shall be conducted on a frequencydescribed in NRC/FEMA guidance. PBNP will invite qualified observers from federal,state, and local governments to observe and critique the exercises. A critique shall beconducted following the exercise to evaluate the ability of organizations to respond asrequired in the Emergency Plan. The critique will be conducted as soon as practicableafter the exercise.

The scenarios for drills and exercises will be varied such that all major elements of theemergency response plans and preparedness organizations are tested within a six yearperiod.

3.5 Drills

Drills are conducted which involve appropriate offsite and on-site emergencyorganizations. These drills are conducted by simulating actual emergency conditions.Drills are evaluated by an assigned monitor. Drills that will be conducted and theirfrequency include:

3.5.1 Communications Drills

Communications with federal, state, and local governments within the plumeexposure pathway EPZ are tested monthly. Communications between PBNPand the NRC Operations Center are tested at least once each month from theControl Room, the TSC and the EOF. Communications between PBNP, state,and local emergency operations centers, and field monitoring teams are testedannually.

3.5.2 Fire Drills

Fire drills are conducted in accordance with the PBNP Fire ProtectionManual. The Fire Protection and Safety Coordinator will coordinate all firedrills with offsite agencies as necessary.

3.5.3 Medical Emergency Drills

A medical emergency drill involving a simulated contaminated individual andcontaining provisions for participation by the Two Rivers CommunityHospital are conducted every two years. The offsite portions of this drill maybe performed as part of the annual exercise. Since the Kewaunee NuclearPower Plant will also be conducting drills with the hospital on a biennialbasis, the hospital and a local ambulance service will participate in drillsannually.




3.5.4 Radiological Monitoring and Radiation Protection Drills

Plant environs, radiological monitoring, and radiation protection drills, bothonsite and offsite are conducted twice each year. These drills evaluate theresponse to, and analysis of, simulated airborne and direct radiationmeasurements in the environment.

3.5.5 Chemistry Drills

In-plant post-accident liquid sampling drills shall be conducted annually oneach unit. Containment atmosphere sampling drills will be conducted eachfuel cycle of each unit.

3.5.6 Site Assembly, Accountability, Release, and Evacuation Drills

A site assembly drill is conducted annually to assure that all personnel areaware of assembly areas. Accountability is implemented to ensure allpersonnel have been accounted for onsite. A release or evacuation ofnonessential personnel may also be conducted as a part of the drill.

3.5.7 Shift Augmentation Drills

Shift augmentation drills will be conducted annually.

4.0 REVIEW AND UPDATING OF THE PLAN, PROCEDURES AND LETTERS OFAGREEMENT

The Emergency Plan is reviewed on at least an annual basis and updated as necessary. The PlantManager is responsible for coordinating these efforts. The Plant Manager is also responsible forcoordinating the review and updating of the EPIPs. This includes a quarterly review ofemergency telephone lists.

The Manager - Nuclear Assessment is responsible with the Supervisor - EmergencyPreparedness for arranging with the Quality Assurance Section for an annual review of theEmergency Preparedness Program. The Emergency Plan and the Appendices to the EmergencyPlan are controlled reference documents which are reviewed and approved appropriately.Distribution of the Emergency Plan and supporting procedures will be in accordance withNuclear Power administrative procedures.

Letters of agreement between PBNP and outside organizations and agencies will be reviewedannually and renewed as needed.




5.0 EMERGENCY EQUIPMENT AND SUPPLIES

The Manager - Radiation Protection has overall responsibilities for the inventory and inspectionof designated emergency equipment and supplies exclusive of fire protection equipment. TheFire Protection and Safety Coordinator has overall responsibilities for the fire protectionequipment. He may, however, assign personnel to assist him with this responsibility.

Designated non-fire emergency equipment and supplies and their location are referenced inAppendix H of the Emergency Plan. This equipment is inventoried, inspected, and calibrated ata frequency in accordance with the Emergency Plan Maintenance Procedures (EPMP).Inventories are completed at least once each calendar quarter and after each use. Inspection,calibration and maintenance are accomplished at a frequency recommended by the manufacturerof the equipment. Portable radiation monitoring equipment included in these inventories iscalibrated in accordance with approved procedures. Reserve instruments/equipment will replacethose which are removed from emergency kits for calibration or repair in accordance with theguidelines of the EPMPs. Equipment, supplies, and parts having finite shelf lives will bechecked and replaced as necessary. Any deficiencies found will either be cleared immediately ordocumented for corrective action.



November 30, 1999RECOVERY

1.0 DISCUSSION

Outlined in EP 5.0 are those preplanned actions to be taken in the event that an emergencysituation arises. After execution of these preplanned actions, there will be need for further plantactions. Depending on the nature of the particular situation, recovery procedures shall bedeveloped for restoring operations and property as nearly as possible to a safe status. The lesscomplex operations, such as an Unusual Event or Alert, require only brief recovery actionprocedures. However, for the Site and General Emergencies, correspondingly complex recoveryaction procedures may be required. Although it is not practicable to plan detailed recoveryactions for all conceivable situations, the following general guidelines will assist in determiningthe specific actions to be taken:

1.1 All recovery actions will be preplanned. This means that each specific action will bethought out in advance and discussed with responsible and knowledgeable personnel. Ifconditions permit, it is preferred that there be a written log of all actions to be taken andby whom.

1.2 Affected areas will be roped off and posted with warning signs indicating radiation levelsand permissible entry times based on survey results. Shielding will be employed to theextent practical. Access to such areas will be controlled, and exposures to personnelentering such areas will be documented.

1.3 Every reasonable effort should be made to limit radiation exposure of personnel involvedin the recovery situation to levels as low as reasonably achievable. Exposures should notexceed 10 CFR 20 limits.

1.4 The TSC Manager is responsible for evaluating the advisability and timing of authorizingpersonnel to reenter affected area(s). An RWP (or equivalent) will be used to controlaccess during recovery operations. Survey results and all other pertinent information willbe collected from logs and other records or indicators in the Control Room, TechnicalSupport Center, and/or in the Emergency Operations Facility. Individuals with directknowledge of recent conditions in the affected area(s) will be interviewed.

1.5 The TSC Manager is responsible for designating an Incident Investigation Team. The Hteam is responsible for gathering all available evidence on contributory factors andreviewing the recovery operations to ensure that all causal factors have been specificallyidentified and all abnormal conditions corrected or neutralized. In addition, this teamwill review recommendations from the Emergency Director where a release ofradioactive material has occurred and consult with those offsite authorities withregulatory or compliance responsibilities.

1.6 Recovery operations may be terminated when all appropriate actions have beencompleted, and the PBNP Recovery Organization, under the direction of the EmergencyDirector, and NRC agree that the plant can be maintained within TechnicalSpecifications.




RECOVERY

2.0 RECOVERY ORGANIZATION

In those cases where post-accident conditions indicate that recovery operations will be eithercomplicated or will extend over a relatively long period of time, the plant operations will shiftfrom the emergency response organization to a long-term recovery organization. The recoveryorganizational structure may be the same as the emergency response organization with additionalmodifications depending upon the nature of the accident, post-accident conditions (i.e., plantconditions, radiation/contamination levels, etc.), and other factors to be determined at that time.The advantage for adopting this transitional approach is for continuity (i.e., managers anddirectors know the problem areas) and lack of confusion among plant personnel and federal, stateand local support agencies.

Prior to initiating a long-term recovery organization, specific recovery operational proceduresshall be defined. A typical long-term recovery organization may be designed as follows:

W.E.Executive

Spokesperson

| EOF l| Manager

OffsiteAfin :Interface IResources

ResourceCoordinator

Incident Investigation Team

In addition to the recovery organization, the TSC Manager shall establish an IncidentInvestigation Team.

The team, responsible for gathering evidence on contributory factors and reviewing recoveryoperations is an interdisciplinary team which reports to the TSC Manager. It will normallyconsist of representatives from Operations, Maintenance, Engineering, and Radiation Protection,as determined by the TSC Manager.



EMERGENCY RESPONSE ORGANIZATION PERSONNELFUNCTION AND RESPONSIBILITY

EP APPENDIX ARevision 19November 30, 1999

APPENDIX A INDEX


SECTION

1.0

2.0

3.0

4.0

5.0

6.0

7.0

8.0

9.0

10.0

11.0

12.0

13.0

14.0

15.0

16.0

17.0

18.0

TITLE PAGE

ADMINISTRATIVE SUPPORT LEADER .............................. 4

CHEMISTRY LEADER .............................. 5

CORPORATE COMMUNICATOR .............................. 5

COUNTY LIAISON .............................. 6

DOSE/PAR COORDINATOR .............................. 6

DOSE/PAR MONITOR .............................. 7

DUTY SHIFT SUPERINTENDENT ........................... 7

SHIFT TECHNICAL ADVISOR ......................... 8

ELECTRICAL LEADER ......................... 8

ELECTRICAL/I&C ENGINEER ......................... 9

EMERGENCY DIRECTOR ......................... 9

ENGINEERING COORDINATOR ........................ 10

ENS COMMUNICATOR ........................ 10

EOF MANAGER ........................ I1

EOF/CR COMMUNICATOR ........................ 12

FIELD TEAM LEADER ........................ 12

HPN/SRC COMMUNICATOR .................... 13

I&C LEADER .................... 13





APPENDIX A INDEX


SECTION

19.0

20.0

21.0

22.0

23.0

24.0

25.0

26.0

27.0

28.0

29.0

30.0

31.0

32.0

33.0

34.0

35.0

36.0

TITLE PAGE

JPIC MANAGER ........................................ . 13

JPIC COMMUNICATOR .. 14

MECHANICAL LEADER .. 14

MECHANICAL SYSTEM ENGINEER . .14

OFFSITE ASSEMBLY AREA COORDINATOR . . 15

OFFSITE RADIATION PROTECTION COORDINATOR . .15

OPERATIONS COORDINATOR . .16

OPERATIONS LEADER .. 16

OPERATIONS SUPPORT CENTER COORDINATOR . . 17

PLANT STATUS MONITOR .. 17

PROBABILISTIC RISK ASSESSMENT ENGINEER . . 18

RAD/CHEM COORDINATOR . .18

RAD/CHEM MONITOR .. 19

RADIATION PROTECTION LEADER .. 19

REACTOR/CORE PHYSICS ENGINEER .. 20

REENTRY TEAM COORDINATOR . .20

RESOURCE COORDINATOR . .21

SBCC SURVEY LEADER .. 21





APPENDIX A INDEX


SECTION

37.0

38.0

39.0

40.0

41.0

42.0

43.0

TITLE PAGE

SECURITY COORDINATOR ........................... 22

STATE LIAISON .22

STATE/COUNTY COMMUNICATOR .23

TSC MANAGER .23

TSC/CR COMMUNICATOR .24

TSC/EOF COMMUNICATOR .25

WE EXECUTIVE SPOKESPERSON .......................... 25


NUCLEAR POWER BUSINESS UNIT EP APPENDIX AEMERGENCY PLAN MANUAL Revision 19

November 30, 1999EMERGENCY RESPONSE ORGANIZATION PERSONNELFUNCTION AND RESPONSIBILITY

EMERGENCY RESPONSE ORGANIZATIONPERSONNEL FUNCTION AND RESPONSIBILITIES

Criteria which may be considered during the selection of personnel for emergency organization positionsinclude the qualification criteria required for normal operational job functions, the managerial andtechnical capabilities demonstrated in the performance of their normal administrative job functions, andcompletion of the appropriate emergency plan training. The qualification criteria for the operating plantstaff are listed in the NPBU Nuclear Organization Manual (NOM).

The Emergency Response Organization charts and reporting structure are located in EP 5.0.

1.0 ADMINISTRATIVE SUPPORT LEADER


1.1.1 Provide clerical and administrative support to responding ERO personnel atthe TSC and EOF.

1.1.2 Ensure each position has adequate office supplies, procedures, and operationalequipment to perform their duties

1.1.3 Coordinate records management, duplication and distribution of alldocuments, fax transmittals, word processing, event recording, and otheroffice support for the emergency response facilities.

1.2 Principal Working Relationships

Resource Coordinator, TSC Manager, EOF Manager




2.0 CHEMISTRY LEADER


2.1.1 Prepare, brief, and dispatch reentry teams on job scope, safety, and hazardousconditions.

2.1.2 Setup of the OSC Chemistry facilities and provide gamma spectroscopysupport at the OSRPF.

2.1.3 Analyze chemistry problems and secure necessary chemistry resources toassist emergency response and recovery operations.

2.1.4 Manages post-accident sampling of containment atmosphere and reactorcoolant system.

2.1.5 Assist with developing work scope packages, modifications, and analyses ofproblems.


Reentry Team Coordinator, Rad/Chem Coordinator, Reentry Teams

3.0 CORPORATE COMMUNICATOR


3.1.1 Establish and maintain communications with various Wisconsin Electriccorporate Qffices in the event of an emergency. (legal, risk management,medical)

3.1.2 Establish and maintain communications with various private and federaloffsite agencies in the event of an emergency. (PSCW, INPO, A&E, NSSS)

3.1.3 Ensure news releases are being posted to various WE corporate offices andINPO via websites, E-m.ail, or briefings.


Emergency Director, JPIC Technical Advisor, Resource Coordinator




4.0 COUNTY LIAISON


4.1.1 Respond to Couynty EOC personnel questions regarding forms transmitted,classifications, PARs, and nuclear terminology

4.1.2 Work in parallel with the counties and EOF to ensure that they are receivingaccurate and timely utility information.


Manitowoc and Kewaunee EOC Directors, State/County Communicator

5.0 DOSE/PAR COORDINATOR


5.1.1 Recommend offsite dose assessment, classification, and protective actionrecommendations.

5.1.2 Communicate periodically with the State Radiological Coordinator regardingoffsite conditions, dose projections, PARs, and status updates

5.1.3 Monitor facility radiological conditions and hazards.

5.1;4 Recommend when it is necessary to authorize dose in excess of the maximumPBNP yearly admin. level (4 rem), or in excess of the 10 CFR 20.1201limits (5 rem).

5.1.5 Review current or potential exposures and recommend when potassium iodideshould be distributed to emergency workers as a protection measure.


EOF Manager, OSRP Coordinator, HPN/SRC Communicator




6.0 DOSE/PAR MONITOR


6.1.1 Assist the Dose/PAR Coordinator with offsite dose assessment anddevelopment of Protective Action Recommendations (PARs).

6.1.2 Maintain communications with the Field Team Leader for current fieldmonitoring team data.

6.1.3 Periodically obtain current weather forecasts and update the status boards asnecessary.

6.1.4 Maintain the Rad/Met status board based upon changes in protective actions,classification, or significant changes in meteorology.


Dose/PAR Monitor, Field Team Leader, OSRP Coordinator

7.0 DUTY SHIFT SUPERINTENDENT


7.1.1 Coordinates the safe operation of the plant, including implementation ofnormal and emergency procedures to safely place and maintain the plant in asafe shutdown condition.

7.1.2 Direct the activities of the plant Operations personnel and shift supportpersonnel, coordinated with the OSC.

7.1.3 Operate the plant in compliance with all plant procedures, directives,Technical Specifications, and emergency procedures.

7.1.4 Provide information and recommendations on accident response.

7.1.5 Monitor plant parameters and plant conditions.

7.1.6 Onsite individual with unilateral authority to classify an event until relieved.




7.1.7 Interface with the emergency response organization in support of theemergency response operations.

7.1.8 Implement emergency response prior to relief by members of the emergencyorganization.


Emergency Director, TSC Manager, Operations Coordinator, EOF Manager

8.0 SHIFT TECHNICAL ADVISOR


8.1.1 Monitor critical safety functions in the Control Room.

8.1.2 Assist with initial communication requirements, if necessary.

8.1.3 Assist with classifications, if necessary.


Duty Shift Superintendent, Duty Operating Supervisor

9.0 ELECTRICAL LEADER



9.1.2 Analyze electrical problems and develop plans for monitoring and controllingplant problems.


Reentry Team Coordinator, Reentry Teams




10.0 ELECTRICAL/I&C ENGINEER


10.1.1 Continuously analyze problems with the operation of plant systems andequipment and develop plans or modifications to mitigate any concerns.

10.1.2 Provide engineering support including Severe Accident Managementresponse.


Engineering Coordinator

11.0 EMERGENCY DIRECTOR


11.1.1 Overall management and responsibility for the emergency response andrecovery operations for Wisconsin Electric, with the non-delegableresponsibilities of:

a. Classification/re-classification of emergencies

b. Protective Action Recommendations for offsite agencies

c. Notification of Federal, State, and County authorities

d. Request for federal assistance

e. Review & approval of news releases/updates technical content

f. Authorizing the use of potassium iodide .(KI)

g. Authorizing emergency radiation exposures in excess of 10 CFR 20 limits

11.1.2 Serve as a senior company contact for offsite governmental agencies at thesite. (NRC, FEMA, Wisconsin Emergency Management, local authorities)


Duty Shift Superintendent, TSC Manager, EOF Manager, JPIC Manager, WE ExecutiveSpokesperson




12.0 ENGINEERING COORDINATOR


12.1.1 Provide the administrative and technical control of any engineers.

12.1.2 Evaluate plant onsite power availability and preferred operating status forunaffected unit.

12.1.3 Direct, coordinate, and approve engineering, design and construction activitieson site.

12.1.4 Ensure that the engineering and design activity is adequately staffed andequipped to provide timely support.

12.1.5 Assists in the planning, scheduling, and expediting of recovery operations.

12.1.6 Provide SAMG Team direction.

12.1.7 Analyze problems with the operation of plant systems and equipment.


TSC Manager, Reactor/Core Physics Engineer, PRA Engineer, Mechanical SystemsEngineer, Electrical/I&C Engineer.

13.0 ENS COMMUNICATOR


13.1.1 Ensuring the NRC has adequate information.

13.1.2 Immediately informing the NRC of changes in emergency classification orprotective action recommendations (initial, upgrades, de-escalation,termination).

13.1.3 Providing plant and radiological status updates to the NRC.

13.1.4 Monitor the event for potential licensing concerns.


TSC Manager, NRC via ENS

-Page IO of 25 INFORMATION USE



14.0 EOF MANAGER


14.1.1 Command and control of the Emergency Operations Facility, including theOffsite Radiation Protection Facility and site access.

14.1.2 Ensure EOF has an adequate staffing level to respond to the event.

14.1.3 Maintain an information flow with the Control Room and TSC to establishpriorities and focus.

14.1.4 Monitor and recommend classification changes and Protective ActionRecommendations

14.1.5 Ensure initial and continuing communications are maintained with offsiteagencies.

14.1.6 Interface with responding representatives from offsite emergency agencies andassist in their information and communication needs.

14.1.7 Maintain accountability of personnel at the EOF and assess and provide forany considerations necessary for their safety.


Emergency Director, TSC Manager, Dose/PAR Coordinator




15.0 EOF/CR COMMUNICATOR


15.1.1 Maintaining a continuous communications flow between the TSC, EOF, andControl Room to monitor:

a. Event classification and Protective Action Recommendations

b. Plant and equipment status

c. Onsite radiological information

d. Procedures in use

e. Major activities and decisions within each facility

15.1.2 Monitor data points and trends which could result in an event classificationchange.


TSC Manager, TSC/CR Communicator, TSC/EOF Communicator

16.0 FIELD TEAM LEADER


16.1.1 Coordinate the offsite sample radiological survey activities of the fieldmonitoring teams.

16.1.2 Ensure continuing communications are maintained with the field monitoringteams; updating them on plant conditions, current meteorological data, andweather forecasts.


Offsite Radiation Protection Coordinator, Dose/PAR Monitor




17.0 HPN/SRC COMMUNICATOR


17.1.1 Ensuring the State of Wisconsin State Radiological Coordinator (SRC) andNRC Health Physics Network (HPN) have adequate information to assistthem in implementing offsite emergency plans.

17.1.2 Immediately informing the SRC and HPN of changes in emergencyclassification or changes in protective action recommendations.

17.1.3 Providing plant and radiological status updates to the SRC and HPN.


Dose/PAR Coordinator, State of Wisconsin SRC, NRC HPN

18.0 I&C LEADER



18.1.2 Analyze instrumentation and control problems and develop plans formonitoring and controlling plant problems.



19.0 JPIC MANAGER


19.1.1 Coordinates JPIC information with counterparts from local, state, and federalagencies.

19.1.2 Supervise all communications operations at the facility and coordinate thedistribution of all news releases and statements.

19.1.3 Arrange for interviews and preside at formal press conferences.


Emergency Director




20.0 JPIC COMMUNICATOR


20.1.1 Coordinate the data flow between the EOF and JPIC.

a. Immediately for changes in emergency classification or changes inprotective action recommendations.

b. Providing plant and radiological status updates.

20.1.2 Coordinate the Emergency Director's review of the technical content of newsreleases.


EOF Communicator at the JPIC, JPIC Manager, Emergency Director

21.0 MECHANICAL LEADER



21.1.2 Analyze mechanical problems and develop plans for monitoring andcontrolling plant problems.



22.0 MECHANICAL SYSTEM ENGINEER









23.0 OFFSITE ASSEMBLY AREA COORDINATOR


23.1.1 Control and organize the release of personnel assembled in onsite and offsiteassembly areas.

23.1.2 Assist with radiological monitoring of evacuees and vehicles, as appropriate.

23.1.3 Maintain accountability for all personnel located in the SBCC.

23.1.4 Assist with maintaining habitability, contamination control and ALARApractices.


TSC Manger, EOF Manager, Offsite Radiation Protection Coordinator

24.0 OFFSITE RADIATION PROTECTION COORDINATOR


24.1.1 Direct the activities of the OSRPF and Field Monitoring Teams (FMTs) insupport of the EOF.

24.1.2 Dispatch and control of FMTs:

a. Obtaining direct radiation, particulate, gas, and iodine samples.

b. Obtaining field environmental samples of air, water, and vegetation;

24.1.3 Implement monitoring, decontamination, and safety plans forpersonnel/vehicles evacuated from the site.

24.1.4 Coordinate and monitor facility habitability.


Dose/PAR Coordinator, Field Team Leader, SBCC Survey Lead, Rad/Chem Coordinator,Offsite Assembly Area Coordinator




25.0 OPERATIONS COORDINATOR


25.1.1 Assist the TSC Manager in setting priorities of TSC activities in support of theControl Room.

25.1.2 Continuously monitor event classifications and provide recommendations tothe TSC Manager.

25.1.3 Ensure critical safety functions are being monitored and trended.

25.1.4 Coordinate the use of SAMGs in the Control Room and TSC with theEngineering Coordinator.

25.1.5 Analyze problems associated with the operations of plant systems andequipment.


Duty Shift Superintendent, TSC Manager, OSC Coordinator

26.0 OPERATIONS LEADER



26.1.2 Analyze operations problems and develop plans for monitoring andcontrolling plant problems.

26.1.3 Provide directions to individuals assigned to maintain reentry team radiocommunications and dispatched reentry team status.

26.1.4 Assist with development of work scope packages and modifications.






27.0 OPERATIONS SUPPORT CENTER COORDINATOR


27.1.1 Ensure the OSC priorities and reentry teams are in direct support of theControl Room and TSC

27.1.2 Direct dispatch of reentry teams as required for search and rescue, firefighting, emergency repairs and damage assessment.

27.1.3 Assess OSC effectiveness and support the Reentry Team Coordinator asnecessary.


Operations Coordinator, TSC Manager, Reentry Team Coordinator, Rad/ChemCoordinator

28.0 PLANT STATUS MONITOR


28.1.1 Serve as a resource for plant and local environment data for event monitoringat the TSC and EOF.

28.1.2 Maintain plant status board and fission product barrier status board.

28.1.3 Provide for the accumulation, retention, and retrieval of computer generatedplant and local environment data.

28.1.4 Question suspicious information, looking for independent/redundantinformation to substantiate questionable information.


EOF/CR Communicator, TSC/CR.Communicator




29.0 PROBABILISTIC RISK ASSESSMENT ENGINEER






30.0 RAD/CHEM COORDINATOR


30.1.1 Coordinate chemistry activities and functions to support collection of onsitechemical data and release information.

30.1.2 Assess onsite radiological conditions and implement protective actionrecommendations for onsite personnel, contractors, and Security officers.

30.1.3 Evaluate the need for post-accident sampling of reactor coolant system and/orcontainment atmosphere.

30.1.4 Evaluate the need to take an isokinetic stack sample.

30.1.5 Recommend when it is necessary to authorize dose in excess of the maximumPBNP yearly admin. level (4 rem), or in excess of the 10 CFR 20.1201 limits(5 rem).

30.1.6 Review current or potential exposures and recommend when potassium iodideshould be distributed to emergency workers as a protection measure.

30.1.7 Offsite dose assessments in support of the EOF, if necessary.

30.1.8 Assist with development of plant procedures to process and control liquid,gaseous, and solid wastes.


Rad/Chem Monitor, Chemistry Leader, Dose/PAR Coordinator, TSC Manager

Page I 8 of 25 INFORMATION USE



31.0 RAD/CHEM MONITOR


31.1.1 Assist the Rad/Chem Coordinator in assessment of onsite radiologicalconditions and communicating plant and facility habitability.

31.1.2 Maintain Systems/RMS status board in the TSC and provide assistance withthe plant maps in the OSC.


Rad/Chem Coordinator, Radiation Protection Leader

32.0 RADIATION PROTECTION LEADER


32.1.1 Prepare, brief, and dispatch reentry teams on job scope, safety, hazardousconditions, and radiological concerns.

32.1.2 Implement appropriate radiation protection support of all onsite activities.

32.1.3 Analyze radiation protection problems and develop plans for monitoring andcontrolling plant problems.

32.1.4 Manage radiological controls for post-accident sampling of containmentatmosphere and reactor coolant system.

32.1.5 Maintain habitability, contamination control and ALARA practices within theTSC/OSC.

32.1.6 Ensure plant maps in the OSC are maintained with current radiological dataand hazardous environments in the plant.


Reentry Team Coordinator, Rad/Chem Coordinator, Reentry Teams




33.0 REACTOR/CORE PHYSICS ENGINEER


33.1.1 Monitor core and reactor coolant parameters for indications of inadequate corecooling and significant changes or trends.


33.1.3 Assist in performing post-accident core damage assessment, if necessary.



34.0 REENTRY TEAM COORDINATOR


34.1.1 Responsible for the reentry teams and recovery operations in response to theemergency, under the direction of the OSC Coordinator.

34.1.2 Assume reentry dispatch and tracking responsibility for onsite teams ofemergency reentry, search and rescue, fire fighting, and non-PBNP personnelrepair efforts (including in the exclusion area).

34.1.3 Coordinate preparation, briefings, and dispatching of reentry teams on jobscope, safety, and plant conditions.

34.1.4 Coordinate the development of work scope packages, modifications, andanalysis of problems.

34.1.5 Continually assist debrief information from returning reentry teams forchanging plant conditions.


OSC Coordinator, Operations Leader, Radiation Protection Leader, Chemistry Leader,I&C Leader, Mechanical Leader, Electrical Leader




35.0 RESOURCE COORDINATOR


35.1.1 Support the emergency with onsite and offsite procurement needs, including:

a. Staffing levels for response and recovery.

b. Emergency equipment for emergency or recovery support.

c. Communications equipment.

d. Emergency facility supplies and equipment.

e. Vendor and Contract support.

35.1.2 Utilize Emergency Preparedness Letters of Agreements as needed.


EOF Manager, TSC Manager, Corporate Communicator

36.0 SBCC SURVEY LEADER


36.1.1 Ensure habitability of the SBCC by the issuance of dosimetry, monitoringcompliance with contamination control practices, and performing radiologicaland smear surveys.

36.1.2 Monitoring and decontamination of vehicles and personnel entering andleaving the exclusion area.


Offsite Radiation Protection Coordinator, Offsite Assembly Area Coordinator




37.0 SECURITY COORDINATOR


37.1.1 Ensure the safety of plant, visitors, contractor, and security personnel.

37.1.2 Direct the onsite Security personnel in maintaining the plant security programin support of the emergency situations and recovery operations.

37.1.3 Direct the coordination of personnel assembly, evacuation, accountability, andrestricting access to secured areas.

37.1.4 Coordinate security escorts of reentry teams as appropriate.

37.1.5 Coordinate onsite and offsite access to the plant as appropriate.


TSC Manager, EOF Manager, Offsite Assembly Area Coordinator

38.0 STATE LIAISON


38.1.1 Respond to State EOC personnel questions regarding forms transmitted,classifications, PARs, and nuclear terminology

38.1.2 Work in parallel with the state and EOF to ensure that they are receivingaccurate and timely utility information.


State of Wisconsin EOC Director and SRC, State/County Communicator, HPN/SRCCommunicator




39.0 STATE/COUNTY COMMUNICATOR


39.1.1 Ensuring the state and counties have adequate information to assist them inimplementing offsite emergency plans.

39.1.2 Immediately informing the state and counties of changes in emergencyclassification or changes in protective action recommendations.

39.1.3 Providing plant and radiological status updates to the state and counties.


TSC/CR Communicator, State and Counties EOC Directors

40.0 TSC MANAGER


40.1.1 Direct all onsite emergency response in support of the Control Room byassuming the responsibility of:

a. Assessment of plant conditions and recommendations of classifications

b. Onsite Protective Action Recommendations

c. Onsite radiological assessment

d. NRC (ENS) Communications

40.1.2 Implement onsite operating procedures and EPIP's in support of theemergency response.

40.1.3 Determination of when to release non-essential personnel.

40.1.4 Evaluate changes in plant critical safety function areas, fission product barrierstatus, and classification changes.

40.1.5 Resolve questions concerning plant licensing requirements with the NRC.


Emergency Director, EOF Manager, Duty Shift Superintendent, Operations Coordinator




41.0 TSC/CR COMMUNICATOR


41.1.1 Maintaining a continuous communications flow between the EOF, TSC, andControl Room to monitor:








EOF Manager, EOF/CR Communicator, TSC/EOF Communicator




42.0 TSC/EOF COMMUNICATOR


42.1.1 Maintaining a continuous communications flow between the Control Room,TSC, and to monitor:








Duty Shift Superintendent, EOF/CR Communicator, TSC/CR Communicator

43.0 WE EXECUTIVE SPOKESPERSON


43.1.1 Attend media briefings to address public concerns.

43.1.2 Liaison between the emergency response organization and other companydepartments impacted by the emergency or whose services are required tosupport the response.


Emergency Director, JPIC Director


NUCLEAR POWER BUSINESS UNIT EP APPENDIX CEMERGENCY PLAN MANUAL Revision 11

November 30, 1999MAPS

1.0 GENERAL

This procedure lists maps to show EPZ areas surrounding PBNP. The maps include travel routesand congregate care locations and facilities. In this procedure, population roses are also includedto show the population distribution with the EPZ areas surrounding PBNP.

2.0 MAPS and TABLES

2.1 Figure 1, "Map of PBNP and Immediate Surrounding Area"

2.2 Figure 2, "Map of General Location Area Surrounding PBNP"

2.3 Figure 3, "Map of Manitowoc County Congregate Center Locations and Travel Routes"

2.4 Figure 4, "Map of Kewaunee County Congregate Care Locations and Travel Routes"

2.5 Figure 5, "Population Rose showing the Population Distribution Within an Area of 0 to10-mile Radius"

2.6 Figure 6, "Population Rose showing the Population Distribution Within an Area of 5 to40-Mile Radius"

2.7 Figure 7, "Survey Identification Map"

2.8 Table 1, "Point Beach Emergency Sampling Sites"



EP APPENDIX CRevision 1 1November 30, 1999

MAPS

FIGURE 1

0

0

Tw-o CreesTown Hall



EP APPENDIX CRevision I INovember 30, 1999

MAPS ''

FIGURE 2

IGENaRAL LOCATION MAP

(With Population Confers Of 25000 Or More 0)

,|,,* ,%*'_Tn|nisA 4..

"'rge, Oa

P- ;;,; *~~~~.- .e w-S *,,_ -_;-

« ; - .i- ; _!, s- t, , :;T

* a_. .........: ... .........."..........a o:/. I



EP APPENDIX CRevision 1 1November 30, 1999

MAPS

FIGURE 3

The above is a simplified map of Manitowoc County showing travel routes withinand away from the 10 mile "risk" area surrounding the Point Beach NuclearPlant. County and state highways may be used to travel from the *risk' areato congregate care facilities in Manitowoc County. Reedsville. Valders, St. Nazianz,Kiel, Newton, and Cleveland.

Public and non-public schools as well as other educational institutions willbe utilized as congregate care facilities. They have adequate emergencyliving capability to accomoodate all of the risk area population.

The small inset map above indicates population of the areas that may besubject to evacuation.




FIGURE 4

KEWAUNEE COUNTY CONGREGATE CARE LOCATIONS, FACILITIES & TRAVEL ROUTES

Xco This is a simplified map of2 S Kewaunee County showing the

~A travel routes within and9 away from the 10 mile 'risk'

Ceck S _'area surrounding Point Beach2____ 2 lA Nuclear Plant. County and_3 State highways may be used

KCo trk K to travel from the "risk"eTrk co area to congregate care

T k /facilities in Algoma, Casco,Luxemburg and Dyckesville.

XiLUtW1 o trk The public and non-publicschools of Kewaunee Countywill be utilized as con-

gregate care facilities.

They have adequate emergency

co Trk Jliving capability tovaccomodate all of the "risk

Z area.!"X~CoTrk F A r&

ouS 29 <The map also designateslocations of communities

kz V where congregate care isX2_,2_ available. They are numbered

1 through 9 and theirlocations are shown on themap.

MANITOWOC CO.The small inset mapindicates population of

POINT BEAC the areas that may beNUCLEAR subject to evacuation.PLANT

CIVIL TOWNS

Total allocation of risk population (5,996)to communities is as follows:

Cko e

1 through 3 - Algoma 3353 _27504 and 5 - Casco 1554 A 12156 through 8 - Luxemburg 25389 - Dyckesville 325

Total 7770

990' 1041990

Total 5996



EP APPENDIX CRevision 11November 30, 1999

MAPS

FIGURE 5

ga _1~so =r*-,gA

ft LW wrU M I b IIii 4 - , - - - II 4.

± HIQ j T,:EbTEI

i m gK

i 4 -A)I [- 246- - _t . -m ___ -_ _ I &a

L -- �k_- _- r

;-CI A4l

. I . -wt _ ._ a

cwMW-1 Iran. n.,Ayllf -1. _ =

I. _ 1 4 N W ......V ---

V / fIL9 VlI I -PL0 bM-- = ___

iQ. IA IIt- I A,' Ia MG lob ml 'I .. 3 .. ,

_ . * t {_ '{. IS$ {+ ? l, .

-F

* 1.**.~ ;r.

I-I f



MAPS


FIGURE 6

a B

N n~W 8-IMI4

II

M\

V as .Is-.34."a'.14,

wmin

e'DO 4H

POPULATxoNj DATRIBON. 5-40 MILES




MAPS

FIGURE 7SURVEY IDENTIFICATION MAP

I!JMtmlE T~U =

Fuml.lJo -- 6 . . _ _

CDtot

_E____=Ll

I 7' I FRAK t0A I\A 1 XRTI II- -1 Ti 7 F/7,rIJTINK V)

4;I 8

AllISA1 A8IrJ~i

I I x a t 4

I

ild,

Ft- I,."I /.

r --- X==-

u-FiI4 J Al_ rs _ _

""~j -- J -

* p -- -

-? I .AGBSONItAir

* *-.ZB

* g'&A

ti rrlhe

-5 ashic

RIVERSj.-

I-, ~ - ~0 River




TABLE IPoint Beach Emergency Sampling Sites

Sector A

A-4 Jct. of Hwy. BB and Hwy. 42A-5 Jct. Nuclear Road (Kewaunee Co.) and Hwy. 42AL6 Jct. Sandy Bay Road and Cemetery RoadA-7 Jct. Cemetery Road and Highway GA-8A Jct. Old Settler Road and Hwy. 42A-8B Jct. Old Settler Road and Wood-Side RoadA-9A Jct. Wood-Side Road and Highway JA-9B Jct. CTH J and Highway 42A-1OA Jct. Town Line Road and Lakeshore RoadA-lOB Jct. Town Line Road and Milne RoadA-1OC Jct. Town Line Road and Highway 42A-1OD Jct. Town Line Road and Wood-Side Road

Sector H

H-2 Jct. Nuclear Rd. (Manitowoc Co.) and Lakeshore Rd.H-3 Jct. Lakeshore Road and Irish RoadH-4A Jct. CTH V (Highway 177) and Sandy Bay RoadH-4B End of Pine Road

Sector J

J-3 Jct. Irish Road and Meyer RoadJ-4a Jct. Meyer Road and CTH V (Highway -1 77)J4B Jct. CTH V (Highway. 177) and Lakeshore RoadJ-5 Jct. Ravine Drive and Elmwood RoadJ-6 Jct. Ravine Drive and Rawley RoadJ-7 The east end of E. Hillcrest RoadJ-8 Jct. Viceroy Road and Highway 0




Table ISector K

K-3 Jct. Twin Elder Road and Irish RoadK-4 Jet Highway 42 and CTH V (Highway 177)K-5A Jct. Highway 42 and Elmwood RoadK-5B Jct. Elmwood Road and Tannery RoadK-6A Jct. Rawley Road and Diviision RoadK-6B Jct. Tannery Road and Rawley RoadK-7 Jct. Hillcrest Road and Tannery RoadK-8A Jct. Tannery Road and Viceroy RoadK-8B Jct. Highway 147 and Maplewood RoadK-9A Jct. Highway 147 and CTH WK-9B Jct. CTH W and Sunset DriveK-10 Jct. Woodland Drive and Cottage Lane

Sector L

L-2 Jct. Nuclear Road (Manitowoc Co.) and Hwy. 42L-4A Jct. Irish Road and Tannery RoadL-4B Jct. Tannery Road and Highway VL-5 Jct. Highway V and Division DriveL-6 Jct. Division Drive and Elmwood RoadL-7A Jct. Corners Road and Saxonberg RoadL-7B Jct. Highway 147 and Sturm RoadL-8A Jct. East Hillcrest and Petrie RoadL-8B Jct. CTH B and Steiners RoadL-9A Jct. Barthels and East Shore RoadL-9B Jct. Crystal Spring Road, Manitou DriveL-1OA Jct. CTH B and Johnson DriveL-1OB Jct. CTH Q and Berringer RoadL-1OC Jct. CTH Q and Jung Lane

Sector M

M-3 Jct. Nuclear Rd. (Manitowoc Co.) and Tannery Rd.M-5A Jct. Saxonberg Road and Nuclear RoadM-5B Jct. Assman Road and Saxonberg RoadM-6 Jct. Assman Road and CTH BM-7 Jct. CTH B and Highway 147M-SA Jct. CTH V and Sams RoadM-8B Jct. Ridge Road and Fisherville RoadM-8C Jct. Highway 147 and Jamnbo Creek RoadM-9 Jct. Jambo Creek Road and FishervilleM-1OA Jct. Fisherville Road and Parkway RoadM-1OB Jct. Francis Creek Road and Lorenz RoadM-1OC Jct. Lorenz Road and Lorenz Lane




Table ISector N

N-2 Jct. Tapawingo Road and Highway 42N-3 Tapawingo Road and Tannery RoadN-4A Jct. Tapawingo Road and Saxonberg RoadN-4B Jct. Saxonberg Road and Gesser LaneN-6A Jct. Nuclear Road (Manitowoc Co.) and CTH BN-6B Jct. CTH B and Tapawingo RoadN-7A Jct. Rabitz Road and Holmes RoadN-7B Jct. Tapawingo Road and Rabitz RoadN-8A Jet. Jambo Creek Road and Twin Bridge RoadN-8B Jct. Twin Bridge Road and Rainbow RoadN-9A Jct. Twin Bridge Road and CTH QN-9B Jct. CTH Q and Factory RoadN-1OA Jct. Siehr Road and Harpt Lake RoadN-lOB Jct. Harpt Lake Rd. and East Tuma Lake Rd.N-1OC Jct. Harpt Lake Rd. and Hwy. 147

Sector P

P-2 Jet. Hwy. 42 and Johanen Rd.P-3 Jct. Two Creeks Road and Tannery RoadP4 Jct. Two Creeks Road and Middle RoadP-5 Jct. Saxonberg Road and Zander RoadP-6A Jct. Zander Road and Tisch Mills RoadP-6B Jct. Two Creeks Road and CTH BP-7A Jct. Horse Rd. and Zander Rd.P-7B Jct. CTH BB and CTH BP-8A Jct. Jambo Creek Rd. and Zander Rd.P-8B Jct. CTH AB and Collegiate Rd. (Kewaunee Co.)P-8C Jct. Collegiate Rd. (Kewaunee Co.) and Bolt Rd.P-9A Jct. CTH Q and Zander Rd.P-9B Jct. CTH BB and Hwy. QP-10 Jct. Knutson Rd. and Bolt Rd.




Table 1Sector Q

Q-2 Jct. Two Creeks Rd. and Hwy. 42Q-4A Jct. Zander Road and Tannery RoadQ-4B Jct. City CTH BB and Town Hall Rd.Q-5 Jct. City CTH BB and Norman Rd.Q-6 Jct. Norman Rd. and Nuclear Rd. (Kewaunee Co.)Q-7 Jct. Sandy Bay Rd. and St. Peters Rd.Q-7B Jct. St. Peters Rd. and Nuclear Rd. (Kewaunee Co.)Q-7C Jct. CTH AB and Nuclear Rd. (Kewaunee Co.)Q-8 Jct. Sandy Bay Rd. and Hwy. BQ-9A Jct. Rangeline Rd. and CTH G.Q-9B Jct. Old Settlers Rd. and Rangeline Rd.Q-9C Jct. CTH AB and Sleepy Hollow Rd.Q-1OA Jct. Old Settlers Rd. and Sleepy Hollow Rd.Q-IOB Jct. CTH KB and CTH AB

Sector R

R-2 Jct. Two Creeks and Lakeshore Rd.R-3A Jct. Lakeshore Rd. and Zander Rd.R-3B Jct. Nero Rd. and Schlies Rd.R-5 Jct. Nuclear Rd. and Wood-Side Rd.R-6A Jct. Wood-Side Rd. and Sandy Bay Rd.R-6B Jet. Sandy Bay Road and Town Hall Rd.R-7A Jct. Sandy Bay Rd. and Norman Rd.R-7B Jct. Norman Rd. and CTH GR-7C Jct. CTH G and Town Hall Rd.R-8 Jct. Town Hall Rd. and Old Settler Rd.R-9A Jct. Town Hall Rd. and CTH JR-9B Jct. St. Peters Rd. and Old Settler Rd.R-1OA Jct. Town Hall Rd. and Town Line Rd.R-1OB Jct. Town Line Rd. and St. Peters Rd.R-IOC Jct. St. Peters Rd. and CTH J


NUCLEAR POWER BUSINESS UNIT EP APPENDIX IEMERGENCY PLAN MANUAL Revision 14

November 30, 1999LIST OF EPIP CATEGORIES ANDCROSS-REFERENCES TO THE EMERGENCY PLAN

l 1.0 INITIAL ACTIONS, CLASSIFICATION, DOSE ASSESSMENT, AND OFFSITEPROTECTIVE ACTIONS

EP 2.0, Section 2.12, 2.21, 2.24, 2.30, 2.31, 2.32, 2.34 and 2.35EP 4.0, Section 1.0 and Table 4-1EP 5.0, Sections 2.0 and 3.0EP 6.0, Sections 2.0, 3.0, 5.0, 6.0 and Table 6-1

2.0 EMERGENCY RESPONSE ORGANIZATION AND OFFSITE NOTIFICATIONS

EP 5.0, Sections 2.0, 3.0, 4.0, 5.0, 6.0, 7.0 and Figure 5-6 and Figure 5-7EP 6.0, Sections 2.0, 5.1EP 7.0, Sections 2.1, 2.6, 3.0, 9.0, Figure 7-1 and Figure 7-2

3.0 EMERGENCY RESPONSE FACILITY ACTIVATION AND EVACUATION

EP 2.0, Sections 2.6, 2.14, 2.22, 2.26, 2.28, 2.40 and 2.41EP 4.0, Sections 1.2, 1.3 and 1.4EP 5.0, Section 3.2 and Figures 5-3, 5-4, 5-5 and 5-6EP 7.0, Sections 2.1, 2.2, 2.3, 2.4, 2.5, 2.6 and 2.7

4.0 EXPOSURE GUIDELINES AND RADIOIODINE BLOCKING

EP 6.0, Sections 6.1, 6.5 and Table 6-9EP 9.0, Section 1.3

5.0 ASSEMBLY AND ACCOUNTABILITY, RELEASE AND EVACUATION OF PERSONNEL

EP 4.0, Section 1.0EP 5.0, Section 3.2EP 6.0, Section 5.1.1, Table 6-2

6.0 RADIATION PROTECTION

EP 6.0, Sections 3.0, 4.0, 5.1.1, 5.1.2, 5.2, 5.3, 6.1, 6.2, 6.5 and Tables 6-1, 6-7 and 6-9EP 7.0, Sections 2.2, 4.0EP 8.0, Sections 3.0 and 5.0

7.0 CHEMISTRY RESPONSE

EP 6.0, Sections 3.0, 4.0, 5.1.2, Table 6-1EP 7.0, Sections 2.3, 2.4, 4.0EP 8.0, Section 3.0

PagelI of 2 INFORMATION USE

NUCLEAR POWER BUSINESS UNIT EP APPENDIX IEMERGENCY PLAN MANUAL Revision 14

November 30, 1999LIST OF EPIP CATEGORIES ANDCROSS-REFERENCES TO THE EMERGENCY PLAN

8.0 EMERGENCY REENTRY AND DAMAGE ASSESSMENT

EP 6.0, Section 4.0, 5.1.1.e, and Table 6-1EP 7.0, Section 2.4, 4.0, 5.0, 6.0 and 7.0EP 9.0

[9.0 MEDICAL EMERGENCIES

EP 5.0, Section 4.2EP 6.0, Sections 6.2, 6.3 and 6.4EP 7.0, Section 6.0

10.0 RECOVERY PLANNING

EP 6.0, Sections 4.0 and 5.3EP 9.0
