ML20064L900

Public Version of Emergency Plan Manual,Including Revisions to Procedures EP 2.0 Re Emergency Plan Definitions,Ep 4.0 Re Emergency Conditions & EP 6.0 Re Emergency Measures

ML20064L900
Person / Time
Site:	Point Beach
Issue date:	07/30/1982
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20064L885	List: ML20064L890 ML20064L900
References
PROC-820730-01, NUDOCS 8208260067
Download: ML20064L900 (209)

Text

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I WISPONSIN ELECTRIC POWER COMPANY POINT BEACH NbCLEAR PLANT f

EMERGENCY PLAN MANUAL l

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! TABLE OF CONTENTS 4

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i' Revision No. Date i . .

Int'roduction . . . . .'.

1.0 . . . . . . . . . . 19 07-30-82 2.0 Emergency Plan Defin'itions . t . . . . . . . . 19 07-30-82 3.0 Summary of Emergency Plan . . . . . . . . . 19 07-30-82 4.0 Emergency Conditions,. . . . . . . . . . . . 19 07-30-82 5.0 Organizational Cottrol of Emergencies . . . 19 07-30-82 6.0 Emergency Heasures . . . . . . . . . . . . . 19 07-30-82 7.0 Cmergency Facilities i Equipment . . . . . . 19 07-30-82 8.0 ' Maintain!ng Emergency Preparedness . . . . . 19 07-30-82 l 9.0 Recovery . . . .. . . . . . . . . . . . . 19 07-30-82 4 1 APPENDICES Appendix "A" - F.mergency Rerbonse Organization Personnel Fuictions & Responsi-bilities . . . . . . . . . . . . . 2 07-30-82

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) Appendix "B" - Dose Plots . . . . . . . . . . . .

Appendix "C" - Maps . . . .c. . . . . . . . . . .

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1 07-30-82 Appendi3 "D" - Letters of Agreement . . . . . . . . 1 07-30-82 Appendix'"E" - State of Wisconsin Peacetime Radio- ~

y logical Emergency Response Plan .

. Appendix "F" - Manitowoc County Nuclear Facility Incident Response Plan . . . . . .

' Appendix "G" .Kewaunee County Nuclear Facility Incident Response Plan . . . . . .

4 Appendix "H" , Typic'al'. Equipment Lists . . . . . . 2 07-30-82 Appendix "I" -' List of EPIP Categories & Crossrefer-j c' ences to the Emergency Plan . . . 1 07-30-82 Appendix "J" - Evacuation Time Estimates for the Area Surrounding PBNP . . . . . . 1 07-30-82 e

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LIST OF TABLES Table Title Section 4-1 Summary of Emergency Action Levels EP 4.0 4-2 Recommended Protective Actions to Reduce Whole Body & Thyroid Dose from Exposure to a Gaseous Plume EP 4.0 5-1 Correlation Between Normal & Emergency organization Titles EP 5.0 6-1 Assessment Actions EP 6.0 6-2 Evacuation Actions EP 6.0 6-3 Recommended Protective Actions EP 6.0

) 6-4 Representative Shielding Factors From Gamma j Cloud Source EP 6.0 6-5 Selected Shielding Factors for Airborne Radionuclides EP 6.0

, 6-6 Representative Shielding Factors for f Surface Deposited Radionuclides EP 6.0 l

l 6-7 Use of Protective Equipment & Supplies EP 6.0 6-8 Guidelines for Protection Against Ingestion of Contamination EP 6.0

! 6-9 Administrative Exposure Limits EP 6.0 i

7-1 Onsite Assessment Equipment & Facilities EP 7.0 7-2 Offsite Assessment Equipment & Facilities EP 7.0 l

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i LIST OF FIGURES Figure Title Section 5-1 Minimum Organization for Normal Operation EP 5.0 l

5-2 Organization Chart - PBNP EP 5.0 5-3 Emergency Organization - Unusual Event EP 5.0 5-4 Emergency Organization - Alert EP 5.0 l 5-5 Emergency Organization - Site Emergency EP 5.0 5-6 Emergency Organization - General Emergency EP 5.0 l

5-7 WE General Office Management & Support Organization EP 5.0 5-8 PBNP Emergency Organization EP 5.0 5-9 Plant Emergency Notification System EP 5.0 5-10 Offsite Emergency Notification EP 5.0 7-1 PBNP Emergency Response - Exclusion Area .

Communication Network EP 7.0 1

7-2 PBNP Emergency Response Offsite Communication l Network E.7 7.0 7-3 PBNP Siren System EP 7.0 l

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i EP 1.0 MAJOR

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INTRODUCTION 1.0 PURPOSE The purpose of the Emergency Plan is to describe an organization for managing i emergency situations, to classify emergencies according to severity, to define and assign responsibilities and authorities, to clearly outline an effective course of action and protective measures required to mitigate the consequences of an accident, and to safeguard the public and plant per-sonnel in the event of an accident at the Point Beach Nuclear Plant (PBNP).

Detailed Emergency Plan Implementing Procedures (EPIP's) required to imple-ment the Emergency Plan have been developed and are available for use at the plant site. These procedures take into account such items as radiation hazards, weather conditions, availability of technical and operating per-sonnel, communications links, and support agencies.

2.0 SCOPE & APPLICABILITY This Emergency Plan is applicable to the Point Beach Nuclear Plant operated by the Wisconsin Electric Power Company (WE) and located at 6610 Nuclear ,

O Road, Two Rivers, Wisconsin 54241. The Emergency Plan describes the consi-deration of advance planning elements and the provisions and implementing procedures developed for emergency situations. The EPIP's for this Plan consist of the plant procedures which are used by plant personnel in emer-gency situations. Other plant procedures that play a role in emergency situations include plant operating, radiological control, security, and administrative procedures. These procedures are compatible with the Plan and will be used to mitigate the consequences of any emergency.

The interrelationships among the various elements of onsite emergency response and the elements of offsite emergency response are described in this Emergency Plan along with the appropriate Federal, State, and local agencies participating in radiological emergencies, i

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_, Revision 19 07-30-82 1

EMERGENCY PLAN DEFINITIONS 1.0 KEY ABBREVIATIONS The following key and readily recognizable abbreviations are used through- 1 out this Plan:

DCS Duty & Call Superintendent DTA Duty Technical Advisor EAL Emergency Action Level EIC Energy Information Center ENC Emergency News Center ,

EPIP Emergency Plan Implementing Procedures i

ESC Emergency Support Center NES Nuclear Engineering Section OSC Operations Support Center PBNP Point Beach Nuclear Plant SBCC Site Boundary Control Center j l

TSC Technical Support Center l l '

WE Wisconsin Electric Power Company 2.0 DEFINITIONS This section provides definitions of terms that are applicable to the PBNP Emergency Plan.

2.1 Accident An unforeseen and/or unintentional event and its consequences that may result in an emergency.

2.2 Administrative & Logistics Manager x A designated officer or senior manager of WE who is responsible for providing administrative, logistic, communications, and ,

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k/s personnel support for the emergency response and recovery operations.

See Table 5-1 for normal organizational title and Appendix "A",

Section 3.0 for function and responsibilities.

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

2.4 Clean Area That area within the protected area excluding the controlled area.

2.5 Controlled Area (Controlled Zone)

The area within the protected area in which radioactive materials and radiation are present or could normally be expected to be present in sufficient quantities to require protective measures. This area typically includes the containments, facades, auxiliary building, the area surrounding these buildings and parts of the service building.

This area is controlled by administrative means.

2.6 Control Room The control room is operated under the direction of the Shift Super-visor. It is the primary place where conditions are monitored and corrective actions for both units are taken to mitigate any abnormal occurrence. It is the location where primary assessment and classi-fication of an accident begins. Its purpose is to monitor the condi-tions of both units and provide the main communications link between the plant and the TSC concerning analysis of reactor system problems, as well as long- and short-term guidance on corrective actions.

2.7 Corrective Actions Those emergency measures taken to improve or terminate an emergency situation at or near the source of the problem in order to prevent or mitigate any release of radioactive material or to reduce the magni-tude of the emergency situation, e.g., shutting down equipment, fire fighting, repair, and damage control.

2.8 Design, Construction & Planning Manager A designated manager who coordinates the activities of plant modifi-cations or other design and construction support required for the emergency response and recovery operations. He also has the requi-site authority to coordinate and expedite plans and schedules for the Site Manager. See Table 5-1 for normal organizational title and g'~s Appendix "A", Section 23.0 for function and responsibilities.

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EP 2.0 Page 3 O 2.9 Emergency The situation or condition which may result in damage to property or risk to tne health and safety of the general public or plant per-sonnel.

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

2.11 Emergency Action Levels (EAL's)

Radiological dose rates; specific concentrations of airborne, water-borne, or surface-deposited contamination of radioactive materials; or specific instrument indications (including their rates of change) that are normally used as thresholds for initiating such specific emergency actions as designating a particular class of emergency, initiating a notification procedure, or initiating a particular protective action.

/s 2.12 Emergency Clacsification System

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Q / A classification system that arranges accidents in order of increasing severity and outlines an effective course of action and protective measures to safeguard the public and plant personnel. For the pur-poses of this plan, four emergency classifications are defined. They are as follows, listed in order of increasing severity:

- Unusual Event

- Alert

- Site Emergency

- General Emergency 2.13 Emergency Director A designated corporate manager of the Company with the requisite authority to activate the WE emergency organization for PBNP and provide emergency plan management direction to the onsite emergency organization. See Table 5-1 for normal organizational title and Appendix "A", Section 1.0 for function and responsibilities.

2.14 Emergency News Center (ENC) (Two Rivers Community House) x This facility is under the direction of the Emergency News Center

_,) Director and functions as a single-point contact for disseminating information to the public during more severe emergencies.

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/3 m- 2.15 Emergency News Center Director A designated officer or senior manager of WE who is responsible for providing accurate and timely information to the public through the news media and coordinating news releases with Federal, State, and local public relations officials. See Table 5-1 for normal organi-zational title and Appendix "A", Section 4.0 for function and respon-sibilities.

2.16 Emergency Plan Implementing Procedures (EPIP's)

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

2.17 Emergency Planning Zone (EPZ)

Offsite area surrounding PBNP for which planning is conducted to ensure that prompt and effective actions can be taken to protect the public in the event of an accident. For the plume exposure pathway, the EPZ has a corresponding radius of approximately 10 miles; and for the ingestion exposure pathway, the EPZ has a corresponding radius of approximately 50 miles (see Appendix "C" and Appendix "J").

-s 2.18 Emergency Support Center (ESC) (Lower and center floors of the

( Energy Information Center)

This facility is operated by the Emergency Support Manager for eval-uating and controlling emergency situations that may affect the public. For example, radiological dose projections and verifications will be performed at the ESC and results will be provided to local, State, and Federal agencies as required for implementation of offsite emergency plans. The ESC also serves as the command center for direction of recovery operations.

2.19 Emergency Support Manager A designated senior manager of the Company who operates the ESC and serves as the official utility contact with State and local govern-ments. See Table 5-1 for normal organizational title and Appendix "A",

Section 2.0 for function and responsibilities.

2.20 Exclusion Area (Site)

The area within the site boundary surrounding PBNP in which the plant personnel have the authority to determine all activities including exclusion or removal of personnel and property from the area. At PBNP, the outer boundary of the exclusion area is coincident with the site boundary (see Appendix "C").

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] 2.21 Gatehouse (Secondary Alarm Station (SAS) or South Gatehouse)

The building at the southeast corner of the protected area manned by security force personnel and used for normal access to and egress from the plant buildings.

2.22 General Office (WE)

Wisconsin Electric Power Company (WE) corporate headquarters located at 231 West Michigan Street, Milwaukee, Wisconsin, 53201.

2.23 Ingestion Exposure Pathway The principal exposure from this pathway would be from ingestion of contaminated water or foods such as milk, livestock feed, or vege-tables. Depending on the magnitude and nature of the radiological emergency, the time of potential exposure may range in duration from hours to months.

2.24 Limited Plant Evacuation The orderly withdrawal of personnel from a room, plant area, or building in the protected area.

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2.25 Low Population Zone (LPZ)

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The area bnmediately surrounding the exclusion area which includes a residential population of which the total number and density are such that appropriate protective actions can be readily taken in the event of a serious radiological accident (see Appendix "C" and Appendix "J").

2.26 Offsite The area beyond the exclusion area of PBNP.

i l 2.27 Onsite All areas at PBNP within the exclusion area.

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

This facility is an asse.shly area for plant personnel to report for instructions from the Plant Operations Manager or his staff. Communi-cations are provided to the TSC.

2.29 Plant Evacuation The orderly withdrawal of all personnel from areas within the fenced

(% protected area, except personnel immediately involved in the emer-( ) gency organization.

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2.30 Plant Operations Manager A designated manager of the Company with the requisite authority, plant operating experience, and qualifications to direct plant oper-ations appropriately. See Table 5-1 for normal organizational title and Appendix "A", Section 6.0 for function and responsibilities.

2.31 Plume Exposure Pathway The principal exposures from this pathway are whole body external exposure to gamma radiation from the plume and from deposited material; and internal exposure from inhalation of radioactive gas from the passing radioactive plume. Depending on the nature of the meteoro-logical and radiological conditions, the time of potential exposure could range from hours to days.

2.32 Population-at-Risk Those persons for whom protective actions are being or would be taken.

2.33 Projected Dose t' s The estimated dose that would be received by individuals if no pro-( } tective actions were taken following a release of radioactive material.

J 2.34 Protected Area The area within the PBNP security fence. This is sometimes referred to as "onsite" by the utility industry. However in this Plan, "onsite" is a defined term.

2.35 Protective Actions Those measures taken in anticipation of or after an inadvertent release of radioactive material for the purpose of preventing or minimizing radiological exposures to persons that potentially could occur if the actions were not taken.

2.36 Protective Action Guides (PAG's)

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

2.37 RadCon/ Waste Manager A designated manager who has the requisite authority, nuclear exper-ience, and technical expertise to manage the radioactive waste and radiological controls aspects of the emergency response and recovery f-~s operations. See Table 5-1 for normal organizational title and l

( ) Appendix "A", Section 19.0 for function and responsibilities.

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k_s 2.38 Radiological Emergency A radiological emergency is defined as an accident that may result in some loss of control of radioactive materials or may involve a hazard or potential hazard to the health and safety of people, or to the safety of property or environment.

2.39 Recovery Operations Those operations taken after the emergency to restore the plant as nearly as possible to its preemergency condition.

2.40 Security Building (Extension Building)

The building inside the protected area containing the central alarm station and the Security Supervisor's office. Office areas unrelated to security are also in the building.

i 2.41 Site Boundary Control Center (SBCC) 1 This facility is located at the south exclusion area boundary access road, approximately one mile southwest of the plant. It serves as a clearing center for evacuated plant contractor personnel, public f

s visitors, and a center for offsite environmental monitoring by health

(' 3 physics personnel. It may also serve as a health physics control

, s/ point for individuals entering or leaving the site. The facility is equipped with emergency radiation monitoring and sampling equipment, health physics supplies, protective and all-weather clothing, and other miscellaneous supplies for use during an emergency situation.

2.42 Site Manager A designated officer or senior manager of the Company who has the requisite authority, management ability, and technical knowledge to manage the plant emergency response and recovery operations. See Table 5-1 for normal organizational title and Appendix "A",

Section 5.0 for function and responsibilities.

2.43 Technical Support Center (TSC) (El. 8' of TSC building)

This facility is within two minutes walking distance of the control room and operates under the direction of the Site Manager. The facility has the capability to supply and display technical infor-mation for use by technical and designated management personnel in support of reactor operations and control room functions during emergency and recovery operations.

2.44 Technical Support Manager A designated manager of the Company with the requisite authority,

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t nuclear experience, and technical expertise to manage the Technical Support Group in support of the plant emergency response and recovery

, operations. See Table 5-1 for normal organizational title and Appendix "A", Section 12.0 for function and responsibilities.

EP 3.0 MAJOR Revision 19 07-30-82

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SUMMARY

OF EMERGENC'l PLAN 1.0 GENERAL The Emergency Plan defines the actions and responsibilities of PBNP per-sonnel in the event of an emergency and delineates the support required from offsite groups during certain specific emergency situations. Emer-gency classifications graded by increasing severity are incorporated in the Emergency Plan. These classifications describe the degree of response by onsite and offsite personnel and agencies. The Emergency Plan is based on the following key objectives:

1.1 Identification & Evaluation Identification and evaluation of various types of emergencies which could potentially occur at the plant and which could affect members of the public or plant personnel and equipment.

1.2 Organization & Direction p

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( Organization and direction of plant personnel actions to limit the consequences of an incident.

1.3 Organization & Control Organization and control of onsite and offsite surveillance activi-ties to assess the extent and significance of any release of radioactive material.

1.4 Delineation of Protective Actions Delineation of protective actions and measures which are based upon and are generally consistent with the EAL's specified in NUREG-0654, Revision 1, Appendix 1, " Emergency Action Level Guidelines for Nuclear Power Plants." The protective actions and measures are intended to protect members of the public and/or plant personnel and equipment in the event of an accident, including measures for recovery of and reentry to the facility.

1.5 Notification of Offsite Authorities l

Notification of offsite authorities as required, and coordination of l

response activities with offsite support groups.

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EMERGENCY CONDITIONS 1.0 EMERGENCY CLASSIFICATION SYSTEM The Emergency Plan is based on potential situations ranging from incidents where effects on the plant status are negligible to highly unlikely major releases of radioactivity which could affect members of the offsite public.

Each classification incorporates a specific emergency organization alerting and mobilization procedure and a set of actions to be taken by emergency organization personnel. Each classification is given a designation to indicate immediate required response of plant personnel when an emergency is announced over the public address (Gai-tronics) system.

The following emergency classification system is based on NRC NUREG-0654, Revision 1, Appendix 1, " Emergency Action Lev *l Guidelines for Nuclear Power Plants," issued November, 1980. Within each classification is a description of immediate plant actions as well as recommended State and local government actions.

1.1 Unusual Event

, An Unusual Event is declared as required by the initiating conditions and EAL's given in Table 4-1.

This classification applies to an unusual plant condition which either has occurred or is impending. This plant condition could eventually lead to a potential degradation in overall safety. Inher-ently, however, this is a situation in which time is available to take precautionary and constructive steps to prevent a more serious event or to mitigate any consequences that may occur.

The Unusual Event status places the plant in a readiness condition where there is a possible cessation of routine activities and pos-sible need of shift personnel augmentation. No.significant release of radioactive material is expected and, therefore, offsite response to a radiological release is not necessary.

This Unusual Event status will be maintained until an escalation in t

emergency class is initiated or a termination of the event is made by I

informing offsite authorities with the completion of the necessary documentation as specified in the EEIP's.

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It should be noted that this classification is equivalent to "Notifi-cation of an Unusual Event" in NUREG-0654, Revision 1, Appendix 1.

1.2 Alert An Alert is declared as required by the initiating conditions and EAL's given in Table 4-1.

An Alert classification is declared when events are in progress or have occurred which involve an actual or potential degradation of the level of plant safety. Although the potential for limited releases of radioactivity in excess of Technical Specification limits may exist, the initial assessment leading to this classification indi-cates that it is unlikely that an offsite hazard will be created.

The initiation of an Alert will institute prompt initial and followup notification to offsite authorities. The plant emergency response will be augmented by the actuation of the TSC and on-shift resource augmentation. Other centers may be activated as required by the Site Manager.

Plant evacuation would not be necessary in an Alert although limited plant evacuation may be necessary. In an Alert, notification is provided on a prompt basis, and follow-up information is provided to Federal, State and local authorities. If releases are expected, actions set forth in Table 4-2 will be recommended.

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This Alert status will be maintained until a recommended escalation or reduction in emergency class occurs or the status is terminated by informing offsite authorities, which includes completion of the necessary documentation as specified in the EPIP's.

1.3 Site Emergency l

j A Site Emergency is declared as required by the initiating conditions and EAL's given in Table 4-1.

The Site Emergency classification is declared when events are in progress or have occurred which involve actual or impending major failures of plant functions. In these events, there is a potential

! for offsite releases which could have an impact on the public to the extent that protective actions are imminent. Therefore, if not already accomplished, the Site Manager will augment resources and

, personnel and initiate activation of the TSC, OSC, the ESC, the SBCC, and the ENC (optional).

Plant evacuation with or without offsite evacuation will be initiated if required. There may be a deployment of onsite and offsite radio-logical monitoring teams to assess radiation levels, with communica-tion systems to transmit information back to the SBCC, ESC and TSC.

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('~ There will be a provision for an Emergency Support Manager at the ESC

\s_,}/ to provide status updates to offsite authorities. These status briefings to offsite authorities, if applicable, will be composed of meteorological information and projected dose estimates based on both actual and projected long-term release (calculated on foreseeable unit conditions). The Emergency News Center Director will establish and maintain communications with the ESC to provide information to the news media on the status of the incident.

The initiation of a Site Emergency requires prompt notification to State and local authorities so that they may activate their emergency control centers and dispatch key emergency personnel, such as State and/or local monitoring teams, to assess offsite consequences. If there is a potential for airborne release via the plume exposure pathway which would cause offsite projected doses of the United States Environmental Protection Agency (USEPA) Protective Action Guide limit to be exceeded, it will be recommended that State and local authorities initiate public protection as set forth in Table 4-2.

This Site Emergency status will be maintained until a recommended escalation or reduction in emergency class occurs or the status is terminated by informing offsite authorities, which includes comple-tion of the necessary documentation as specified in the EPIP's.

[b  % 1.4 General Emergency A General Emergency is declared as required by the initiating condi-tions and EAL's given in Table 4-1.

The General Emergency classification indicates that events are in progress or have occurred which involve actual or imminent substan-tial core degradation / melting and a potential for loss of containment integrity.

There will be a prompt notification to the appropriate State and local offsite authorities of the General Emergency status. If the following items have not been initiated, they will be instituted during a General Emergency. Resources and personnel will be aug-mented by the activation of the TSC, OSC, ESC, SBCC, and the ENC.

Plant evacuation or limited plant evacuation will be initiated as required. The onsite and offsite radiological monitoring teams will be dispatched. The Emergency Support Manager at the ESC will provide status updates to appropriate offsite authorities. These status briefings to offsite authorities will be composed of plant status, release of radioactive materials status, meteorological information, radiological dos? projections, and affected EPZ areas. At the ENC the Emergency News Center Director will establish and maintain communi-cation with the ESC to provide information to the news media on the incident status.

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'} A General Emergency involves the potential or actual release of airborne radioactivity which is likely to result in offsite projected doses that would exceed the limit for the United States Environmental Protection Agency (USEPA) Protective Action Guides for plume exposure pathway. Therefore, recommendation to State and local authorities would be to activate full-scale emergency operations with the recom-mended protective actions as set forth in Table 4-2.

This General Emergency status will be maintained until a termination or recommended reduction in emergency class is made by informing offsite authorities, which includes completion of the necessary documentation as specified in the EPIP's.

2.0 SPECTRUM OF POSTULATED ACCIDENTS The accidents that could occur at all commercial nuclear power plants have been classified by the United States Nuclear Regulatory Commission (USNRC)

(Appendix E 10 CFR 50) according to their severity of consequences and probability of occurrence. These accidents applicable to a pressurized water reactor like PBNP are addressed in Table 4-1 from the viewpoint cf initiating events, alarm actuation, and/or associated readings.

The inclusion of Table 4-1 in the Emergency Plan in no way concedes that all the listed scenarios are likely or even possible. This table is to be

/ used by the plant operators as an emergency classification guide. Since

( [,, \ some accident scenarios can be very complex, it is recognized that, with

'\s,/ information available, knowledge and skill acquired, and years of operator training and experience, the swift classification of those accidents can be aided with a simplified table.

Specific emergency operating procedures are not written for all the in-cluded accidents. In order to deal with unlikely and complex scenarios, the EPIP's provide for sequenced actions ir.dicating clear direction to be followed by PBNP operators. Table 4-1 prevides guidance for EPIP response to varying accident situations and conditions. Table 4-1 should be used only if the reactor is critical or at hot. shutdown unless specified other-wise in this plan.

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• Notet - Duty in Call Superintendent g b .a - Duty Shift Supervisor T R )4-1 /

• FSAR - Final Safety Analysis Report MASP - Modified Amended PBNP Security Plan EMERGENCY CLASSIFICATION Emergency Category Initiating Condition Indication Used C r.ssi ficat ion

1. Safety System Functions Unplanned initiation of emergency core cooling A_ny n of the following first-out reactor trip Us. usual Event with injection to the primary system panel annunciation with indicator confir- 1-Hour (7) mation noted:

1. " Containment press hi",

lPI-945, PI-947, PI-949 (2/3 >5 psig)]

, 2. " Steam line loop A lo-lo press" lPI-468, PI-469, PI-482 (2/3 <530 psig))

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3. " Steam line loop B lo-lo press" lPI-478, PI-479, PI-483 (2/3 <530 psig)l

4. " Pressurizer lo press SI"

[PI-429, PI-430, PI-431 (2/3 <1735 psig))

5. Wide range pressure <1500 psig Loss of containment integrity requiring When shutdown commences as determined by DSS Unu ual Event shutdown by Technical Specifications and DCS 1-Hour (5)

Less of engineered safety feature requiring When shutdown commences as determined by DSS Unusual Event l shutdown by Technical Specifications and DCS 1-Hour (5)

Loss of fire protection system function When shutdown commences as determined by DSS Unusual Event requiring shutdown by Technical Specifi- . and DCS 1-Hour (5) ,

i cations (i.e., both fire pumps inoperable) and no backup fire suppression system i

2. Abnormal Primary Exceeding Technical Specification primary system When shutdown commences as determined by DSS Unusual Event Leak Rate leak rate (10 gpm) and DCS 1-Hour (5)

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Emergency Category Initiating Condition Indication Used Classification Leak rate >50 gpm All of the following: Alert f

1. " Volume control tank level hi-lo" lLI-141 and/or LI-Il2 <8%]

2. Decreasing pressurizer level

[LI-426,L1-427,LI-428)

3. " Charging pump speed hi"

4. Charging line flow (FI-128) >50 gpm more than letdown flow (FI-134)

Leak rate in excess of available pump All of the following: Site Emergency capacity including charging, high head SI and low head SI 1. " Volume control tank level hi-lo

[LI-141 and/or LI-ll2 (8%]

2. No pressurizer level indicated

[LI-426,LI-427,LI-428)

3. All available pumps running as indicated by

, the red light at the switch

4. Increasing core exit T/C temp as indicated by P-250 and confirmed on local readout.

3. Abnormal coolant unexpected decrease in subcooling margin Both of the following: Unusual Event Temperature / Pressure

1. Alarm on P-250, if operat,ie

2. Confirmation by manual calculation Pressure >2735 psig Pressure >2735 psig on PR-420 and NRC only

" Code, safety or POHV not closed" l-hour open line (2)

DNBR <l.30

4. Abnormal Primary / Exceeding Technical Specification primary-secondary When shutdown commences as determited by DSS Unusual Event Secondary Leak leak rate and DCS 1-Hour (5) i

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Emergency category Initiating condition Indication used Classification Gross failure of 1 SG tube (>400 gpe) & loss of All of the following first-out reactor panel Alert offsite power (FSAR 14.2.4) annunciation with confirmation indication:

1. " Pressurizer Lo Press SI,"

[t1-429, PI-430, PI-431 (2/3 (1735 psig)]

2. a . " Steam generator A level hi"

[LI-461, LI-462 LI-463 (2/3 >70%)] or

b. " Steam generator B level hi" (LI-471. LI-472, LI-473 (2/3 >70%)]

- 3. a. "4.16 kv bus undervoltage"

& 0 volts on 403 & A04 voltmeters.

b. XO4 to A03 ammeter on CO2 (0 amps)

c. XO4 to A04 ammeter on CO2 (0 amps)

4. SI flow >400 gpa indicated by FI-924 &

FI-925 and pump discharge pressure corresponding to flow.

Rapid failure of >10 SG tubes (4000 gpm) with All of the following first-out reactor panel Site Emergency or without offsite AC annunciation with confirming indication:

1. " Pressurizer lo press SI" (PI-429, PI-430, PI-431 (2/3 <1735 psig)]

2. a. " Steam generator A level hi"

[LI-461, LI-462, LI-463 (2/3 >70%)]

or

b. " Steam generator 8 level hi"

[LI-471 LI-472, LI-473 (2/3 >70%)]

3. SI flow >4,000 gpm indicated by FI-626, l FI-928, FI-924 & FI-925 l l

S. Core Fuel Damage Gross fuel damage in core indicated Both of the following: Unusual Event

1. Letdown line radiation monitor (R9)

(sample line R109) 100 x alarm setpoint.

2. Sustained offscale & chemical analysis shows fission product concentration increase by 100X.

_ - - _ . - _ _ _ _ - _ - - - _ _ - _ - - _ - - _ _ _ _ _ _ _ _ - _ - _ _ - - -- -. , _ .. . ._=

h T .

Tr.ble Pege 4 U Emergency Category Initiating Condition Indication used Classification Massive fuel damage 300 pCi/cc iodine-equivalent as determined by Alert by chemical analysis

1. Massive loss of fuel clad integrity Initiating Conditions Nos. 1, 2. 4 & 5 General Emergency

2. With simultaneous loss of primary system integrity exist and No. 3 is possible: 1-Hour open line (3)

3. With potential loss of containment integrity

1. 300 pCi/cc iodine-equivalent determined by

. chemical analysis

2. Primary system leak >1000 g m indicated by SI flow >1000 cpm (FI-924 & FI-925) and pimp discharge pressure corresponding to flow

3. Minimum containment pressure suppression equipment is not available (any of the following):

a. No fan cooler operating and <2 spray pumps.

b. No spray pump operating and <4 fan coolers

c. <2 fan coolers running with I spray pump

4. " Containment press hi" (PI-945, PI-947. PI-949 (2/3 >5 psig)]

5. "Costtainment spray" with 2/3 + 2/3 >25 psig lPI-945 PI-947, PI-949]

[PI-946, PI-948, PI-950]

6. Secondary Coolant Reduction in feedwater enthalpy incident 1. a . Decreasing feedwater temp indicated by Unusual Event Anomaly (FSAR 14.1.7) 70-418& & TO-438A on P-250 and

b. confirmed by local temperature indicator on outlet of No. 5 fee & ater heater.

2. Unexpected increasing power on encore nuclear instrumentation Steam line break with primary to secondary leak All_ of the following first-out reactor trip Alert rate in excess of 10 cpm (FSAR 14.2.5) panel annunciation with confirmation: 1-Hour open line (3)

1. Either

a. " Steam line loop A Lo-Lo press" (PI-468, PI-469, PI-482 (2/3 <530 psig)]

or

b. " Steam line loop B Lo-Lo press" lPI-478, PI-479, PI-483 (2/3 <530 psig))

A.

t

(" 's Table

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Emergency Category Initiating Condition Indication Used Classification

2. Confirmed primary-to-secondary leak rate of at least 10 gun.

3. Either:

a. " Steam line loop A isol channel alert" lF1-464, F1-465 (1/2 >3.9x10 5 lb/hr)l or

b. " Steam line loop B isol channel alert"

[FI-474, FI-475 (1/2 >3.9x10s Ib/hr)]

Secondary Coolant Transient initiated by loss of feedwater, followed g of the following: General Emergency Anomaly by loss of auxiliary fee &ater for >l hour 1-Hour open line (3)

(FS&R 14.1.!!) 1. Decreasing SG levels -

"A" SG lLI-461, LI-462, Li-463)

"B" SG [LI-471, LI-472, LI-473)

2. No auxiliary fee &ater flow -

[FI-4002, FI-4007. FI-4014]

[FI-4036,F1-4037)

7. Abnormal Effluent Radiological effluent Technical Specification limits Airborne effluents only Unusual Event exceeded but <10 times the limit (FS&R 14.2.3) 1-Hour (8)

Radiological effluent Technical Specification limits Liquid effluents only Unusual Event exceeded (FS&R 14.2.2) 1-Hour (8)

Radiological effluents >10 times Technical Airborne effluents only Alert Specification instantaneous limits. (An instan- 1-Hour (8) taneous rate which, if continued for >2 hours, would result in a dose of aDout I mR at the site boundary under average meteorological conditions.)

8. Major Electrical Sustained loss of offsite power >15 minutes All of the following: Unusual Event Failures (FSAR 14.1.2)

1. "4.16 kV bus undervoltage"

& O volts on 103 & 404 voltmeters.

2. XO4 to 103 ammeter on 002 (0 amps).

3. XO4 to 104 ammeter on CO2 (0 amps)

n h

( w Tabla Page 6

• Emergency Category Initiating Condition Indication Used Classification Sustained loss of onsite AC power capability Both of the following: Unusual Event

(>15 minutes) 1-Hour (5)

1. "4,16 kv bus undervoltage" &

O volts on A05 and A06 voltmeters

2. " Emergency Diesel Starting System Disabled" for both Diesels Loss of all vital onsite DC power >15 minutes Both of the following: Site Emergency

1. " Annunciator power failure" ora i

C01, CO2, 003, and C04

2. <100 volts on the voltmeters for all batteries Loss of offsite power and loss of all onsite AC , A of the following:

J Site Emergency power for >15 minutes

1. "4.16 kv bus undervoltage" 0 volts on A03, A04, A05, A06 & "Emerg Diesel starting system disabled" for both Diesels I 2. XO4 to A03 ammeter on CO2 (0 amps)

• 3. XO4 to A04 ammeter on CO2 (0 amps) l Loss of offsite and all onsite AC power with loss of Q of the following: General Emergency all auxiliary feedwater for >2 hours

1. Unit aus NW meter XO2 on CO2 (0 m)

2. Station aux MW meter XO4 on CO2 (O MW) 1

3. XO4 to A03 ammeter on CO2 (0 amps) ,

4. XO4 to A04 ammeter on CO2 (0 amps)

! 6. XO2 to A01 ammeter on CO2 (0 amps)

7. a. No auxiliary feedwater flow

[FI-4036, FI-4037]

b. Decreasing SG level -

"A" SG {LI-461, LI-462, LI-463l

! "B" SG lLI-471, LI-472, LI-473)

9. Control Room Evacuation Evacuation of control room >15 minutes & As required by DSS Site Emergency no control at remote shutdown station 1-Hour open line (3)

10. Fire Fire in vital area or on the controlled side of plant As reported by Fire Brigade Chief Unusual Event lasting >10 minutes after initial use of fire extinguishing equipment.

A '

h .

A ) Tabla Pay 7

• Emergency Category Initiating condition Indication used Classification Fire affecting 1 train of safety systems. As reported by Fire Brigade Chief Alert Fire affecting 2 trains of safety systems As reported by Fire Brigade Chief Site Emergency

11. Plant Shutdown Function Nonfunctional indications or alarms in the control Both of the following

Unusual Event room on primary system parameters requiring plant 1-Hour (5)

1. " Annunciator power failure" on C04.

2. Failed indication as determined by DSS.

Turbine mechanical failure with consequences 1. Annunciator " Turbine supervisory." L;nusual Event

2. Indication on TR-6019 of bearing vibration

>7 mils.

3. Bearing vibration alarm on back of C03.

4. Visual confirmation of turbine housing penetration by a blade or disc.

Significant loss of effluent monitoring capability &  !. Loss of LW16 (RE223) during a release Unusual Event meteorological instruments which impairs ability to or perform emergency assessment. Loss of effluent 2. Loss of R18 (RE218) during a release monitoring may/may not require plant shutdown. or

3. a. Loss of wind speed indication or wind direction indication and

b. Loss of R14 (RE214) and RMS 11 Channel 1 (RE315, RE317. RE319) or

c. Loss of R15 (RE215) and CR9 and RMS 11 Channel 5 (RE225, RE226) or

d. Loss of R21 (RE221) and RMS II channel 2 (RE325, RE327) or

e. Loss of GW112 (RE224) and RMS II Channel 6 Failure of reactor protection system to All of the following: Alert complete a trip which brings reactor subcritical 1-Hour open line (3) i 1. Unplanned first out annunciator on C04 with confirmation from associated indicator

2. Intermediate range detector output not decaying

3. >l RCC RPI indicates fully withdrawn

(~% O Tabla (O ).

(V f Page 8 b /

• Emergency category Initiating condition Indication used classification All alarms (annunciators) lost >l5 minutes while unit 1. " Annunciator power failure" on Col. CO2 & Alert is not in cold shutdown 1(2)CO3, 1(2)C04 Loss of functions needed for cold 4hutdown for >4 g of the following: Alert hours while at cold shutdown

1. Loss of service water Unit 1 = south & west header Unit 2 = north & west header

2. Loss of both trains of RHR

3. Loss of component cooling '

12. Abnormal Radiation a. Effluent monitors detect !*vels corresponding to Airborne effluents only Site Emergency Levels at Site any of the following:

(1) >50 mR/hr for \ hour (2) >250 mR/hr for % hour for the thyroid (3) >500 mR/hr whole body for 2 minutes (4) >2500 mR/hr to the thyroid for 2 minutes at the site boundary for adverse meteorology

b. Any of the above doses measured in the environs As reported to DSS by HP Supervisor

c. Any of the dose rates projected, based on plant parameters

a. Effluent monitors detect levels corresponding to Airborne effluents only General Emergency either:

(1) 1 R/hr whole body (2) 5 R/hr thyroid at the site boundary under actual meteorclogical conditions

b. Either of the above doses measured in environs As reported to DSS by HP Supervisor

c. Either of above dose rates projected based on other plant parameters

13. Fuel Handling Accident Major damage to irradiated fuel in containment Both of the following: Alert

1. As reported to DSS by core Loading Supvr.

2. Alarm on Victoreen on manipulator & alarm on R211

'* O.

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Table

% P&ge 9 %

• Emergency Category Initiating Condition Indication Used Classification 4 Fuel damage accident with release of radioactivity Both of the following: Alert to auxiliary building (FSAR 14.2.1) fuel handling & drumming area vent (R221) [

2. Alarm on Victoreen on spent fuel pit bridge.

i.

14. Serious or Fatal Injury Transportation of seriously or fatally injured Reported as judged by DSS Unusual Event individual from site to hospital (expect hospitalization for at least (Reference EPIP 11.1) 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)

15. Security Threat Security threat or attempted sabotage Per MASP Per MASP & Appendices

, or 1-Hour Red Phone only Ongoing security compromise (open Line) (4) 1

16. Hazards to Plant Unusual aircraft activity over facility Visual observation of Operations Superviscr or Unusual Event Operation security force Nei.r or onsite explosion or flammable or toxic gas As reported to DSS by plant personnel making Unusual Event release visual observation Missile impacts from any source on facility Visual observation by Operations Supervisor Alert Missile impact causing damage to two trains of

safety systems Visual observation by Operations Supervisor Site Emergency l

Aircraft crash in protected area (within the fence) visual observation by Operations Supervisor Alert i

I Known explosion damage to facility affecting plant Visual observation by Operations Supervisor Alert I operation. Toxic or flammable gases in facility environment excluding normal process gases 1

Toxic or flammable gases entering into vital areas Visual observation by Operations Supervisor Site Emergency (control room, auxiliary building, etc.) excluding normal process gases 1

i i

e _ ~ . . . . - - - - . . .

k U v Tabit

..ge o a

. t Emergency category Initiating condition Indication used Classification

17. Natural Events Any earthquake Activation of >2 accelerographs and verified by actual physical ground shaking or by con-tacting Dr. David Willis, University of Wisconsin, Milwaukee Seismic Center at 1-414/963-4602. Unusual Event Any tornado visible from site Verification by Operations Supervisor Unusual Event Low Lake Michigan water level With no (v pumps running, water level is 3.9' Unusual Event below 0' on surge chamber level & confirmed by measuring forebay level at 10.9' below pumphouse floor (7' level)

Earthquake greater than operating basis earthquake Earthquake with attendant structural damage of Alert contairment or spent fuel pit Any tornado striking the facility Visual observation by Operations Stpervisor Alert Seiche near design level >6" of water in .urbine hall Alert Winds in excess of design levels Wind speed indicated as >100 mph Alert Wind with damage Structural damage to containment Site Emergency Failure of protection for vital equipment at low M of the following: Site Emergency levels (i.e., caused by seiche > design levels)

1. >3' water in both EDG rooms.

2. >2' water in vital switchgear room.

3. >2' water in auxiliary feed pump room.

Unusual Event

18. Reactivity Transient Uncontrolled rod withdrawal (FSAR 14.1.1 & 14.1.2)

CVCS Malfunction (FSAR 14.1.5) Unusual Event Accidental Criticality NRC Only (3)

("\ (R .

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b) \

b/

Tab 1st PageIt-}

o Emergency Category Initiating Condition Indication Used Classification

19. Load Transient Loss of Electrical Load (FSAR 14.1.10) Unusual Event

20. Other Condition that warrants State and/or local official DCS & DSS concurrence Unusual Event awareness Condition that warrants establishment of technical DCS & DSS concurrence Alert support center & emergency support center -

Condition that warrants use of monitoring teams DCS & DSS concurrence Alert Personnel contamination Health Physicist & DCS concurrence NRC-only 1-hour (10)

Any unplanned reactor trip DCS & DSS concurrence NRC-only j 1-Hour (7) i Strike by employees or guard force DCS & DSS concurrence NRC-only 1-Hour (12)

Loss of red phone (ENS) DCS & DSS concurrence NRC-only 1-Hour (13)

Personnel or procedural error DCS & DSS concurrence NRC-only 1-Hour (6) 10 CFR 20.403 DCS & DSS concurrence NRC-only 1-Hour (11) 4 p w nammwe new hews e e * -- e. g e e fN$

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I TABLE 4-2 -

RECOMMENDED PROTECTIVE ACTIONS TO REDUCE WHOLE BODY & THYROID DOSE FROM EXPOSURE TO'A GASEOUS PLUME Projected Dose (Rem).to Individual in General Public Recommended Actions! -

Comments-i Whole body <1 No planned protective actions.2 Previously recommended or State may issue an advisory to seek protective actions may -

Thyroid <5 shelter and await further instructions. be reconsidered or terminated.

Monitor environmental radiation levels.

Whole body 1 to <5 Seek shelter as a minimum. If constraints exist, special or Consider evacuation. Evacuate unless - consideration should be given Thyroid 5 to <25 constraints make it impractical. for evacuation of children i

Monitor environmental radiation levels. and pregnant women.

Control access to the affected area.

Whole body 5 and above Conduct mandatory evacuation. Seeking shelter would be an or Monitor environmental radiation levels alternative if evacuation Thyroid 25 and above and adjust area for mandatory evacuation were not immediately possible.

based on these levels.

Control access to the affected area.

(1) These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take existing conditions into consideration.

(2) At the time of the incident, officials may implement low-impact protective actions in keeping with the principle of maintaining radiation exposure as low as reasonably achievable.

e 1

7 Q . =

y* i j 4

/

EP 5.0 s ) .

MAJOR

~ .I b Revision 19

/

W n 07-30-82

(,)

ORGANIZATIONAL CONTROL OF EMERGENCIES 1.0 DISCUSSION

, Using the normal' shift operating organization as a base, this section of the: Emergency Plan describes the emergency organization that is activated onsite and its augientation and extension offsite should offsite response become nec'essary. Authorities and responsibilities of key individuals and groups are delineated. The communications links established for notifying, alerting, and mobilizing emergency personnel are described.

2-. 0 NORMAL'PLANTIORGANIZATION*

If both units ars in a condition other than cold shutdown or refueling shutdown, each rperating shift normally consists of eight qualified indivi-duals. The Shift Supervisor, who holds a Senior Reactor Operator (SRO) license, is in direct! charge of all plant operations during his assigned shif t and is directly t;e'ponsible for the actions of his crew. Other shift personnel are: One,0perating Supervisor who holds a Senior Reactor Operator (SRO) or Reactor Operator (RO) license, two Control Operators who hold Reactor Cperator licenses, three Auxiliary Operators and one person (could

('N be an Auxiliary Operator) who holds a' Reactor Operator license. There is A] at least one qualified health physics individual on each shift. A DTA, with special training in off' normal events, will be available at all times

X within 10 minutes to assist the evaluation and assessment capabilities of the Shift Supervisor. This normal operations organization is shown in Figure 5-1. Figure 5-2 shows the normal PBNP organization. Individual r.esponsibilities for normal operations are defined in administrative proce-cures. The Operating Supervisor and Control Operators perform the immediate operator actions'as stipulated by written and approved procedures during off-normal or emergency conditions. They are responsible for verifying that automatic control acti~ons take place and for taking immediate operator action initiating a reactor trip when a reactor protection signal setpoint i

is exceeded or when they determine that the safety of the reactor, personnel, or the environment is in jeopardy.

In the - event of an accident which could evolve into an emergency classifi-estion,in sccordance with the appropriate EAL's or in the case that initict.ing conditions exist that result in one of the EAL's being met direct.ly, the Shift Supervisor has the responsibility and authority to take immediate action to mitigate the consequences of the emergency. He will consult with the DCS and assign the appropriate emergency classification i and initiate the necessary EPIP's. The DTA will report to the control room and assume an advisory role. If the event is classified to be an Unusual Event, the Shift Supervisor will return the plant to a safe status and terminate the event using the organization shown in Figure 5-3.

m

• The~ crew of eight with two Senior Reactor Operators and three Reactor Operators

[ (V) is the staffing goal PBNP is actively pursuing.

I h

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I EP 5.0 Page 2 If the Shift Supervisor, based on his judgement and in conjuction with the O DCS, determines that the incident has the potential of or is actually exceeding predetermined EAL's (see Table 4-1), which will result in an Alert or higher level emergency, the normal shift organization shall be shifted into an emergency mode of operation depending on the situation and classification.

The Shift Supervisor will direct the plant response to assess and control the emergency and initiate the required plant and offsite notifications in accordance with Figures 5-9 and 5-10. If for some reason the Shift Super-visor is incapacitated, the Operating Supervisor will assume the responsi-bility and authority of the Shift Supervisor (until properly relieved by a qualified individual) and coordinate the plant response including the initiation of necessary offsite notifications.

3.0 ONSITE EMERGENCY ORGANIZATION This section of the Emergency Plan describes the responsibilities of the onsite personnel during an event classified to be an Alert, Site Emergency, or General Emergency.

3.1 Direction & Coordination The Shift Supervisor will be in the control room and maintain respon-

, sibility for operation of plant equipment and controls during emergency

(~

conditions other than fires. His preliminary emergency classifi-cation assessment will be determined by the EAL's (Table 4-1). If

) the incident is classified as an Alert or higher level emergency, the appropriate emergency centers as shown in Figures 5-4 through 5-6 may be activated and the shift personnel may be augmented. The Shift Supervisor will assume the responsiblilty of the Plant Operations Manager and continue to assess the emergency until relieved of this responsibility by the Plant Operations Manager (DCS).

The Plant Operations Manager is initially responsible for all onsite activities and personnel. He will operate from the TSC and coordi-

[ nate all procedures involving the control room, TSC, onsite OSC (staging area), and security building. The Plant Operations Manager, upon assuming emergency assessment responsibility from the Shift i Supervisor will conduct a detailed evaluation of plant conditions and i

offsite dose potential. Based upon this evaluation, he will reclas-l sify the event if necessary.

3.2 Plant Staff Emergency Assignments The organizations for each emergency classification are shown in Figures 5-3 through 5-6. Table 5-1 correlates the emergency organi-zation titles with normal operational titles. Appendix "A" lists a general summary of the plant staff emergency assignments including titles, locations, basic functions, primary responsibilities, and in (x) v I

( ~

)

I EP 5.0 Page 3 some cases, working relationships. A brief description of the emer-

/ gency organizational situations is as follows:

D) 3.2.1 Unusual Event (Figure 5-3 and EP 4.0, Section 1.1)

This emergency organization consists of normal shift per-sonnel. Appropriate procedures assigned to the control room will be accomplished under the direction of the Shift Super-visor (Appendix "A", Section 7.0). Maintenance staff augnentation will take place on a case-by-case basis.

3.2.2 Alert (Figure 5-4 and EP 4.0, Section 1.2)

Upon activation of appropriate emergency centers, responsi-bility for assessment, evaluation and recovery will be removed from the Shift Supervisor. The Plant Operations Manager will assume responsibility for assessment and per-form a detailed evaluation of the plant condition. All onsite radiation surveys and monitoring will be conducted under the direction of the Chemistry / Health Physics Super-visor. He will ensure that properly trained personnel are onsite at all times and capable of implementing these proce-dures in his absence. The Maintenance Supervisor will assume maintenance and repair coordination and search and

/ rescue responsibilities. A backup DTA will advise the

(' , Technical Support Manager (Appendix "A", Section 12.0).

Supervisory personnel will coordinate any limited plant evacuation and ensure accountability of their personnel. If appropriate, the TSC will be activated in approximately 30 minutes and fully operational in one hour. The ESC may be activated during an alert. If such is the case, the Site Manager will actuate the ESC within one hour and will assume overall responsibility for the emergency response and recovery operations and orocedures of the plant emergency personnel until relieved by the Emergency Support Manager.

3.2.3 Site Emergency (Figure 5-5 and EP 4.0, Section 1.3)

Assessment of the event as a site emergency will require the actuation of the ENC to provide periodic press updates.

Offsite radiation surveys will be initiated as necessary from the SBCC under the coordination of the Health Physics Director (Appendix "A", Section 20.0). These surveys will be under the direction of the chemistry & Health Physics Supervisor until the ESC is fully operational. A group will be organized in the ESC under the direction of the RadCon/

Waste Manager (Appendix "A", Section 19.0) which will direct offsite surveys as well as perform offsite dose assessment procedures. The results of these surveys and assessment procedures will be communicated to the Site Manager and the Emergency Support Manager by the Rad / Con Waste Manager.

Assigned technical personnel from the PBNP organization will

[}

s_,/ report to the TSC to assist in the emergency response opera-tions.

f

. EP 5.0 Page 4 q These personnel will augment the TSC staff within one hour i of the beginning of an emergency. Additional personnel will provide logistic, administrative, and scheduling support.

These personnel, under the Administrative & Logistics Manager (Appendix "A", Section 3.0), will ensure 24-hour continuity of all resources.

3.2.4 General Emergency (Figure 5-6 and EP 4.0, Section 1.4)

The General Emergency category requires that the emergency response organization be established to obtain and provide extensive amounts of plant data and information. To ensure this, the ESC will activate a group under the Design, Con-struction & Planning Manager (Appendix "A", Section 23.0) to provide detailed coordination with offsite technical support.

This group will be activated under this emergency classifi-cation within two hours of the beginning of an emergency.

The organization for a Site Emergency is also established.

4.0 AUGMENTATION OF ONSITE EMERGENCY ORGANIZATION This section describes offsite supporting assistance available to the onsite staff emergency organization.

4.1 Headquarters Support

(

(O) The PBNP normal organization as shown in Figure 5-2 has available the technical and administrative support services of the WE general office management and support organization as shown in Figure 5-7.

This organization can and will respond, as necessary, to emergencies at PBNP. The Site Manager will inform the Assistant Vice President of those emergencies either requiring notification of, or reports to, offsite organizations and agencies as well as those situations where offsite assistance is needed. The Assistant Vice President will relay emergency information to the Executive Vice President for evaluation. If the situation warrants, the Executive Vice President will activate the WE emergency organization for PBNP (Figure 5-8).

The WE emergency organization for PBNP is responsible for offsite

emergency management activities and will provide to, or obtain assis-tance for, the onsite emergency organization as required. These l responsibilities include, but are not limited to

4.1.1 Providing Emergency Plan management direction to the plant emergency organization.

l 4.1.2 Providing liaison and communications with the Federal, State, and local government organizations. If requested, the Company will send representatives to the appropriate State and local emergency operations centers.

j l

L ,

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. EP 5.0 Page 5 g 4.1.3 Providing public relations coordination and making news (g-w ) releases.

4.1.4 Providing funds necessary to implement the PBNP Emergency Plan and the general office plan as applicable.

4.1.5 Providing security management direction and support.

4.1.6. Supporting the plant emergency organization in engineering and technical matters by obtaining the assistance of Bechtel Power Corporation, Westinghouse Electric Corporation, or other appropriate resources.

4.1.7 Coordinating the restoration and/or operation of all gener-ation, transmission, and distribution facilities.

4.1.8 Supply logistic support for emergency personnel (e.g.,

transportation, temporary quarters, food and water, sanitary facilities in the field, and special equipment and supplies procurement).

4.1.9 Directing reentry and/or recovery operations and post-accident planning.

4.1.10 Assigning post-accident investigation and review responsi-bilities.

U'~N 4.1.11 Providing general assistance for environmental monitoring.

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

The Corporate Medical Director is a fully-licensed physician employed by WE. The Medical Director is qualified in radiological health and is available for assistance in an emergency if required.

4.2 Local Services Support During the operation of PBNP, it may become necessary to request and util-ize assistance provided by local organizations and agencies. Since it is essential that support from these organizations and agencies be available, the following agreements and understandings have been made:

4.2.1 Two Creeks Volunteer Fire Department When requested, the Two Creeks Volunteer Fire Department will, as stated in Appendix "D", provide fire fighting assistance at PBNP.

4.2.2 Town of Two Creeks

()

s The Township of Two Creeks, as stated in Appendix "D", will make available to WE the Two Creeks Town Hall to be used as

I t

, EP 5.0 Page 6 s, required during an emergency at PBNP. The Two Creeks Town I Hall would also be used as an alternate offsite assembly area for plant and support personnel if the primary assembly areas become untenable during the course of an emergency situation.

4.2.3 Two Rivers Community Hospital The Two Rivers Community Hospital will provide medical assistance to PBNP personnel. The agreement, attached in Appendix "D", provides for the treatment of personnel who suffer injuries complicated by radioactive contamination or radiation. Individuals may be transferred to the University Hospital & Clinics in Madison, Wisconsin, should the treat-ment required extend beyond the capabilities of the Two Rivers Community Hospital. The Two Rivers Community Hospital will maintain the capability and facilities to provide decontamination, first aid, and emergency stabilization medical treatment to injured personnel from PBNP. These services and facilities are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.

4.2.4 City of Two Rivers The City of Two Rivers will make available the facilities of the Two Rivers Community House for use by WE during an emergency at PBNP. This facility will be used as the (i(N )

s primary location for the ENC. Details of this agreement are presented in Appendix "D". In addition, arrangements have l been made with the City of Two Rivers to provide ambulance service to assist in transporting injured persons from PBNP.

1 l

4.2.5 University of Wisconsin Hospital & Clinics As detailed in Appendix "D", the University of Wiscor. sin Hospital & Clinics will accept and provide treatment to personnel with injuries beyond the capabilities of the Two Rivers Community Hospital, even if complicated by radio-active contamination. The University of Wisconsin Hospital

& Clinics are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day for either treatment or consultation.

i l 4.2.6 Doctors Clinic, Ltd.

l l At least two licensed physicians of the Doctors Clinic, Ltd., Two Rivers, Wisconsin, will provide medical super-vision and care for employees of PBNP (see Appendix "D"),

who have medical conditions complicated by exposure to radi-ation. Both doctors have received training qualifying them to care for this type of patient.

OT

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f EP 5.0 Page 7 4.2.7 Manitowoc County Sheriff's Department b

b When alerted, the Manitowoc County Sheriff's Department will respond within 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 the PBNP exclusion area in the unlikely event that an emergency requires such assistance.

c. Provide assistance in security-related matters.

d. Implement protective actions as directed by the Division of Emergency Government.

Details of this agreement are presented in Appendix "D."

4.2.8 Wisconsin State Patrol The Wisconsin State Patrol, District No. 3, when requested, will:

a. Assist the Manitowoc County Sheriff's Department in blocking roads and controlling traffic, including estab-(O^ b.

lishing road blocks and detour routes.

Provide assistance in keeping members of the general public from entering the exclusion area,

c. Provide assistance in security matters.

d. Assist the Manitowoc County Sheriff's Department in the evacuation of the general public.

Details of this agreement are presented in Appendix "D." ,

4.2.9 Kewaunee Nuclear Power Plant The Kewaunee Nuclear Power Plant laboratory facility will provide assistance for radiological and chemical sample analysis for air, water and other needed samples during a radiological emergency at PBNP. Details of this agreement are presented in Appendix "D."

4.2.10 Kewaunee School District The Kewaunee School District, when requested, will make available the facilities of the Kewaunee High School for use l by WE during an emergency at PBNP. Details of this agreement O are presented in Appendix "D."

f

, EP 5.0 Page 8 Figure 5-10 describes the notification and coordination of

([)N these groups and agencies during emergencies.

5.0 COORDINATION WITH PARTICIPATING AGENCIES This section identifies the principal State agency (designated State authority) and other governmental agencies (local, State, and Federal) having planning and/or implementation responsibilities for emergencies in the Manitowoc County and Kewaunee County area of PBNP in the State of Wisconsin.

5.1 State & Local Agencies 5.1.1 Wisconsin Department of Administration, Division of Emergency Government (DEG)

The Administrator of the DEG, Department of Administration, has been designated by the Governor of the State of Wisconsin as the State officer to assume the primary responsibility and authority for radiological emergency response planning.

The DEG is to exercise principal supportive roles, in addition to other State agencies, whose involvement will be coordinated by the DEG. The DEG will brief the Governor as to the situation and actions taken by the Federal, State, and local agencies and activate the State emergency operating center

/(/N (EOC) in the Hill Farms State Office in Madison, if necessary.

\

5.1.2 Wisconsin Department of Health & Social Services, Division of Health (DOH)

The Division of Health (DOH), Department of Health & Social Services, under the Radiation Protection Act, WIS STATS 140.50 to 140.60, is responsible to prevent exposure to ionizing radiation in amounts which are detrimental to health according to nationally accepted standards. The Chief of Radiation Protection Section, Bureau of Environ-l mental Health of DOH, is the State Radiological Coordinator l (SRC) of the State Radiological Response Team for peacetime radiological emergencies. Team members are personnel of the Section as designated by the SRC, augmented by selected personnel from the DEG and other State agencies trained specifically for radiological incidents. They will do the following: Conduct an initial survey to determine direct radiation levels and/or the severity and extent of the contaminated area, including soil, food and crop samples by taking readings and samples for analysis and making food chain dose estimates; advise how decontamination of the area should be accomplished; and assist in checking the evacuees of an involved area as to contamination or exposure.

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. EP 5.0 Page 9

,s 5.1.3 Wisconsin Department of Transportation, Division of En-forcement & Inspection, State Patrol (SP)

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The Wisconsin State Patrol supports the Division of Highways and local law enforcement services directing vehicular and pedestrian movement out of and around the area of the inci-dent, controlling access into the area and providing security at the site. All of the SP field cars have standard civil preparedness radiation monitoring survey meters and all troopers have been trained in their use. Some troopers have been trained as Radiological Defense Officers. All troopers are trained in handling vehicular accidents involving hazar-dous materials. The SP academy also conducts courses available to local law enforcement officers for their training in these techniques. Besides mobile radios in all 500 Division of Enforcement & Inspection vehicles, the Office of Trans-portation Safety has a communication van which can serve as a forward command post at the site. Each district has a supply of walkie-talkies on a dedicated frequency that are available through emergency police services for local and State emergency communications at the site of an incident.

The SP is available for courier service, by motor vehicle, for taking the State Radiological Response Team to the site, and delivering samples to the State Laboratory of Hygiene for analysis if necessary to expedite the response.

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( 5.1.4 Wisconsin Department of Natural Resources, Division of Enforcement The Conservation Wardens of the Division of Enforcement, Department of Natural Resources, can support the local law enforcement services as does the SP. There are standard civil preparedness radiation monitoring survey meters distri-buted among the wardens. About 6 to 12 wardens in each district receive some training in survey instrument use.

The wardens have mobile radios in their cars on the SP frequency. The Department can provide courier service, by motor vehicles and plane, to take the State Radiological Response Team to the 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 DEG, for implementing the Emergency dighway Traffic Regulation Plan when, as a result of a radiological incident, a large area is cordoned off by the law enforcement services and vehicular traffic is directed to other roads.

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. EP 5.0 Page 10

-~s 5.1.6 Wisconsin Department of Agriculture

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The Department of Agriculture has standard civil prepared-ness radiation monitoring 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 sale of foods emitting harmful levels of radioactivity. The Department can advise the use, sale, or disposal of animal feeds containing harmful levels of radioactive contami-nation. The Department can gather samples of milk and crops to determine radionuclide and related stable element concen-trations, and can advise dairies as to the disposition of milk, farmers as to the feeding of their cows on stored feed, and growers as how to restore lar.d to productivity.

Arrangements can be made by the Department with respect to handling of animals exposed to radioactive contamination.

5.1.7 Wisconsin Department of Military Affairs Section 21.11 of the Wisconsin Statutes contains the authority for the Governor to order all or any part of the Wisconsin National Guard personnel and/or equipment into active State service for public emergencies, disturbances or disasters.

Because of the relatively short duration and immediate Cf' r~'g reaction time needed in a raciological incident, the National l

\ ,) Guard, under the Department of Military Affairs, will be involved in such incidents only if the size of the area l involved requires their support. The National Guard could provide additional traffic control, communications, emergency

, provisions of food, radiological monitoring and decontamination l services. The Army National Guard has helicopters stationed in Madison and West Bend. If so ordered by the Governor, these can provide aerial reconnaissance and surveillance, insertion of personnel and equipment, aerial evacuation, aerial supply, illumination, ccmmunications and command and control. The Air National Gaard has fixed wing aircraft at Madison and Milwaukee and, if so ordered by the Governor, could provide services similar to the helicopters with the exception of take-off and landing capabilities and providing illumination. Additional radiation monitoring equipment maintained and operated by the U.S. Army is available at armories throughout the State. Nearly every one of the 72 l

company-sized units has a two-to-five man team trained in chemical-radiological procedures.

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. EP 5.0 Page 11 5.1.8 Manitowoc & Kewaunee County Under the provisions of the Wisconsin Statutes 22.16 and the Manitowoc and Kewaunee County Emergency Government Ordi-nances, authorities of both Counties have the responsibility and authority to coordinate offsite emergency activities in the event of a radiological incident. Each County has prepared a County Nuclear Facility Incident Response Plan to carry out this responsibility which is applicable to emer-gencies at PBNP (see EP 10.6 and EP 10.7).

Upon notification of an emergency at PBNP which requires participation of local or County agencies, each County will activate its emergency organization. Each emergency organi-zation is under the direction of the County Board Chairman and is composed of representatives from various partici-pating agencies which include the County Sheriff, County Emergency Government Director, County Highway Commissioner, fire fighting organizations, and school administrators. The Manitowoc and Kewaunee County Emergency Organization will provide or assist the emergency response activities by the following:

a. Provide notification to County and support agencies and local area residents that an incident has occurred at (p PBNP, if necessary.

b. Provide liaison and communication capabilities, with the plant facility and appropriate Federal, State and local organizations.

c. Assist in providing release of accurate public infor-mation concerning the offsite consequences of the emergency through all available media. In addition, advise and instruct area residents on what protective actions should be taken.

1 i

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

general public.

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

5.1.9 Local Water Supply Utilities In the unlikely event that an accidental discharge of liquid l radioactive material occurs into Lake Michigan which exceeds prescribed limits, notification that the event has occurred will be made to the municipal water utilities of Two Rivers, Manitowoc and Green Bay as well as the State of Wisconsin,

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- EP 5.0 Page 12

(g Division of Emergency Government. These notifications will i'-' f be made as soon as possible but no later than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the initial start of the release.

5.2 Federal Government Should an emergency situation or accident occur at PBNP, notifi-cation, reports, or requests for assistance may be made by WE to various Federal agencies and organizations. Details for notifying and making reports to these agencies, as well as for requesting and obtaining assistance, are provided in the EPIP's. The following agencies may, as the situation warrants, require notification or reports, or provide assistance if required:

5.2.1 NRC Operations Headquarters, Bethesda, Maryland The NRC requires notification and reports as stated in EP 5.0, Section 6.0.

5.2.2 Nuclear Regulatory Commission (NRC)

Office of Inspection & Enforcement, Region III.

5.2.3 Department of Energy (DOE)

/'~Ng The DOE in Region 5 has agreed to provide radiological g ,,/ assistance upon request. This request can be made by either the Emergency Support Manager or the Wisconsin Division of Emergency Government. The Radiological Assistance Team will respond as directed by the Chicago Operations Office of DOE.

5.2.4 United States Coast Guard When requested, the United States Coast Guard, Sturgeon Bay and Two Rivers, Wisconsin will evacuate all craft on Lake l Michigan within a specified EPZ, control traffic into the zone, and instruct persons on the beaches within the zone to leave.

l Details of the above agreements are contained in Appendix "D."

6.0 NUCLEAR REGULATORY COMMISSION (NRC) NOTIFICATION & REPORTS The following section outlines the required notification and reporting procedures to the Nuclear Regulatory Commission (NRC). Notification to the NRC under this section should not necessarily mean the implementation of the Emergency Plan. The notification and reporting sequence is categorized into four distinct groups which are the following:

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. EP 5.0 Page 13 6.1 Notification of Significant Events (10 CFR 50.72)

\s / Telephone notification to the NRC Headquarters and NRC Region III shall be made as soon as possible, and in all cases within one hour for any of the following significant events and shall identify that event as follows:

6.1.1 Any event requiring initiation of the Emergency Plan or any section of that plan.

6.1.2. The exceeding of any Technical Specification safety limit (Table 4-1, Item 3).

6.1.3 Any event that results in PBNP not being in a controlled or expected condition while operating or shut down.

6.1.4 Any act that threatens the safety of PBNP or site personnel, or the security of special nuclear material, including instances of sabotage or attempted sabotage (Table 4-1, Item 15).

6.1.5 Any event requiring initiation of shutdown of PBNP in accor-dance with Technical Specification limiting conditions for operations (Table 4-1, Item 1).

y"'g 6.1.6 Personnel error or procedural inadequacy which, during i

\ '/ normal operations, anticipated operational occurrences, or accident conditions, prevents or could prevent, by itself, the fulfillment of the safety function of those structures, systems, and components important to safety that are needed to:

a. Shut down the reactor safely and maintain it in a safe shutdown condition (Table 4-1, Item 11).

b. Remove residual heat following reactor shutdown (Table 4-1, Item 11).

c. Limit the release of radioactive material to acceptable i levels or reduce the potential for such release.

(Table 4-1, Item 12) 6.1.7 Any unplanned or unanticipated event resulting in manual or automatic actuation of engineered safety features, including the reactor protection systems. (Actuation of engineered safety features, including the reactor protection system which result from and are part of the planned sequence l during surveillance testing are not included.) (Table 4-1, Items 1 & 20) v l

l

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T EP 5.0 Page 14 6.1.8 Any accidental, unplanned, or uncontrolled radioactive

,\

release. (Normal or expected releases from maintenance or s other operational activities are not included.) (Table 4-1, Item 12) 6.1.9 Any fatality or serious injury occurring on the site and requiring transport to an offsite medical facility for treatment or observation for an extended period of time (greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />). (Table 4-1, Item 14) 6.1.10 Any serious personnel radioactive contamination requiring extensive onsite decontamination or outside assistance.

(Table 4-1, Item 20) 6.1.11 Any event meeting the criteria of 10 CFR 20.403 (Sections 6.2.2, 6.2.3, & 6.2.4, below) for notification. For repor-ting purposes Sections 6.2.3 and 6.2.4 require 24-hour and 30-day notification, respectively. (Table 4-1, Item 20) 6.1.12 Strikes of operating employees or security guards, or honoring of picket lines by these employees. (Table 4-1, Item 21) ,

6.2 Immediate Notification (10 CFR 20.403a)

(-g (f Telephone and telegraph notification shall be made immediately

) (within one hour) to the NRC Headquarters and NRC Region III for any incident involving byproduct, source, or special nuclear material and which may have or threatens to cause:

6.2.1 Exposure of the whole body of any individual to 25 Rem or more of radiation; exposure of the skin of the whole body of any individual to 150 Rem or more of radiation; or exposure of the feet, ankles, hands, or forearms of any individual to 375 Rem of more of radiation.

6.2.2 The release of radioactive material in concentrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 5,000 times the limits specified for such materials in 10 CFR 20, Appendix B, Table II.

6.2.3 A loss of one working week or more of the operation of any facilities affected.

.i 6.2.4 Damage to property in excess of $200,000.

6.3 Twenty-Four Hour Notification (10 CFR 20.403c)

Telephone and telegraph notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Headquarters and NRC Region III for any incident involving licensed material and which may have caused or threatens to cause:

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. EP 5.0 Page 15 6.3.1 Exposure of the whole body of any individual to 5 Rem or

, more of radiation; exposure of the skin of the whole body of any individual to 30 Rem or more of radiation; or exposure of the feet, ankles, hands, or forearms to 75 Rem or more of radiation.

1 6.3.2 The release of radioactive material in concentrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 500 times the limits specified for such materials in 10 CFR 20, Appendix B, Table II.

! 6.3.3 A loss of one day or more of the operation of any facilities affected.

6.3.4 Damage to property in excess of $2,000.

6.4 Thirty-Day Notification (10 CFR 20.405)

Letter notification shall be made within 30 days to the Director, Office of Inspection & Enforcement, U.S. Nuclear Regulatory Commis-sion, Washington, D.C. 20555, with a copy to the Region III Office of Inspection & Enforcement, U.S. Nuclear Regulatory Commission for the following:

/ 6.4.1 Any incident for which notification is required in Immediate i

O Notification & Twenty-four Hour Notification.

6.4.2 Each exposure of an individual to radiation or radioactive material in excess of any applicable limit set forth in 10 CFR 20 or the facility license.

6.4.3 Levels of radiation or concentrations of radioactive material (not involving excessive exposure of any individual) in an unrestricted area in excess of 10 times any applicable limit set forth or the facility license.

( 6.5 Reports l

Each written report required by Sections 6.2, 6.3 and 6.4 shall contain the following:

6.5.1 The extent of exposure of persons to radiation or to radio-active materials.

6.5.2 The levels of radiation and concentrations of radioactive material involved.

6.5.3 The cause of the exposure levels or concentrations.

l 6.5.4 Corrective steps taken or planned to ensure against recur-rence.

O

• EP 5.0 Page 16 Any report filed with the NRC pursuant to this shall be prepared so (qb ') that names of individuals who have received exposure to radiation will be stated in a separate part of the report with each indivi-dual's social security number, date of birth, and an estimate of the individual's exposure.

7.0 METHODS OF NOTIFICATION 7.1 Notification of Offsite Agencies Notification of offsite agencies is included in the EPIP's. The off-site notification EPIP's provide for an established message authenti-cation scheme for each emergency classification, guidance on assuring and verifying that each agency is notified, and an incident report form for each emergency classification. The incident report form provides for message verification and information for the initial and follow-up messages. The initial messages contain information about the location of incident, name and title of caller, date/ time of incident, class of emergency, whether a release is taking place, potentially affected population and areas, and whether protective actions may be necessary. The follow-up messages contain the basic information from the initial message with the following additional information if it is known and appropriate: The type and form of any actual or projected radiological release; meteorological conditions; estimate of quantity of radioactive material released or being re-(p)

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leased; actual or projected dose rates at site boundary and at 2, 5, and 10 miles, including sector (s) affected; surface contamination predictions; emergency response actions in progress; recommended emergency actions, including protective measures; request for any needed onsite support by offsite organizations; and prognosis for worsening or termination of the emergency.

j The notification of offsite agencies will begin within 15 minutes of the classification of a Site Emergency or a General Emergency. For other classes, the notification will begin within one hour. Figure 5-10 describes the primary notification and coordination of offsite agencies during emergencies. Communications capabilities are discussed in EP 7.0 of this Emergency Plan.

7.2 Notification of the General Public The general public will be notified through normal methods including press releases and news conferences of the lesser emergency classifi-cation where protective actions are not required of the general public such as Unusual Event and Alert. In emergencies, which may require some protective actions to be taken by the general public such as some General Emergencies, notification will be accomplished by the Manitowoc County Sheriff's Department and the State of Wiscon-

[ sin, Division of Emergency Government. The primary method of notifying

' residents in the affected area would be by a siren system as described in EP 7.0, Section 9.0, and police and emergency vehicles driving in i

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. EP 5.0

Page 17  ;

l the area with " yelp" sirens on, mobile public address systems, and door-to-door personal contact. This notification procedure will j commence with the population within the area of greatest risk and i incorporating the balance of the population within the EPZ as  !

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TABLE 5-1 CORRELATION BETWEEN NORMAL & EMERGENCY ORGANIZATION TITLES Emergency Organization Normal Organization Alternate Title Title Title Emergency Director Executive Vice President Assistant Vice President Emergency Support Manager Assistant Vice President Manager - NES I

Emergency News Center Director Vice President, Communications Superintendent - Information Services Administrative & Logistics Manager Director, Purchasing Manager - Procurement Section Site Manager Manager - PBNP Designated Alternate or DCS Plant Operations Manager General Superintendent Superintendent - Operations or DCS Shift Supervisor Shift Supervisor Shift Supervisor shift Support Coordinator Nuclear Plant Engineer - Shift Supervisor Operations 1 Maintenance Supervisor Superintendent - Maintenance & Assistant to Superintendent -

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Table 5-1 Page 2 Emergency Organization Normal Organization Alternate Title Title Title Technical Support Manager Superintendent - Technical Superintendent - EQRS or DCS Services Data Processing Coordinator Nuclear Plant Engineer Nuclear Plant Engineer (Reactor Engineering) (Reactor Engineering)

Administrative Supervisor Supervisor - Administrative Supervisor - Staff Services Services System Analysis & Procedure Superintendent - Reactor Senior Project Engineer, NES Support Coordinator Engineering, NES Chemistry / Health Physics Superintendent - CHP Superintendent - System Engineering, Supervisor NES Instrumentation & Control Superintendent - I&C I&C Supervisor Supervisor Core Physics Coordinator Superintendent - Reactor Nuclear Plant Engineer Engineering (Reactor Engineering)

RadCon/ Waste Manager Superintendent - Regulatory Project Engineer - Radiological

. Affairs, NES Design, NES Radwaste/ Technical Support Superintendent - System Project Engineer - Mechanical Coordinator Engineering, NES System Engineering, NES Licensing Support Coordinator Project Engineer - NES Licensing Engineer, NES

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Table 5-1 Page 3 Emergency Organization Normal Organization Alternate Title Title Title Health Physics Director PBNP Health Physicist Senior Health Physics Supervisor Design, Construction & Planning Manager - NES Superintendent - Reactor Engineering Manager or System Engineering, NES Director, Quality Control Superintendent - QAD Utility Engineering Director Project Engineer, Mechanical System Engineering NOTES:

1. Duty & Call Superintendents (DCS), Technical Advisors (DTA), and other on-call supervision are not identified in this figure because the positions are filled not only by organization title but also by experience and other qualifications.

2. It is not intended to imply that either the personnel in the " normal organization" or the " alternate" are committed personnel to the extent that each position must be filled within one day. The personnel listed as filling the " emergency organization" are what one could expect in the long-term. Over the short-term the Assistant Vice President or Manager - Nuclear Operations can designate any qualified person to fill vacant positions.

3. It is not anticipated to have a person in the respective emergency centers for each " emergency organization" title 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.

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EP 6.0 MAJOR t Revision 19

) 07-30-82 EMERGENCY MEASURES 1.0 DISCUSSION Emergency measures begin with the identification and classificatior. of an emergency and the activation of the appropriate emergency organizaiion.

Emergencies are classified in four distinct classes. Definitions for each class, criteria for classifying emergency situations, and examples of emergencies falling in each class are described in EP 4.0. The initial corrective and protective actions are recommended. The details of these various emergency measures are contained in the plant's EPIP's. 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 varying degree and scope of emergency organization. The emer- i gency organizations for each class are depicted in Figure 5-3 through i Figure 5-6. These figures have been designed to show titles of emergency personnel and the places to which they report during each classification of emergency. The function and responsibilitics of these personnel are more (p

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s) fully described in EP 10.1.

The various emergency classifications can occur individually or in some order of progression over a period of time. The onsite emergency organi-zation will be activated when the emergency is announced on the public address (Gai-tronics) system. The public address announcement will include the location and the classification of the emergency. Initially, the emergency organization will consist of the normal operating shift plant personnel who are qualified as emergency team members. Additional emer-gency team members, plant staff personnel are readily available during normal working hours and on a call-in basis during other than normal working hours per Figure 5-9. Activation of offsite emergency organi-zations will be accomplished in accordance with the severity of the emergency class. EPIP's provide for predetermined message formats for notification of offsite agencies, in conjunction with an established message authentication scheme for each emergency classification. The overall offsite notification of supporting groups and agencies is shown in Figure 5-10.

3.0 ASSESSMENT ACTIONS 3.1 Responsibility for Assessment Effective coordination and direction of all elements of the emergency organization require continuing assessment throughout the duration of i .

l

EP 6.0 Page 2 O the emergency situation. The assessment of plant conditions, radi-ation levels, and offsite consequences is initially coordinated by the shift Supervisor and the Plant Operations Manager (DCS). The Shift Supervisor is in direct charge of all emergency operations until a DCS arrives at the plant. At this time, the DCS's emergency organization title becomes the Plant Operations Manager, and joint responsibility and decision-making by these two persons, (Plant operations Manager and Shift Supervisor) shall prevail.

The assessment of emergencies can usually be accomplished by the normal operating shif t under the direction of the Shif t Supervisor.

However, other members of the plant staff, including the use of the emergency organization as described in EP 5.0, Section 2.0, will be called upon as required. Technical services and support will be obtained from the combination of WE general office personnel, plant staff personnel, and outside support organizations as necessary and appropriate.

3.2 Types of Assessment Actions The different types of assessment actions are described in Table 6-1.

The details of the assessment function are incorporated in the EPIP's for each emergency classification. Continued assessment will be s performed as required, with updating of offsite response agencies.

(( In addition, the results may require additional notifications, emer-gency actions, or reclassification of the accident.

3.3 Methods of Assessment Accidents involving releases of radioactive materials to the environ-ment require special methods of assessment to ensure that responses are appropriate for the protection of the population-at-risk as well as plant personnel. The plant has an extensive system for monitoring radioactive materials released to the environment (e.g., liquid process, containment purge exhaust and auxiliary building ventilation exhaust, air ejector vent monitors). As a general requirement, the various process monitors are capable of initiating appropriate alarms or actuating control equipment to provide containment of radioactive materials if pre-established limits are reached. These systems will allow for monitoring releases of radioactivity during accident condi-tions. In any accident condition where releases are not monitored or able to be monitored, emergency procedures provide the basis for calculating theoretical worst case release rates corresponding to a design basis accident described in the PBNP, FFDSAR.

In addition, the site has a permanent meteorological installation so that wind speed and direction, as well as standard deviation of wind direction, are recorded continuously in the control room. In the event the above instrumentation is inaccessible or inoperative, such information can be obtained from Kewaunee Nuclear Power Plant, the O local Coast Guard Station, or the National Weather Service.

T EP 6.0 Page 3 i

The methodology and technique used to predict the offsite concentra-tion of radioactive noble gases and iodine are as follows:

On determination of any emergency or potential emergency condition anticipated to have significant offsite dose consequences, a pro-cedure is initiated to project doses. The Site Manager is responsible for ensuring that the appropriate EPIP's are performed. These concen-tration levels will be verified by offsite monitoring teams deployed with portable radiological and communications equipment. This infor-mation 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 serious consequences. Operator training is a vital factor in ensuring that corrective actions are taken in an expeditious manner. The instrumentation, control system monitors, and radiation monitoring system provide indications used by the operators to regulate systems necessary for the safe and proper operation of the plant.

These systems provide the operator with the information and controls needed to start up, operate at power, and shut down the plant. The systems also f 3 provide the means to cope with abnormal operating conditions should they

( occur. Control of systems and display of information from these various systems are centralized in the control room. This instrumentation provides a basis for initiation of corrective actions.

When necessary, the following additional corrective actions can be imple-mented during emergency situations:

4.1 Fire Fighting Detailed procedures for responding to fire situations are defined in the PBNP Fire Protection Manual. The Fire Protection Manual des-cribes detailed instructions on fire protection and fire fighting with the fire protection organization and individual responsibi-lities. If outside assistance is needed, the Two Creeks Fire Depart-ment would be called in to assist in extinguishing the fire.

4.2 Damage Control & Repair For minor emergencies, the plant personnel will normally be able to handle the cleanup, repair, and damage control. For major emergen-cies, the support of other Company personnel or specialized outside contractors may be required to assist in the damage control, cleanup, and repair operation. Emergency response operations will be handled with the assistance of agencies available for that purpose.

Exposure to personnel during corrective actions should be controlled l \ as stipulated in EP 6.0, Section 6.1.

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. I EP 6.0 )

Page 4 J w

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d 5.0 PROTECTIVE ACTIONS The EPIP used in classifying emergencies has predetermined EAL's that, when met or exceeded, will require protective actions to be taken. In addition, the Shift Supervisor and/or a DCS may initiate EPIP's as they determine necessary. EPIP's include assessment actions, corrective actions, and pro-tective actions as appropriate. Protective actions will ensure that personnel, both on and offsite, will be notified and actions initiated for their protection in the event radiation or airborne activity levels from a radio-logical emergency onsite may exceed predetermined values, or when other situations threaten personnel safety.

Protective actions taken within the exclusion area are the responsibility of the Site Manager and Shift Supervisor, while those taken offsite beyond the exclusion area fall under the jurisdiction of the State of Wisconsin Division of Emergency Government with the resources of the State Division of Health & Social Services, Radiation Protection Section and the Manitowoc and Kewaunee County Emergency Governments. Recommendations of protective actions to be taken offsite will be made only by the Emergency Support Manager.

5.1 Protective Actions, Evacuation, & Personnel Accountability g This subsection provides for the timely relocation of individuals to prevent or minimize exposure 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 radiological emergency has occurred, or may occur, which will result in concentrations of airborne activity or radiation levels that exceed normal limits for a specific area or areas and cannot be readily controlled. In addition, protective actions will be taken for onsite personnel in such situations as fires, meteorological danger, etc., where personnel safety is threatened.

b. Notification & Response Time i

The actuation of fire alarms, radiation alarms, plant evacuation alarm, telephone calls, and public address (Gai-tronics) announcements, as applicable, will alert onsite personnel to hazardous conditions and to actions they must take. Such actions may be to assemble in emergency teams, to report to assembly areas, to evacu-ate specific areas within the plant, or to evacuate the plant. Table 6-2 describes the assembly areas for y onsite personnel which could include plant personnel, contractor personnel, and visitors to protect them from direct radiation or airborne hazards according to evacu-ation classification. The means and time required to

c. . _ _ . . _ . , _ __ _ - . _ - - _ _

T i

EP 6.0 Page 5 T-s_ / notify the above personnel are delineated as follows:

Approximately two minutes are required in the control room to determine that an accident has occurred. In addition, it is conservatively estimated that eight minutes are required to determine local severity of the accident. Indications of importance for identification and assessment include pressurizer pressure, pressurizer level, containment pressure, and automatic initiation of safety injecticn. Therefore, the best estimate for initial notification of onsite personnel would be approxi-mately 10 minutes or greater, depending on instrumenta-tion response and assessment capability at the time of the incident. It is important to note that most credible accidents in a nuclear power plant develop slowly and

" defense-in-depth" concepts delay the release of signi-ficant amounts of radioactivity.

c. Security A Site Access Control The security program at PBNP is designed to deter, detect, and delay an intruder. The plant protected area is enclosed by a standard security fence. Plant per-sonnel reporting to the plant during an emergency will

. assemble at the OSC (staging area). Personnel required (s

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to enter the protected area pass through the gatehouse at the entrance of the security fence. Security personnel will control access, log incoming personnel, and provide assistance, as required or requested. In the event these areas are uninhabitable, security control will be performed at the SBCC.

Provisions to restrict access to areas of the site outside the fenced protected area will be accomplished i

under the direction of the Shift Lieutenant. The Shift Lieutenant will assign a security force to control access to the plant property by barricading and manning the site roads with appropriate placement of lights, chains, traffic cones, padlocks, and gates. Access l

control will be performed with the aid and cooperation of the Manitowoc County Sheriff's Department as well as assistance from the Wisconsin State Patrol and the i United States Coast Guard.

l Plant security procedures are referenced in the EPIP's for various emergency situations (see Appendix "I").

d. Evacuation & Relocation Evacuation at PBNP will depend on the nature of the l

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emergency and the extent of the area affected. The t, Shift Supervisor will initiate any plant evacuation and

F' i

EP 6.0 Page 6 s any limited plant evacuation. These evacuations will be made after careful consideration of the benefits and the risks involved. The details of the responsibilities and functions for plant personnel during an evacuation of the protected area are included in the EPIP's. In general, evacuations will be in accordance with the following guidelines:

(1) A limited plant evacuation will be considered when any of the following conditions exist:

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

(b) Unscheduled containment evacuation alarm.

(c) Unevaluated airborne radioactive concen-trations in excess of the MPC's specified in Appendix B to 10 CFR 20.

(d) Excessive radioactive surface contami-nation levels (HP personnel may require evacuation of rooms, areas, or the affected

, portions thereof).

i

)

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

The criteria for these radiation levels and alarms do not apply to anticipated 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 EPIP's, or as directed over the public address system. If evacuation is from areas within the controlled area, personnel will proceed to the HP station for account-ability and radiation monitoring.

(2) A plant evacuation will be considered when the conditions that require a limited plant evacu-ation are not confined to a building of the plant, or when general area radiation levels outside of the controlled area exceed prescribed limits. In addition, a plant evacuation could be initiated following a limited plant evacuation if ps a hazard continues to increase in severity or

() spreads to other areas or the Shift Supervisor 1

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a EP 6.0 Page 7 O deems it necessary to evacuate nonessential personnel from the plant. When a plant evacu-ation is ordered, personnel inside the protected area will proceed as follows:

(a) Visitors, the public on the beach and fishing pier, and contractor personnel will proceed to the SBCC where personnel accounting and monitoring for contami-nation will be accomplished.

(b) Duty shift operations personnel will report bnmediately to the control room and remain there until instructed otherwise.

(c) Essential personnel with assigned emer-gency duties shall proceed to the TSC or preassigned locations as previously directed.

(d) All other Company personnel with no assigned emergency duties shall proceed to the OSC assembly area located at El. 18.5' of the TSC building.

() Individuals who do not have an emergency assignment may be released at the onsite OSC after radiation monitoring and personnel accounting have been completed.

e. Personnel Accountability Personnel accountability is the responsibility of plant supervision with the coordination of the Security Super-visor. During an emergency situation which requires personnel in the plant to evacuate to the various support centers, the group supervisors are responsible for assuring that all personnel are accounted for and the results reported to the TSC. The security guard will furnish a list of all visitors and construction personnel to ensure complete accountability. If personnel are unaccounted for, teams will be dispatched to locate, and, if necessary, rescue the personnel. Personnel 1 accountability procedures will be included in the EPIP's (see Appendix "A").

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l EP 6.0 Page 8

f. Monitoring Evacuees All individuals within the protected area of the plant are required to have in their possession personnel monitoring devices capable of measuring the dose re-ceived from external sources of ionizing radiation.

These devices consist of thermoluminescent dosimeter (TLD) for permanent record and/or a pocket dosimeter for day-to-day indication of external radiation exposures.

A combination of checking dosimeters and questioning of evacuees will be used to determine if there were any significant external exposures involved in the emer-gency. For any known or suspected overexposures, the TLD's will be read as soon as possible, and further investigation will be conducted to determine the amount of exposure and the necessary action to be taken.

If normal contamination control is not possible, moni-toring for contamination and internal exposure at the SBCC and OSC will be accomplished by using portable in-strumentation and questioning. Any persons suspected or known to have ingested or inhaled radioactivity will be whole body counted as soon as conditions permit to s assess internal exposure.

~ 5.1.2 Offsite Area

a. Action Criteria Required protective actions for offsite areas are dis-cussed in the State and local plans. As mentioned, the plant shall classify the accident (EP 4.0, Section 1.0) and notify the Federal, State, and local authorities.

The State plan has adopted the U.S. Environmental Pro-tection Agency's Protective Action Guides for initiating actions to protect public health and safety. These are given in Table 4-2. The local communities and State agencies have detailed plans for activating their agen-cies and taking various protective actions and performing social services. Any recommendation of protective actions for people offsite will come only from the Emergency Support Manager.

The criteria for determining protective action strate-gies to be taken in areas beyond the plant exclusion area encompass a number of factors and considerations.

The determination of what emergency protective actions should be implemented in any given accident situation must be based on the actual plant conditions that exist or that are projected at the time of the accident, with

(( 'N,,) the consideration of weather conditions, local protec-tion factors for typical residential units, evacuation i

EP 6.0 Page 9 O times, release potential and projected or potential doses. Therefore, the effective means in utilizing and applying protective actions in the event of an accident is an important consideration to reduce radiation expo-sure to the general public.

There are various types of protective actions that can be taken which include the following:

a. Population sheltering

b. Evacuation

c. Controlling food, milk, and water distribution

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

e. Individual protective actions (e.g., respiratory protection equipment and protective clothing)

Table 6-3 lists protective actions that may be recom-mended for various accident phases and approximate time periods as a function of exposure pathways following an

/ f-~g initiation of an accident. This information should be (t

useful for appropriate State and local agencies in making value judgments that are necessary to plan actions in limiting the radiation exposure to the general public during an emergency at PBNP.

(1) Sheltering & Evacuation Protective actions such as sheltering and evacua-tion can provide protection for the public against exposure to gaseous radioactive fission products l released during an accident at PENP. Evacuation of the population in the plume exposure pathway

to minimize public exposure to a passing radio-active material could be potentially 100% effective.

However, the protective action of population sheltering may be more appropriate at the time of the accident with the consideration of such factors as weather conditions, wind direction, roadway conditions, duration and type of exposure, and projected or potential doses to the population.

, (2) Shieldinq Shielding estimates for several distinct building types have been made by using currently available shielding technology. Table 6-4 through Table 6-6

EP 6.0 Page 10 present these estimates and indicate the wide range of potential shielding factors afforded by normally inhabited structures, and that basements of both homes and large buildings offer very effective shielding against radiation. The shielding effectiveness of a structure is ex-pressed in terms of a shielding factor which is the ratio of the dose received inside the struc-ture to the dose that would be received outside the structure. The benefits of population sheltering can be maximized by recommending that windows and doors of homes be closed and sealed, and ventilation systems turned off to minimize the turnover rate of air within the building.

(3) Exposure Pathways If there was an atmospheric release of radioactive materials, doses to the public could occur by external radiation as the cloud passes, by exposure to external radiation from radionuclides deposited on the ground and other surfaces, or by internal exposure due to inhalation or ingestion of radio-nuclides. Levels in excess of accepted protective 7x s

) action guides would generally occur closer to the source so that the protective actions could be g recommended on a two-phased approach. The first phase would be to evacuate those individuals in these closer areas (i.e., within a 2-mile radius),

while the second phase could be a recommendation to take shelter and institute food, water, and milk control since the need for evacuation versus sheltering in the 2- to 10-mile area may not be evident. However, beyond 10 miles there is little apparent distinction between the effective-ness of evacuation and sheltering in terms of minimizing projected health effects.*

The protective actions discussed above are only a few of the alternate courses of action which could be taken in a radiological emergency.

• 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, Alburquerque, New Mexico, and Rasmussen, N. C. , Depart-ment of Nuclear Engineering, M. I. T., Cambridge, Massachusetts, as presented at the American Nuclear Society Topical Meeting on Probabilistic Analysis of Nuclear Reactor Safety, May 8-10, 1978.

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EP 6.0 Page 11 C'N s- b. Company Responsibilities During an Offsite Emergency The responsibilities of the Company during an offsite emergency include the following:

(1) To provide the best possible effort to resolve the emergency onsite and thus alleviate the offsite conditions.

(2) To notify participating agencies in accordance with Figure 5-10. In addition, the Company will provide the best possible information, recom-mendations, and support services to these agen-cies in the least practicable time.

(3) To coordinate the Company's action with those of Federal, State and local agencies involved in offsite aspects of the emergency.

(4) To continue assessment of conditions throughout the emergency and provide current information to those concerned, as it becomes available.

g c. Participating Agency Responsibilities .

4 Participating agency responsibilities are denoted in EP 5.0, Section 5.0 and are further explained in the letters of agreement shown in Appendix "D."

e. Notification & Response Time Notification of businesses, property owners and tenants, school administrators, recreation facility operators, and the general public within the EPZ's will be accom-plished by local and State authorities as described in their response plans. An integrated siren system and the Emergency Broadcast System (EBS) will be used to notify the general public of an emergency requiring protective action. The State of Wisconsin has the responsibility of activating the integrated system  ;

including messages on EBS. These messages will include protective action instructions as well as general infor-mation concerning emergencies. The siren system controls ,

are maintained and operated by the Sheriff's of Manitowoc and Kewaunee counties. The siren system is tested periodically. The details of the means and the times to '

evacuate the above persons are discussed in Appendix "J."

5.2 Use of Onsite Protective Equipment & Supplies .

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/4 The use of protective equipment and supplies, as presented in Table 6-7,

! will be used to minimize external and internal radiological exposure and contamination to individuals on and offsite. Typical emergency

(

r EP 6.0 Page 12 s

)

equipment lists are present*d in Appendix "H." Detailed procedures on the use of protective equipment and supplies are inJorporated in the Health Physics Administrative Control Policies & Procedures Manual and the EPIP's (see Appendix "I").

5.3 Contamination Control Measures 5.3.1 Exclusion Area Measures will be taken to prevent or minimize direct expo-sure to or ingestion of radioactive materials within the onsite areas of the exclusion area. The details of the contamination control measures for onsite areas are con-tained in the Health Physics Administrative Control Policies

& Procedures Manual at the plant. The following is a brief outline of these procedures:

a. Controls have been established at the plant to ensure that routine levels of removable contamination outside the boundaries of the controlled area are maintained below 100 dpm/100 cm 2 beta gamma activity and nondetec-table for alpha activity. Fixed surface contamination limits are 0.1 mrem /hr measured at one inch from surface f s for beta gamma and 50 cpm as read by PAC-lSAGA survey

( ) instrument for alpha.

b. All tools and equipment used in the controlled area are checked for contamination before being taken from the controlled area. If the item is found to be contami-nated and decontamination is not practical, the item remains controlled. Equipment and tools are uncondi-tionally released for use outside the area if removable contamination and radiation levels are less than the allowable limits previously stated in EP 6.0, Section 5.3.1.a.

c. Removal of material and equipment from the controlled area with radiation and contamination levels in excess of the allowable limits must be approved for "condi-tional" release by HP personnel. Any item approved for

" conditional" release will be packaged, sealed, labeled, and handled in accordance with applicable regulations to prevent the release of any contamination.

d. Personnel working within the controlled area are moni-tored by HP personnel. Radiation work permits (RWP's) are required by all personnel working in high radiation areas or contaminated areas. Specific instructions, precautions, and limitations are listed on the RWP.

% e. Protective clothing is required to be worn by all indi-y_,) viduals entering a contaminated area. Individuals leaving the controlled area are monitored for contami-nation before entering the clean area of the plant.

EP 6.0 Page 13 s

i

f. The quarterly integrated accumulation of radionuclides in the body shall not exceed that which would result from exposure to the maximum permissible concentrations (MPC's) of radionuclides in air or drinking water for occupational exposure as indicated in 10 CFR 20.103. In general, exposure to airborne concentrations higher than the MPC's are prevented or avoided to the extent prac-ticable, but if exposures are necessary, the wearing of appropriate, properly fitted, respiratory protective equipment is required as determined by an HP Supervisor.

Periodic air samples are taken in selected operational and work areas to ensure that MPC levels are not ex-ceeded.

Decontamination following a radiological emergency will be conducted in accordance with approved EPIP's or approved routine HP procedures.

5.3.2 offsite For areas beyond the exclusion area, the State of Wisconsin Division of Emergency Government with the resources of the Division of Health & Social Services, Radiation Protection (ps) Section, is responsible for assessment and evaluation and will determine protective actions to be taken within the

\w / EPZ's. The State of Wisconsin Radiological Response Team (s) will identify levels and control access within the affected area. Other State agencies shall take actions, as neces-sary, under the direction of the Administrator of the Division of Emergency Government, to assess and control the dairy and agricultural products within the affected area.

In addition, the Administrator of the Division of Emergency Government, along with principal supportive State agencies, will provide advisory information regarding the use of potentially affected home food and water supplies throughout the EPZ. These State agencies will also be responsible for ensuring that contamination levels are below the established criteria before normal use is restored.

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

6.0 AID TO AFFECTED PERSONNEL Provisions have been made to assist personnel who are injured or have

[ {g)'s received high radiation exposures. Company employees and some contractor

personnel are trained in first aid and radiation protection procedures.

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EP 6.0 Page 14

\~ / First aid and decontamination facilities are available onsite and offsite, and necessary transportation services are also available. The following subsections describe measures to be used to provide any necessary assis-tance.

6.1 Emergency Personnel Exposure Criteria All personnel permanently employed at PBNP are issued a thermolumine-scent dosimeter (TLD) . Most also have a pocket dosimeter. Normal operating procedures require that these devices are picked up at the gatehouse and worn within the protected area. These requirements and associated normal procedures ensure that all plant personnel will have a monitoring device in the event of any plant emergency. It is the responsibility of HP personnel to ensure issuance of personnel monitoring devices to nonplant personnel whose services may be utilized during an emergency. Personnel monitoring devices are avail-able at the HP station, gatehouse, and the SBCC.

In all situations, every reasonable effort will be made to minimize exposure to emergency personnel. In the event of injuries, fires, or minor radiation incidents, the limits set forth in 10 CFR 20, Section 20.101 shall apply. In addition, the customary PBNP admini-strative radiation exposure limits will be observed. These limitu

, es are summarized in Table 6-9. In the event of major radiation emer-t( gencies, adninistrative limits may be suspended by the Site Manager or his designated representative upon the recommendation of the Health Physics Director. In some situations, it is possible that certain activities or duties for the protection of persons or the substantial protection of property may result in whole body doses of 25 Rem when immediate action is required. When circumstances allow time and planned actions to be taken, the expressed approval of the Health Physics Director or Chemistry / Health Physics Supervisor and the Site Manager or his designated representative shall be obtained by emergency workers prior to exceeding doses in excess of PBNP administrative limits and 10 CFR 20 limits. When circumstances do not allow time for planned actions, an attempt should be made to obtain approval from a group supervisor trained in HP procedures and a senior manager to exceed doses in excess of PBNP administrative limits and 10 CFR 20 limits. The Health Physics Director, Chem-istry/ Health Physics supervisor, and group supervisors are responsible to wisely allocate allowable exposure to emergency workers in excess of occupational limits. Individuals who have been exposed to more than 25 Rem to the whole body shall be removed from further emergency duty and referred to a physician for attention. Decisions to accept doses in lifesaving situations in excess of specified limits will be on a volunteer basis, and left to the judgment of the Health Physics Director and Chemistry / Health Physics Supervisor if available.

However, it is suggested that voluntary lifesaving exposures should be restricted to 100 Rem to the whole body. The prospective volunteer

'N should be made aware that whole body doses in the order of 100-200 Rem s,) may result in radiation sickness, and whole body doses in excess of

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EP 6.0 Page 15 m i 200 Rem involve a risk of fatality. The volunteer should avoid risk in cases where the victim's exposure is known to be at a fatal level or the victim is already fatally injured from an accident. After completion of lifesaving efforts, personnel who have been exposed to greater than 25 Rem to the whole body will be removed from further emergency duty and referred to the care of a physician.

The emergency exposure criteria for nonplant personnel and volunteers involved in providing first aid, decontamination, ambulance service, and medical treatment to injured persons shall be limited to the following criteria:

6.1.1 In the event of injuries, fires or minor radiation inci-dents:

i

a. Nonplant personnel are evacuated from the area and denied reentry except for medical and fire personnel.

b. Medical and fire personnel may be exposed to limits specified in Table 6-9 and 10 CFR 20.

6.1.2 In the event of a major radiation emergency such as some Site Emergencies, the provisions of emergency exposure f f- g criteria that were set for plant personnel shall be applied

(( ) to assisting nonplant personnel in the emergency response effort. When an assisting agency, e.g., DOE Region V Radio-logical Assistance Team or State of Wisconsin Section of Radiation Protection, has its own emergency plan, the pro-visions of that agency's plan shall apply to that agency's personnel.

6.1.3 Emergency Exposure Criteria for Airborne Concentrations In the event of an emergency, exposure to airborne concen-trations of radioactivity shall be limited by the following:

a. In the event of injuries, fires, or minor radiation incidents, normal plant limits apply. The 7-consec-utive-day integrated accumulation of radionuclides in the body should not exceed that which would result from exposure to the MPC's of radionuclides in air for occu-pational exposure as listed in 10 CFR 20, Appendix B, Table I. The MPC's then, for breathing air, are the same as listed in 10 CFR 20 except as may be provided by:

(1) In any 7-consecutive-day period where the planned numbers of hours of exposure will be less than 40, the limits specified in 10 CFR 20, Appen-

/N dix B, Table I may be increased proportionately.

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E EP 6.0 Page 16

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\s_,) (2) In any 7-consecutive-day period where the planned number of hours of exposure will be greater than 40, the limits specified in 10 CFR 20, Appendix B, Table I shall be decreased proportionately.

(3) Respiratory protection and stable iodine shall be used whenever appropriate to control inhalation doses (See Section 6.5 for details on admini-stering thyroid-blocking agents).

(4) Limits for exposure to Xe-133 and other noble gases are based on beta plus gamma dose limits to the skin.

b. In the event of a major radiation emergency such as some Site Emergencies, exposure to airborne concentrations of radioactivity shall be limited by the following:

(1) Whenever practicable, total exposure of any individual during an emergency should be limited to 40 MPC-hours. MCP-hours are simply calculated by multiplying the concentration in terms of the number of MPC's by the total time of exposure.

} (2) If emergency operations demand, total exposure of

[/

N- any individual shall be limited to 1,200 MPC-hours.

This is roughly equivalent to the 3 Rem / quarter limit for external radiation exposure.

(3) Respiratory protection and stable iodine shall be used whenever appropriate to control inhalation doses (See Section 6.5 for details on admini-stering thyroid-blocking agents).

(4) Limits for exposure to Xe-133 and other noble gases are based on beta plus gamma dose limits to the skin.

(5) It is the responsibility of all plant personnel, their supervisors, the Health Physics Director and the Chemistry / Health Physics Supervisor to wisely allocate the exposure permitted by (1) or (2) above.

(6) An integrated exposure of 10,000 MPC-hours for nuclides with relatively short effective half-

lives is roughly equivalent to an external, I whole-body exposure of 25 Rem and should be received only with the approval of the Health

( Physics Director or Chemistry / Health Physics f'"

l l (g) Supervisor and the site Manager or his designated i representative. Similar exposure to nuclides with long effective half-lives are to be avoided and should be restricted to 1,200 MPC-hours as in (2) above.

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EP 6.0 Page 17 (7) Since the effects of external and internal ex-posure may be additive, personnel should avoid exposures over 10,000 MPC-hours, even in the event of life-saving or rescue action, unless external radiation fields are minimal and unless effective half-lives are short.

(8) Personnel who have been exposed to more than 10,000 MPC-hours shall be removed from further emergency duty and referred to a physician for attention.

6.1.4 Exposure Records & Control Exposure records for emergency workers and forms are maintained for plant personnel at the extension building and OSC. This information will be utilized to determine emergency team assignments. It is the responsibility of the Health Physics Director and his designated personnel to establish and maintain the personnel monitoring program during emergency situations. Provisions for establishing an emergency dosimeter service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are provided as is distribution of self-reading pocket dosimeter to determine doses received by emergency (fs)

N' personnel. Detailed procedures for personnel monitoring are included in the EPIP's (see Appendix "I").

6.2 Decontamination & First Aid Facilities for decontaminating personnel are available at the HP sta-tion or with available supplies at the SBCC. All personnel leaving the controlled area or leaving a contaminated area will be monitored for contamination by use of appropriate survey instruments. During emergencies, personnel onsite will be checked for contamination as

( necessary.

Personnel found to be contaminated will undergo decontamination under the direction of HP personnel. Such measures may include isolating affected areas, placing contaminated personnel in clean protective clothing before moving, and decontaminating personnel, their clothing, and equipment prior to release.

Emergency first aid and medical treatment will be given to injured or

ill personnel. Shift personnel that are trained in first-aid are available onsite on a 24 hour-per-day basis and will assist injured or ill personnel either at the scene of the accident or in the first-aid room. If affected personnel must be transported to medical facilities, measures will be taken to prevent the spread of contamination if present. Such measures may include the placing of affected personnel l ~N in clean protective clothing or wrapping in blankets and alerting the l organizations who will provide the transportation and treatment.

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EP 6.0 Page 18 i

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(_/ The plant maintains an onsite first-aid room located in the extension building on the second level. The first-aid room is equipped with facilities suitable for the temporary care of a victim of an accident or illness until the services of a physician can be obtained. Addi-tional first-aid supplies are available at the following locations:

Gatehouse, turbine building, switchyard, Unit 1 and Unit 2 facades, SBCC, TSC, and entrance to the controlled area.

6.3 Medical Transportation An emergency vehicle maintained onsite will be used to transport injured and contaminated personnel. This vehicle is normally parked in the plant extension building garage. The vehicle is equipped with emergency first-aid and oxygen breathing equipment. In addition, arrangements have been made for backup assistance by the City of Two Rivers Fire Department emergency vehicle to provide transportation in case of the need to transport more than one injured party.

6.4 Medical Treatment Arrangements have been made with Two Rivers Community Hospital for treatment of PBNP personnel. Hospital personnel have been instructed and trained with regard to potentially contaminated patients. In

-~s addition,at least two area physicians have taken radiological health (N/ ) instruction courses under the sponsorship of the Company and are on the Two Rivers Community Hospital Staff. The University of Wisconsin Hospital in Madison, Wisconsin, will provide backup services in the event that the services of Two Rivers Community Hospital become tem-pararily unavailable or that additional services are required. The University Hospital provides instruction and training on handling radiological accident patients. Letters or written agreements with respect to arrangements for both hospitals and medical services are included in Appendix "D."

6.5 Iodine Prophylaxis (Thyroid Protection) 6.5.1 Background A number of chemical compounds can be ingested before or shortly after inhalation of radioactive material to inhibit the biological assimilation of inhaled radionuclides. Of these, stable iodine has received more attention as a chemical prophylactic agent than other elements because inhaled radioiodine presents a radiological hazard under certain types of nuclear reactor accidents.

Radiciodine is quickly absorbed into the blood stream and concentrates preferentially in the thyroid. This can result in significant doses to the thyroid gland. Therefore, a 77

{ }

EP 6.0 Page 19 protective action to be considered after an accident in-volving the release of a gaseous plume of radioactive material containing radioactive iodine, is the use of stable iodine as a thyroid-blocking agent. This can reduce the accumu-lation of radioactive iodine in the thyroid gland.

6.5.2 Criteria for Use The criteria for administering a thyroid-blocking agent (Potassium Iodide) to emergency personnel depends on the projected absorbed dose to the thyroid and the severity and magnitude of the accident. If the initial estimate at the j plant indicates that thyroid total absorbed doses of 0.9 Rem or more are projected, or if there is an inherent severity and magnitude of the accident, administration of a thyroid-l blocking agent will be distributed to company emergency and support personnel. For the greatest effectiveness, the thyroid-blocking agent should be administered as soon as

., possible, preferably within two hours of exposure. For most individuals the majority of radiciodine uptake by the thyroid occurs within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after a short-term exposure. The initial administration of a blocking agent will be of some value even as long as 4-8 hours after the exposure period.

s The determination of whether the thyroid-blocking agent should be continued on a daily basis will be determined by the Corporate Medical Director after evaluation of the situ-ation.

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TABLE 6-1 ASSESSMENT ACTIONS

• Action Description

1. Surveillance of Control Room Radiation levels, pressures, temperatures, levels, flows, and Instrumentation meteorological data are monitcred. The control room operators can assess plant status by observing sensor readout. Most sensors have visual and audio alarms. Primary and secondary system data will be provided to the Technical Advisor as necessary for his assessment. Control room operators will take corrective actions as necessary.

2. Personnel Accountability A head count of all personnel onsite made by the emergency organi-zation. Security log-in sheets and personnel rosters will assist in this assessment.

3. In-plant Radiological Surveys The radiation monitoring teams will perform these surveys. The radiation levels on the plant's fixed area and process monitoring systems will be obtained from the TSC or control room to assist in these evaluations. Surveys of equipment and personnel for contamination are done with portable equipment from the emergency lockers or other devices used routinely.

4. Site Boundary Surveys Handled in same fashion as in-plant surveys by the radiation moni-toring teams.

• NOTE: DETAILED ASSESSMENT ACTIONS PROCEDURES ARE DESCRIBED IN THE EPIP'S FOR VARIOUS EHERGENCY CLASSIFI-CATIONS (SEE APPENDIX "I").

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j Table 6-1 l Page 2 -

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Action Description i

j 5. Offsite Consequence Assessment The radiological assessment personnel will be using effluent monitors '

j and meteorological data to make assessments of offsite consequences. .

I Radiation monitoring teams will report survey results to validate calculations as time permits.

6. Environmental Monitoring For less immediate actions, samples of various environmental '

media are collected and analyzed by either PBNP personnel or an outside contractor laboratory. Results will be evalu-ated by WE personnel.

7. Assessment 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 the population-at-risk as illustrated in Table 4-2.

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Table 6-2 EVACUATION ACTIONS l

PLANT PERSONNEL i Personnel Visitors Assigned Emergency Outside Inside Duties Other Than Not Assigned j EVACUATION Protected Protected Contractor Control Room Emergency

{ CLASSIFICATION Area Area Personnel Personnel Duties

! Limited Plant No Action Take Action Take Action Take Action as Take Action j Evacuation Required as Directed as Directed Directed as Directed Plant Evacuation Take Action Report to Report to Report to the Report to OSC l as Directed SBCC SBCC TSC as Previously assembly area i Directed El. 18.5' of TSC building i

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Table 6-3 -

RECOMMENDED PROTECTIVE ACTIONS ACCIDENT PHASE EXPOSURE PATHWAY EXAMPLES OF ACTIONS TO BE RECOMMENDED Emergency Phase l Inhalation of gases, radio- Shelter, access control, evacuation, respiratory (0.5 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)* iodine, or particulate protection, prophylaxis (thyroid protection)

Direct whole body exposure Shelter, access control, evacuation Intermediate Phase 2 Ingestien of milk Take cows off pasture, prevent cows from (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 30 days)* drinking surface water, discard contami-nated milk, or divert to stored products such as cheese.

Ingestion of fruits and Wash all produce, or impound produce, produce delay harvest until approved, substi-tute uncontaminated produce.

Ingestion of water Cut off contaminated supplies, substi-tute from other sources, filter, demineralize.

Whole body exposure and in- Relocation, decontamination, access control halation

! A l Table 6-3 -

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. i I l ACCIDENT PHASE EXPOSURE PATHWAY EXAMPLES OF ACTIONS TO BE RECOMMENDED l

Long Term Phase 3 Ingestion of food and water Decontamination, condemnation, or destruction (over 30 days) f contaminated from the soil of food; deep plowing, condemnation, or alter-either by resuspension or nate use of land q uptake through roots I

Whole body exposure from Relocation, access control, decontamination .

, deposition material or fixing of contamination, deep plowing l j inhalation of resuspended I

! material. '

l (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.

i j (3) Long Term Phase - Recovery period.

• i

) *" Typical" post-accident time periods.  ;

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- _ _ _ . . = . _ - . .

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.l Table 6-4 REPRESENTATIVE SHIELDING FACTORS FROM GAMMA CLOUD SOURCE Shielding i) Representative Structure or Location Factor Range Outside 1.0 --

Vehicles 1.0 --

I 4 Wood-frame house (2) 0.9 --

l (no basement)

Basement of wood house 0.6 0.1 to 0.7 I)

Masonry House (no basement) 0.6 0.4 to 0.7( } ,

I l

Basement of masonry house 0.4 0.1 to 0.5(3) l Large office or industrial building 0.2 0.1 to 0.3(a 4)' '

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

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

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

(4) Theshieldingfactordependsonwherethepersonnei/arelocatedwith-in the building (e.g., the basement or an inside room).

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• Take from SAND 77-1725 (Unlimited Release) 4 s_ / .

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.-,-,_,,_,,.~-.,.,,.-..,-,,c..., . - , - _ - , - . - - . , . . . . - , , , , _ , , . . . , , . , , . . , , , . , , - - .,i,,-

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Table 6-5 SELECTED SHIELDING FACTORS FOR AIRBORNE RADIONUCLIDES Wood house,lno basement 0.9 Wood house,. basement 0.6 Brick house, no basement 0.6 Brick house, basement 0.4 j Large office or industrial building 0.2 i

Outside 1.0

• Taken from SAND 77-1725 (Unlimited Release) lI .

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[V REPRESENTATIVE SHIELDING FACTORS FOR SURFACE DEPOSITED RADIONUCLIDES g

Representative Shielding Representative Factor (1)

Structure or Location +

Range

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1 1 m above an infinite smooth 1.00 --

surface 1 m above ordinary ground - s 0.73 0.47-0.85 1 m above center of 50' road'-

ways, 50% decontaminated' O.55 0.4-0.6 Cars on 50' road:

Road fully contaminated 1 0.5 0.4-0.7 Road 50% decontaminated 0.5 0.4-0.6 Road fully decontaminated ,

0.25 0.2-0.5 Trains 0.40 0.3-0.5 One and two-story wood-frame 0.4(2) 0.2-0.5 house (no basement)

/ p). One and two-story block house (no basement) 0.2 2) 0.04-0.40 House basement, one or two walls l:4~

fully exposed: 0.1 2) 0.03-0.15 I h

) One story, less than 2' of 0.05 2) basement, walls exposed 0.03-0.07 Two stories, less'than 2' of basement, walls exposed 0.03 2) 0.02-0.05 Thr'ee- or four-stori struc- 2 tures, 5,000 to 10,000 ft per. floor:

First and second floors 0.01-0.08 Sasement. 0.05f2 0.01 0.001-0.07 Multi-story structures

>10,000 ft2 per floor:

Upper floors 0F'

. 2) 0.001-0.02 Basement C # l', O.001-0.015 (1) The ratio of dose received inside the structure to the dose that would be received outside the structure. 1

( (2) Away from doors and windows.

, Taken from SAND 77-1725 (Unlimited Release)

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Table 6-7 USE OF PROTECTIVE EQUIPMENT & SUPPLIES Equipment Criteria for Issuance

• Storage Location Means of Distribution

a. Respiratory Equipment:

1) Full-Face Respirator For areas of airborne (a) Control Room (a) Used as needed by operators (Filter)** particulate activity (b) HP Station (b) Issued under the control of Protection Factor-50 only (Notes 3 & 4). (c) Emergency Equipment Chemistry & Health Physics Lockers (d) Onsite OSC (Staging Area)

(e) SBCC

2) Continuous Flow Air- For areas of airborne (a) Control Room (a) Used as needed by operators Line (Supplied Air, particulate, iodine, (b) HP Station (b) Issued under the control of Full-Face Respirator) gas activity, or com- (c) Emergency Equipment chemistry & Health Physics Protection Factor- binations of same Lockers 2,000 (Notes 2 & 4).

• 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.

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. Table 6-7 Page 2

' Equipment Criteria for Issuance

• Location Means of Distribution

3) Self-Contained (a) Inhalation hazard (a) Control Room (a) Used as needed by operators l Breathing Apparatus during fire (b) HP Station (b) Issued under the control of 4

Protection Factor- fighting (c) TSC Chemistry & Health Physics

. 10,000 (b) For areas of air- (d) Emergency Equipment borne particulate Lockers iodine, gas activity, or combination of same (Notes 1, 2 & 4).

! b. Protective Clothing As needed in areas of (a) Various areas (a) Used as needed by operators (Coveralls, Hoods, known contamination of the plant

, Boots, Gloves) (b) SBCC

c. Potassium Iodide Reduce accumulation of (a) Control Room Issued as needed under j

for Thyroid-Blocking radioactive iodine in (b) Onsite OSC direction of HP personnel the thyroid gland, used (c) TSC I

durirg a radiation emergency only j NOTES 4

(1) This type of respirator may provide greater protection and is preferred emergency device in unknown airborn concentrations.

(2) Limitations on occupancy in gaseous atmospheres will also 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 of self-contained) are not recognized as effective for concentrations greater than two times HPC.

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.. e Table 6-8 GUIDELINES FOR PROTECTION AGAINST INGESTION OF CONTAMINATION

• O 1.0 GROUND CONTAMINATION 1.1 Action Levels 1.1.1 Projected whole body dose above the ground level 21 Rem.

1.1.2 Ground contamination levels 22,000 pCi/m 2 at t = 1 hr post-accident.

1.1.3 Exposure rate 212 mR/hr at 1 meter above ground at t = 1 hr post-accident.

1.2 Recommended Protective Actions 1.2.1 Evacuation of affected area.

1.2.2 Restriction of entry to contaminated offsite areas until radiation level has decreased to levels approved by the State.

2.0 FOOD & WATER CONTAMINATION 2.1 Action Levels J Concentration in Milk or Water (0.5 Rem WB (5 Rem WB or bone: or bone:

1.5 Rem 15 Rem Total Intake via all Pasture Grass thyroid) thyroid) Food & Water Pathways (Fresh Weight)

Preventive Emergency Level Level Preventive Emergency Preventive Emergency Nuclide* (pCi/1) (pCi/1) (pCi) (pCi) (pCi/kg) (pCi/kg)

I-131 (thyroid) 0.012 0.12 0.09 0.9 0.27 2.7 Cs-137 (WB) 0.34 3.4 7 70 3.5 35 Sr-90 (bone) 0.007 0.08 0.20 2.0 0.7 7

Sr-89 l (bone) 0.13 1.3 2.6 26.0 13 130

References:

U. S. Food & Drug Administration, Federal Register, Vol. 43, No. 242, December 15, 1978.

I

! If other nuclides are present, Regulatory Guide 1.109 will be used to I

calculate the dose to the critical organ (s). Infants are the critical segment of the population.

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Table 6-8 Page 2 2.2 Recommended Protective Actions Preventive Emergency

1. Removal of lactating Isolate food and water from cows from contaminated its introduction into commerce pasture and substitution after considering:

of uncontaminated feed.

a. Availability of other

2. Substitute source of un- possible actions; contaminated water.

b. Importance of particular

3. Withhold contaminated food in nutrition; milk from market to allow radioactive decay. c. Time and effort to take action;

4. Divert fluid milk to pro- d. Availability of other foods.

duction of dry whole milk, butter, etc.

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Table 6-9 I

ADMINISTRATIVE EXPOSURE LIMITS 5 1

9 Extremities '

(Hand, Fore-arms, Feet &

Category Whole Body 3 Skin 4 Ankles)

A. Daily Administrative Limits 2 300 mrem (100 mrem)1 600 mrem 1,500 mrem B. Weekly Administrative Limits! 600 mrem 1,200 mrem 3,000 mrem i

i 1 Notes:

(1) Exposure in excess of the 100 mrem limit requires the approval of the group supervisor.

(2) Exposure in excess of the daily (300 mrem) or weekly administrative limits requires the j approval of the Health Physicist or Superitendent - CHP. '

! (3) Whole Body Exposure is defined as exposure to the whole body, head and trunk, blood forming organs, I and lens of the eyes and gonads.

(4) Skin exposure is defined as exposure to the skin of the whole body.

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] (5) Limits are derived from Health Physics Administrative Control Policies & Procedures Manual. l 1 i f

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V EP 7.0 MAJOR

'3 Revision 19 07-30-82 EMERGENCY FACILITIES & EQUIPMENT 1.0 DISCUSSION This section of the Emergency Plan identifies, describes, and gives locations of emergency operation centers, support centers, communication systems, and first-aid and medical facilities.

2.0 CENTERS FOR EMERGENCY OPERATIONS The emergency facilities, as shown in EP 10.1, are a coordinated group, separated physically to minimize interference and confusion, and connected by dedicated communications lines to ensure an uninterrupted flow of data and instructions. Figures 7-1 and 7-2 show the emergency communications network that will allow coordination of all phases of the emergency response operations.

2.1 Emergency Support Center (ESC) (See EP 2.0, Section 1.18) gs This facility, under the direction of the Emergency Support Manager

(, ) assisted by the Site Manager, is the focal point of all emergency response operations and is the primary interface between PBNP and offsite agencies. Comprehensive coordination is achieved by:

2.1.1 Maintaining communication links with the other emergency centers and receiving periodic updates of the progress of the emergency procedures.

2.1.2 Providing primary contact point for State and local emer-gency response agencies and providing information and coordination during the emergency response operations.

2.1.3 Directing overall emergency response operations of Company personnel both onsite and offsite.

2.1.4 Obtaining technical assistance from Westinghouse Electric Corporation, Bechtel Power Corporation, and other vendors who can contribute to the response effort.

2.1.5 Providing adninistrative and logistic support for the addi-tional personnel and equipment required.

2.1.6 Developing and initiating plans to handle large amounts of contaminated waste material.

EP 7.0 Page 2 O

\s_/ 2.1.7 Acting as a liaison with local health care facilities and coordinating the transfer of injured personnel who are radiologically contaminated.

2.1.8 Providing for offsite radiological surveys and organizing transportation, equipment, and personnel. Results will be evaluated by the Health Physics Director and transmitted to the Site Manager by the RadCon/ Waste Manager.

The ESC is located on the center and lower floors of the EIC with an alternate location at the TSC. Communications links will be main-tained with the TSC, SBCC, ENC, and designated offsite agencies.

2.2 Technical Support Center (TSC) (See EP 2.0, Section 1.43)

This facility is operated by the Technical Support Manager under the supervision of the Site Manager and serves as:

2.2.1 Primary communications link between the control room, ESC, and designated offsite agencies as shown in Figures 7-1 and 7-2.

2.2.2 Coordination point for all onsite activities during emer-

-, gency response operations.

'\__/ 2.2.3 Plant and computer system monitoring facility to provide real time data to technical advisory personnel for the evaluation of plant conditions and recommendation of response procedures.

2.2.4 Technical reference center with complete files containing appropriate drawings and system descriptions.

2.2.5 Coordination area for onsite health physics radiological monitoring personnel. From this point, they will be directed to assist in radiological surveys, personnel monitoring, j decontamination, reentry, and rescue procedures.

2.3 Operations Support Center (OSC) (Staging Area) l (See EP 2.0, Section 1.28) l This facility is provided to minimize congestion in the control room

! and the TSC by coordinating incoming and outgoing personnel during emergency response operations. The OSC serves as a:

2.3.1 Staging area to brief oncoming control room personnel of the emergency condition of the plant and thus minimize shift turnover time.

-~s 2.3.2 Coordination area for nonshift personnel to conduct site (v ) fire fighting procedures.

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EP 7.0 Page 3 O

V 2.3.3 Coordination area for technicians to be dispatched to areas requiring their support.

2.3.4 Coordination area during plant site searches for missing persons or security breaches.

The OSC (staging area) is located on El. 88 of the TSC building.

There are direct communications between the OSC and the TSC.

2.4 Control Room (See EP 2.0, Section 1.6)

The control room is the primary operations center during events classified as Unusual Event and prior to the activation of the other emergency centers for more serious accidents. The Shift Supervisor is responsible for initiating and coordinating all EPIP's, including security procedures, from the control room until additional assis-tance is available. All plant control manipulation is conducted from this area under the Shift Supervisor's cognizance. Access to the control room is limited by administrative control.

2.5 Security Building (Extension Building) (See EP 2.0, Section 1.40)

This facility, located in the extension building, is under the super-vision of the Security Supervisor, who coordinates:

'v 2.5.1 Primary access control at the gatehouse to limit both per-

[ sonnel and vehicular traffic to and from the site.

2.5.2 control point for both personnel accountability and per-sonnel monitoring during plant evacuation procedures.

Site security personnel assist as required with the emergency response operations. They initially report to the Shift Supervisor until the Site Manager arrives. In the event that the security building may not be radiologically habitable, the designated alternate location is the SBCC. The security building has a communications link with the control room which can be shifted to the TSC when the latter is activated.

2.6 Site Boundary Control Center (SBCC) (See EP 2.0, Section 1.41)

The operation of this facility is the responsibility of the Health Physics Director. The SBCC serves as:

2.6.1 A personnel accountability and contaminatica monitoring center for evacuated visitors and contractor personnel.

2.6.2 A health physics control point for individuals entering or leaving the site.

b

( / 2.6.3 A central point for offsite field radiological assessment teams. Information obtained will be relayed to the RadCon/ Waste Manager at the ESC.

EP 7.0 Page 4 O

\ l

\s / 2.6.4 A coordinating center for security and traffic control.

The SBCC is locationed at the south exclusion area boundary access road, approximately one mile southwest of the plant. Connunications links are established with the ESC and offsite radiological moni-toring teams. The alternate to the SBCC is the Two Creeks Town Hall.

2.7 Emergency News Center (ENC) (See EP 2.0, Section 1.14)

This facility, under the direction of the Emergency News Center Director, is responsible for providing the news media with infor-mation concerning the emergency. This facility will provide periodic updates of the emergency situation and coordinate with the public relations offices of the NRC, State, and local agencies to ensure that only one official-status report is provided. The ENC can main-tain communications links with the ESC and designated offsite news media agencies. The ENC is located at the Two Rivers Community House with an alternate location at the Kewaunee High School. The ENC will be activated at the discretion of the Emergency Support Manager.

3.0 COMMUNICATIONS SYSTEMS The details of the onsite and offsite emergency communications networks are

,_.s shown in Figures 7-1 and 7-2. The systems are designed to provide reliable p /  ; communication links between the various emergency centers and offsite s_- authorities. It consists of a combination of the plant public address j system, plant telephone system, multiple telephone lines to outside ex-changes, including dedicated telephone lines, utility communications and paging system, and radiocommunications facilities. A brief detailed de-scription is as follows:

3.1 Internal plant two-channel multi-station public address system. Each public address station has the capability of general announcement or party-line conversation via either channel.

3.2 PBX telephone system with at least 100 telephone extensions, including locations at the TSC, onsite OSC, ESC, and SBCC. Switchboards of the PBX system are located in the control room and the plant office area and control of the system can be transferred from the main office to the control room or vice versa by control room personnel. The PBX system has a battery backup power supply with approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of capacity. Three in-plant extensions automatically take over three Mishicot, Wisconsin exchange lines upon loss of all in-plant PBX system switchboard power.

3.3 Telephone lines to outside exchanges include six Mishicot, Wisconsin exchange lines; one Appleton leased line and two Milwaukee leased lines having communications capability through the microwave system; i

three microwave-based leased lines for computer time sharing which g-'3i have voice communications capability; one Milwaukee leased land line; one extension to the main WE Milwaukee switchboard; one NBC Operations

,,\~ direct line with extensions in the control room, TSC and SBCC; and one NRC health physics direct line with three extensions. There is a

EP 7.0 Page 5 (m) s- m Mishicot exchange line in the TSC, eight more in the ESC, and one pay phone line outside the gatehouse entrance to PBNP. The ENC has seven Two Rivers exchange lines, one PBNP PBX line and one WE central office Centrix system line. The ENC also has a 100-pair cable in-stalle6 which is available for use during an emergency.

3.4 An internal sound powered communications system with headset plug-in connections exists throughout the plant, including the control room.

3.5 Two-way radios are located in the control room and SBCC, and mobile units are provided in certain plant vehicles. There are also two portable units available for use by the DCS which are stored in the plant gatehouse. In addition, DCS's may utilize a personal telephone paging " beeper" while on call. There is also a two-channel network FM system utilizing fixed and portable units for operations and security use.

3.6 Radiocommunications are available to communicate with offsite facili-ties in the unlikely event that telephone communications should be interrupted. In particular, a transmit / receive capability exists 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day from the control room on the Manitowoc County Sheriff Department's frequency. This system allows indirect communications with the Two Rivers Community Hospital.

l'm i 3.7 In addition, a National Warning System (NAWAS) is also available for

\_ / communications with offsite facilities. This system is a statewide dedicated open-wire telephone warning system which enables PBNP to talk directly to the State Warning Center in Madison, Wisconsin; the Weather Station Offices in Milwaukee, Green Bay, Madison, and Lacrosse; and Manitowoc and Kewaunee County Sheriff's Departments in the event of an emergency. The State of Wisconsin, Division of Emergency Government is responsible for maintaining and testing the National Warning System (NAWAS).

3.8 Radios are available for communications between field assessment teams and the SBCC.

To ensure the continuous capability of providing early notification from the plant to the outside agencies for implementation of pro-tective actions, testing of communications links between the plant and these agencies will be conducted monthly. In addition, as described in EP 8.0 Section 3.2 periodic exercises and drills are conducted to further demonstrate adequate communications capability.

4.0 ASSESSMENT FACILITIES The monitoring instruments and laboratory facilities needed to initiate emergency measures as well 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 facilities are listed on Table 7-1.

1

EP 7.0 Page 6

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

4.3 Methods for detecting and measuring radiciodine concen-trations of 5 x 10 8 pCi/cc using a single channel analyzer and silver zeolite filters have been established. Kewaunee Nuclear Power Plant has agreed to count iodine samples at the request of PBNP.

5.0 PROTECTIVE FACILITIES & EQUIPMENT The control room is intended to serve as the onsite protective facility.

It is designed to be habitable under accident conditions. Emergency lighting, power, air filtration, ventilation system, and shielding walls which enable operators to remain in the control room to ensure the reactor can be main-tained in a safe condition. In addition, the operators will be able to evaluate plant conditions and relay pertinent information and data to the appropriate onsite and offsite emergency centers, personnel and agencies during all emergencies. To ensure that operating shift and other personnel can remain self-sufficient, portable radiation monitors, respiratory equip-ment, portable lighting, and alternate communications systems are maintained in the control room. During extreme conditions, selected personnel from the TSC will evacuate to the control room.

6.0 FIRST-AID & MEDICAL FACILITIES

((-s As l s A permanent medical facility is provided onsite at PBNP and is located in the security building (extension building) on the second level. It con-tains the supplies needed for first-aid treatment. Stretcher baskets and first-aid kits are at various locations throughout the plant. The first-aid kits are located on the uncontaminated or " clean" side of the plant. If, for emergency reasons, it is necessary to transfer first-aid supplies to a controlled or contaminated area, the unused supplies will be retained by HP personnel for disposition. The first-aid treatment of injured personnel will be administered by trained personnel. Further medical care may be obtained by transporting the individual to a hospital via emergency vehicle in accordance with the PBNP Hospital Assistance Plan in the EPIP's. The Company Medical Director is responsible for defining the requirements for the first-aid equipment throughout the plant. The PBNP Industrial Safety coordinator is responsible for maintaining the supply inventory. First-aid

! supplies are available at the following locations:

6.1 Gatehouse First-aid kit 6.2 Turbine Building Stretchers (outside control room, El. 8' Unit 1 truck access),

first-aid kit (control room), and burn kit (control room).

fv 6.3 Switchyard First-aid kit and burn kit

EP 7.0 Page 7 O

5s_s/ 6.4 Units 1 & 2 Facades Stretcher (El. 66' outside containment personnel hatch) 6.5 Site Boundary Control Center (SBCC)

First-aid kit and burn kit 6.6 " Checkpoint Charlie" (entrance to controlled area)

First-aid kit, burn kit, scoop stretcher, and oxygen breathing unit 7.0 DAMAGE CONTROL EQUIPMENT & SUPPLIES Damage control equipment consisting of fire hose stations, fire extin-guishers, fire hydrants, and portable lanterns are located throughout the plant to be used by the fire brigade teams in the event of a fire. The PBNP Fire Protection Manual describes the specific details of fire pro-tection, 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 as necessary for fire fighting, entry into airborne radioactive areas or entry into toxic gas areas. Other damage and control equipment and supplies will be used to affect repairs depending on the situation at hand (e.g., steam suits and miscellaneous equipment at the plant.)

{}

v 8.0 METEOROLOGICAL EQUIPMENT PBNP has a permanent meteorological installation. Meteorological data can be obtained from the recorders in the control room. The recorders continu-ously record wind speed, wind direction, and 00 (standard deviation of wind direction). In the event the above instrumentation is inaccessible or inoperative, such information can be obtained from the Kewaunee Nuclear Power Plant, local Coast Guard Station, or National Weather Service.

9.0 PROMPT NOTIFICATION SYSTEM I

Details of the PBNP prompt notification system are shown on Figure 7-3.

Listing of the equipment can be found on Table 7-3.

l The system is designed to provide notification of the public within 10 miles l of PBNP. The system as shown includes 11 sirens. State and local response l plans describe the use of this siren system and the associated provisions for use of local radio stations and the Emergency Broadcast System for message' dissemination.

10.0 MANITOWOC COUNTY EMERGENCY OPERATIONS CENTER Manitowoc county has a permanent emergency operations center at the county i g.s Sheriff's department in Manitowoc, Wisconsin. Kewaunee county has a perma-

• nent emergency operations center at the Algoma Police Department building

\' ') in Algoma, Wisconsin. These centers are used for command and control of county agency response to an emergency.

. O o v .

TABLE 7-1 ONSITE ASSESSMENT EQUIPMENT & FACILITIES SYSTEM EQUIPMENT Geophysical Monitors Meteorological I wind speed indicator Monitor wind speed at El. 150' I wind direction indicator Monitor wind direction at El. 150' 1 wind speed indicator Monitor wind speed at El. 10 meters <

1 wind c'd rection indicator with - Monitor wind direction. Monitor 00 calculator standard deviation of wind direction at El. 10 meters EIC* (windmill) Monitors wind speed & direction seismic 3 strong motion accelerographs Record ground accelerations (Unit 1 facade, switchyard & EIC*)

yda ological 6 lake resistance temperature detectors Monitor lake temperature 500 yds off shore I surge chamber level indicator May function as a lake level indicator 1 forebay level indicator May function as a lake level indicator

• The EIC is located approximately 100 yds. south of the protected area. The EIC also has 1 wind speed indicator and I wind direction indicator located at approximately El. 60'.

Radiological Monitors I

Unit 1 Process Monitors IR11 containment / containment purge stack Measures particulate activity 1R12 containment / containment purge stack Measures gaseous activity

m l

Table 7-1 Page 2 SYSTEM EQUIPMENT FUNCTION Unit 1 Process Monitors RMS-II Channel 3 containment purge stack Measures high range gaseous activity 1R15 steam air ejector Measures gaseous activity IR16 containment fan cooler liquid Measures liquid activity 1

1R17 component cooling loop liquid Measures liquid activity 1R19 steam generator blowdown Measures liquid activity Unit 2 Process Monitors 2R11 containment / containment purge stack Measures particulate activity 2R12 containment / containment purge stack Heasures gaseous activity RMS-11 Channel 4 containment purge stack Measures high range gaseous activity i 2R15 steam air ejector Measures gaseous activity 2R16 containment fan cooler liquid Measures liquid activity 2R17 component cooling loop liquid Measures liquid activity 2R19 steam generator blowdown Measures liquid activity

, Common Process Monitors R14 auxiliary building vent stack Measures gaseous activity 4

RMS-II Channel 1 auxiliary building Measures high range gaseous activity vent stack R18 waste condensate overboard Measures liquid activity R20 spent fuel pit heat exchanger Measures liquid activity R21 drumming (spent fuel pit) vent stack Measures gaseous activity

e x .

Table 7-1 Page 3

SYSTEM EQUIPMENT FUNCTION Common Process Monitors RMS-II Channel 2 drumming (spent fuel pit) Measures high range gaseous activity vent stack GW16 waste distillate overboard Measures liquid activity CR9 combined steam air ejector overboard Measures gaseous activity RMS-II Channel 5 combined steam air Measures high range gaseous activity ejector overboard GW112 gas stripper building vent stack Measures gaseous activity RMS-II Channel 6 gas stripper building Measures high range gaseous activity vent stack Units 1 & 2 Area Monitors R1 control room Monitors general area radiation levels 1&2R2 containment El. 66' Monitors general area radiation levels l R3 chemistry lab Monitors general area radiation levels 1&2R4 charging pump hallway Monitors general area radiation levels R5 spent fuel pit Monitors general area radiation levels 1&2R6 primary sample room Monitors general area radiation levels 1&2R7 seal table, con'tainment El. 46' Monitors general area radiation levels R8 drumming area Monitors general area radiation levels 1&2R22 steam generator blowdown tank Monitors radiation levels of secondary coolant tank i

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Table 7-1 Page 4 SYSTEM EQUIPMENT FUNCTION Radiation Monitors &

Sampling Equipment Gamma spectrometers (multichannel analyzers) Isotopic identification and analysis Geiger-Mueller survey instruments Measures gamma & beta radiation count rate (0-1,000 R/hr)

Ionization chambers Measures gamma & beta radiation dose rate (0-10,000 R/hr)

Contamination survey instruments Count samples, equipment & personnel for gross alpha, gross beta & gamma activity Air sampling equipment concentration

. Neutron survey instruments Measure neutron radiation dose rate TLD/ direct reading pocket ion chamber Measures personnel gamma dose Whole body counter Determines internal radionuclide uptake Fire Detection Smoke detectors Detect products of combustion Rate of rise heat detectors Associated with sprinkler systems, detect quick rise of temperature Facilities Chemistry laboratory & HP Station Equipped for chemical & radiological analyses (available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day) 15 TLD radiation monitoring stations Measure environmental radiation (available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day)

o

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l TABLE 7-2 e OFFSITE ASSESSMENT EQUIPMENT & FACILITIES i

System Equipment Function Geophysical Monitors Meteorological Wind speed & direction Monitors wind speed & direction at U.S. Coast Guard approximately El. 60'

Station, Two Rivers i

1 Manitowoc County Wind speed & direction Monitors wind speed & direction Airport at approximately El. 20' I

Surface temperature Measures temperature Radiological Monitors

),

Environmental (6) Fixed air sampling stations Collect particulate & iodines

{ Monitoring

?

(16) TLD radiation monitoring stations Measure environmental radiation I

Kewaunee Nuclear Gamma spectrometer Isotopic identification & analysis

! Power Plant i Laboratory Facilities i Kewaunee Nuclear Chemistry laboratory Equipped for chemical & radiological Power Plant analyses (available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day)

Vendor Chemistry & counting laboratory Equipped for chemical & radiological j analyses (available within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

I I

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. .. _. _ . . .. _ __ .- - ~ _ _ _ _ . _

l TABLE 7-3 KEWAUNEE & MANITOWOC COUNTY

~ SIREN LOCATIONS Siren No. Location Sound Level 1 613 Juneau Street, Kewaunee 124dBC l

2 .8 miles west of STH "42" on Krok Road 130dBC 3 .2 miles east of CTH "B" on Old Settler Road 125dBC i 4 .7 miles south of CTH "G" on STH "42" 130dBC l 5 1 mile east of CTH "B" on Nuclear Road 125dBC (Kewaunee County) 6 Northeast corner of CTH "B" and CTH "BB" 114dBC 7 Two Creeks Road and STH "42" 130dBC I 8 1.1 miles east of STH "163" on Nuclear Road 125dBC (Manitowoc County) 9 .4 miles west of STH "42" on CTH "V" 130dBC 10 .4 miles south of CTH "V" on STH "147" 114dBC 11 1500 - 27 Street, Two Rivers 125dBC (See Figure 7-3 for siren locations.)

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FIGURE 7-1 PBNP EMERGENCY RESPONSE EXCLUSION AREA COMMUNICATION NETWORK

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FIGURE 7-2 PBNP EMERGENCY RESPONSE OFFSITE COMMUNICATION NETWORK v

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See Table 7-3 for siren details.

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- t fb EP 8.0 '

O MAJOR Revision 19 07-30-82 MAINTAINING EMERGENCY PREPAREDNESS 1.0 DISCUSSION '

PBNP maintains, as two separate documents, this Emergency Plan and the EPIP's. It is intended that the Emergency Plan be maintained up to date by using established procedures contained in the Operating PBNP Admini-strative Control Policies & Procedures Manual, Quality Assurance, Volume 1.

The EPIP's contain detailed information extracted from the Final Facility Description & Safety Analysis Report (FFDSAR), other pertinent documents, and detailed site emergency procedures. The EPIP's are controlled by standard plant administrative procedures and are distributed and revised accordingly. As a minimum, the Emergency Plan and EPIP's will be reviewed on an annual basis and updated as necessary. Updates will take into account needed changes identified by drills and exercises. Approved changes to the Emergency Plan and EPIP's are forwarded to all organizations and indivi-duals responsible for their implementation. Revised pages are dated and marked to show where changes have been made.

2.0 RESPONSIBILITIES 2.1 Assistant Vice President The Assistant Vice President, as the designated Emergency Support Manager, has the overall responsibility for radiological emergency response planning, including the development and updating of emer-gency plans and coordination of these plans with other organizations, i corporate policy and plans, the FFDSAR, and the agreements and under-standing with Federal, State, and local organizations. The Assistant Vice President may designate personnel to assist him in meeting this responsibility.

2.2 Manager - PBNP The Manager - PBNP is responsible for the coordination of efforts in planning, training, exercises, drills, and review and updating of the Emergency Plan and EPIP's including agreements and understandings l with outside agencies. He will receive appropriate guidance on l emergency planning and preparedness from the Assistant Vice President.

The Manager - PBNP may designate personnel to assist him in meeting this responsibility.

i

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EP 8.0 p Page 2 Q

2.3 PBNP Manager's Supervisory Staff The PBNP Manager's Supervisory Staff will arrange for audits of the emergency preparedness program every two years. The audit will include the Emergency Plan, the EPIP's, practices, training, exercises, drills, records, and equipment. Management controls will be implemented for evaluation and correction of audit findings. The results of the audit will be documented, reported to the Manager's Supervisory Staff and the Offsite Review Committee, and retained for a period of at least five years.

3.0 ORGANIZATIONAL PREPAREDNESS 3.1 Training All personnel assigned to PBNP will take part in a formal training program under the direction of the Superintendent - Training and Health Physicist. Each individual will receive, as a minimum, general employee indoctrination and training. In addition, key plant personnel and personnel assigned duties associated with the Emergency Plan will undergo specialized training for their responsibilities. The Super-intendent - Training may delegate specialty instructor duty to personnel qualified to perform such training. Each Superintendent is responsible

('v

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for ensuring that his personnel have received the appropriate training.

The Superintendent - Engineering, Quality & Regulatory Services will senure proper training of Engineering, Quality & Regulatory Services and Administrative Services The training program for plant personnel with regard to the Emergency Plan will include the following:

3.1.1 All PBNP employees will be indoctrinated on the Emergency

Plan and EPIP's through the general employee training program.

The training provided through this program with regard to l emergency planning will be conducted on an annual basis as a l minimum with provisions for prompt indoctrination of new employees. The objectives of this training are to:

1

a. Familiarize personnel with the scope, applicability, and implementation of the Emergency Plan and EPIP's.

b. Teach the general duties and responsibilities assigned to all plant personnel.

i c. Keep personnel informed of any changes in the Emergency l Plan and EPIP's.

i o L

1 EP 8.0 Page 3

d. Maintain a high degree of preparedness at all levels of the plant organization.

3.1.2 PBNP personnel will receive, as a minimum, the following instructions:

a. Orientation in the general content of the Emergency Plan and EPIP's applicable to the group being trained.

b. Specific items which must be taught to all individuals are as follows:

(1) Location of emergency equipment and supplies; (2) Name, location, and function of emergency centers; (3) Plant alarms and personnel response; (4) Use of communications systems; (5) Personnel accountability; (6) Exposure criteria and unique accident exposure dp) problems;

\G (7) General radiaton protection orientation; (8) Location and availability of controlled copies of the Emergency Plan and EPIP's.

3.1.3 Personnel assigned to the onsite emergency organization with specific Emergency Plan duties and responsibilities will l

receive specialized training for their respective assign-ments as follows:

a. The various emergency managers and coordinators at l levels below the Emergency Support Manager will receive training in the coordinating details of the Emergency Plan and its interaction with State and local plans.

Special emphasis will be given to the required recom-mendations for offsite protective actions. This training shall be completed prior to the assignment of an indivi-dual as an emergency manager or coordinator and shall be updated annually.

b. The Company general office support personnel will take part in exercise and drills coordinated with PBNP as appropriate. These exercises and drills along with i proper annual training will ensure that headquarters personnel are aware of their emergency plan responsi-O bilities and are capable of fulfilling them.

i EP 8.0 O Page 4

c. The Company will annually provide the opportunity for training for offsite organizations and agencies as specified in respective agreements and understandings.

In addition, those offsite organizations and agencies that may provide onsite emergency assistance will be encouraged to become familiar with the general layout of PBNP facilities as it relates to their responsibilities, will meet key personnel and will be invited to attend appropriate Emergency Plan training and orientation courses conducted by or for the Company. Training programs will be provided for specific offsite organi-zations and agencies as appropriate.

d. The opportunity for annual training for hospital per-l sonnel, ambulance / rescue personnel, police, and fire departments will be provided which includes the pro-cedures for notification, basic radiation protection, and their expected roles. Appropriate training will be provided to these groups.

e. The company will provide on an annual basis some training for the general population in the EPZ (See Section 6.0 for details on Public Information Program).

f. The Company will annually provide the opportunity for interested media personnel to become more familiar with technical background of nuclear power generation in general and PBNP in particular.

3.2 Drills & Exercises PBNP conducts periodic drills and exercises. A drill in this context is a supervised instruction period aimed at testing, developing, and maintaining skills in a particular operation. It is often a compo-nent of an exercise which is an event that tests the integrated capa-bility and a major portion of the basic elements existing within emergency preparedness plans and organizations. Each drill or exercise is conducted to ensure that the participants are familiar with their duties and responsibilities, to verify the adequacy of and methods used in EPIP's and other emergency procedures, to check the availability of emergency supplies and equipment, and to verify the operability of j emergency equipment.

The Superintendent - Training and Health Physicist are responsible for planning, scheduling, and coordinating all Emergency Plan drills

and exercises. They may, however, assign personnel to assist them l with this responsibility. All Emergency Plan drills and exercises j are subject to the approval of the Manager - PBNP.

a

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EP 8.0 O Page 5 When a major drill or exercise is required, the Superintendent -

Training and Health Physicist will:

3.2.1 Develop and prepare a scenario. This scenario shall include but not be limited to the basic objective (s) of the drill or exercise; the date(s), time period, place (s) and partici-pating organizations; the simulated events; a time of real and simulated initiating events; a narrative summary describing the conduct of the drill or exercise and arrange- i, ments for qualified observers.

3.2.2 Coordinate efforts with other appropriate emergency organi-zations and agencies.

3.2.3 Obtain the approval of the Manager - PBNP.

3.2.4 Schedule a date to conduct the drill and assign observers.

3.2.5 Critique the results of the drill or exercise.

3.2.6 Retain critique results for review prior to future drills and guidance in developing Emergency Plan or EPIP's as appropriate.

(._-} In addition' the Manager - PBNP will assign personnel to correct any deficiencies.

3.3 Exercises PBNP conducts an emergency response exercise to demonstrate the effectiveness of the Emergency Plan on a frequency deterrained jointly with the State. This exercise includes mobilization of State and local personnel and resources adequate to verify the capability to respond to an accident. PBNP will invite qualified observers from Federal, State, and local governments to observe and critique the exercises. A critique is scheduled at the conclusion of the exercise to evaluate the ability of organizations to respond as required in the Emergency Plan. The critique will be conducted as soon as prac-ticable after the exercise. The scenario for the annual exercise will be varied from time to time such that all major elements of the emergency response plans and preparedness organizations are tested within a five-year period. PBNP will make provisions to commence an exercise between 6 pm and midnight and another between midnight and 6 am once every six years.

3.4 Drills Scheduled drills are held involving appropriate offsite as well as onsite emergency organizations. These drills are conducted by simu-

\ lating actual emergency conditions. Drills are evaluated by an

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EP 8.0

[\s./ Page 6 assigned monitor. Examples of drills that will be conducted and their frequenc,y, include:

3.4.1 CommunibationsDrills Communications with Federal, State, and local governments within the plume exposure pathway EPZ are tested monthly.

Communications with Federal and State emergency response organizations within the ingestion pathway EPZ are tested annually. Communications between PBNP, State, and local emergency operations centers, and field assessment teams are tested annually.

3.4.2 Fire Drills Fire drills are conducted in accordance with the PBNP Fire Protection Manual. The Fire Protection Supervisor will coordinate all fire drills with offsite agencies as necessary. ,

3.4.3 Medical Emergency Drills A medical emergency drill involving a simulated contaminated

) individual and containing provisions for participation by

\s / the Two Rivers Community Hospital are conducted every two years. The offsite portions of this drill may be performed as part of the required annual exercise. Since the Kewaunee

, Nuclear Power Plant will also be conducting drills with the hospitals on a biannual basis, the hospital will have annual drills.

3.4.4 Radiological Monitoring & Health Physics Drills -

Plant environs, radiological monitoring, and health physics drills, both onsite and offsite are conducted semiannually.

These drills evaluate the response to, and analysis of, simulated airborne and direct radiation measurements in the environment.

3.4.5 Chemistry Drills In plant liquid sampling exercises shall be done annually.

3.4.6 Site Accountability & Evacuation Drills A site evacuation drill is conducted so that all personnel are aware of proper routes and assembly areas. The account-ability procedure is checked as part of the evacuation drill l ) to ensure that all personnel have either been evacuated or

\s / accounted for onsite.

v EP 8.0

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Page 7 v

4.0 REVIE51 & UPDATING OF THE PLAN & PROCEDURES The Emergency Plan is reviewed and updated on at least an annual basis.

The Manager - PBNP is responsible for coordinating these efforts. The Manager - PBNP is also responsible for coordinating the review and updating of the EPIP's. This includes quarterly updates of emergency telephone lists.

The Offsite Review Committee is responsible for an annual review (Technical Specification 15.6.5.3.8.e.). The Emergency Plan is a major procedure although Technical Specification 15.6.8.1 does not clearly specify it.

Appendices to the Emergency Plan are minor procedures which are reviewed and approved appropriately. Distribution of the Emergency Plan will be in

'ccordance with QA Volume 1 procedure PBNP 3.15.5.

5.0 EMERGENCY EQUIPMENT & SUPPLIES Th.: Health Physicist is responsible for the inventory and inspecticn of designated emergency equipment and supplies exclusive of fire protection equipment. The Fire Protection Officer is responsible for the fire pro-tection equipment. He may, however, assign personnel to assist him with this responsibility.

Designated emergency equipment and supplies and their location are listed in Appendix "H" of the Emergency Plan. This equipment is. inventoried and inspected at least once each calendar quarter and after each use. Portable radiation monitoring equipment included in these inventories is calibrated in accordance with approved procedures. Reserve instruments / equipment will replace those which are removed from emergency kits for calibration or repair. Equipment, supplies, and parts having finite shelf lives will be checked and replaced as necessary. Any deficiencies found will either be cleared immediately or documented for corrective action.

A report, including any deficiencies, is submitted to the Superintendent -

Technical Services following each inventory inspection. He assigns personnel responsible for correcting deficiencies.

6.0 PUBLIC INFORMATION PROGRAM WE will provide on an annual basis some training for the general population within the EPZ. These training programs will include the following:

6.1 Educational material concerning radiation.

6.2 Identification of a contact point for further information.

a

e EP 8.0 Page 8 6.3 Protective actions which can be taken for any radiological emergency.

These actions would range from simple sheltering and respiratory protection to the more complex and serious steps such as evacuation.

In addition, public notification and education methods are included in the EPIP's. These procedures include methods of education and notification of .

the adult and transient population within a 10-mile radius.

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EP 9.0 MAJOR

(~'s) Revision 19 (G 07-30-82 RECOVERY 1.0 DISCUSSION outlined in EP 5.0 are those preplanned actions to be taken in the event that an emergency situation arises. After execution of these preplanned actions, there will be need for further plant actions. Depending on the nature of the particular situation, recovery procedures shall be developed for restoring operations and property as nearly as possible to a safe status. The less complex operations such as in an Unusual Event or Alert require only brief recovery action procedures. However, for the Site and General Emergencies, correspondingly complex recovery action procedures may be required. Although it is not practicable to plan detailed recovery actions for all conceivable situations, the following general guidelines will assist in determining the specific actions to be taken:

1.~ All recovery actions will be preplanned. This means that each specific action will be thought out in advance and discussed with responsible and knowledgeable personnel. If conditions permit, it is

/~' preferred that these be a written log of all actions to be taken and (k,)N by whom. Affected areas are roped off and posted with warning signs indicating radiation levels and permissible entry times based on survey results. Shielding is employed to the extent practical.

Access to such areas is controlled, and exposures to personnel entering such areas is documented.

1.2 Every reasonable effort should be made to limit radiation exposure of personnel involved in the recovery situation to levels as low as reasonably achievable. Exposures should not exceed 10 CFR 20 limits.

1.3 The Site Manager is responsible for evaluating the advisability and timing of authorizing personnel to reenter affected area (s). An RWP will be used to control access during recovery operations. Survey results and all other pertinent information will be collected from l

logs and other records or indicators in the control room and/or in l

the ESC. Individuals with direct knowledge of recent conditions in the affected area (s) will also be interviewed.

1.4 When all appropriate actions have been executed, the Site Manager may terminate recovery operations. The decision to terminate the recovery operations may be initiated by recommendations of a plant review committee established for the recovery, which is responsible

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EP 9.0 Page 2 7-)

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for gathering all available evidence on contributory factors and reviewing the recovery operations to ensure that all causal factors have been specifically identified and all abnormal conditions corrected or neutralized. In addition, this review committee will review recommendations from the Site Manager where a release of radioactive material has occurred and consult with those offsite authorities with regulatory or compliance responsibilities.

2.0 RECOVERY ORGANIZATION In those cases where post-accident conditions indicate that recovery oper-ations will be either complicated or will extend over a relatively long period of time, the plant operations will shift from the emergency response organization to a long-term recovery organization. The recovery organi-zational structure will be the same as the emergency response organization with additional modifications depending upon the nature of the accident, post-accident conditions (i.e., plant conditions, radiation / contamination levels, etc.) and other factors to be determined at that time. The advan-tage for adopting this transitional approach is for continuity (i.e.,

managers and directors know the problem areas), and lack of confusion among plant personnel and Federal, State and local support agencies.

Prior to initiating a long-term recovery organization, specific recovery

/T operational procedures shall be defined. A typical long-term recovery

('k_,/ organization description of the general plant staff assignments, basic functions, and primary responsibilities are further described below:

2.1 Assistant Vice President (Emergency Support Manager)

The Assistant Vice President (Emergency Support Manager) is respon-sible for selecting the senior personnel to fill the key position in the long-term recovery organization and for implementation and coor-dination of recovery operations (See Appendix "A", Section 2.0).

2.2 Manager - PBNP (Site Manager)

The Manager - PBNP (Site Manager) is responsible for the overall implementation and management of the recovery operations of the l plant. This includes overseeing the operations of the various func-tional groups and ensuring that all activities, proposed courses of action, and contingency plans receive proper analysis and coordi-l nation (See Appendix "A", Section 5.0).

2.3 Vice President, Communications (Emergency News Center Director) l l

( The Vice President, Communications (Emergency News Center Director) l is responsible for assisting in coordinating the exchange of infor-mation with public and governmental agencies (See Appendix "A",

s. Section 4.0).

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.t EP 9.0 Page 3 2.4 Director, Purchasing (Administrative & Logistics Manager)

The Director, Purchasing (Administrative & Logistics Manager) is responsible for providing the necessary administrative / logistics requirements such as communications, manpower, transportation, commissary arrangements, and accommodations (See Appendix "A",

Section 3.0).

2.5 Plant Operations Group (Appendix "A", Figure 3)

The Plant Operations group (Appendix "A", Figure 3) consists of the plant staff responsible for performing plant operations and mainte-nance activities during recovery operations.

2.6 Technical Support Group (Appendix "A", Figure 4)

The Technical Support group (Appendix "A", Figure 4) consists of the plant staff responsible for providing plant operations and engineering support, technical planning and analysis, in-plant HP management, and data reduction and management activities during recovery operations.

2.7 RadCon/ Waste Management Group (Appendix "A", Figure 5)

The RadCon/ Waste Management group (Appendix "A", Figure 5) consists

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of the plant staff responsible for safely and effectively managing the quantities of radioactive gases, liquids, and solids during the recovery operations.

2.8 Design, Construction & Planning Support Group (Appendix "A", Figure 6)

The Design, Construction, & Planning Support group (Appendix "A",

Figure 6) consists of the plant staff responsible'for developing plans and schedules, coordinating and monitoring the status of tasks and reporting the work progress of all other recovery support or management groups during recovery operations. In addition, the group coordinates the activities of the nuclear steam supply systems supplier, the architect engineer, construction forces, and other individuals or consultants.

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Appendix A s MINOR Revision 2

~') 07-30-82 EMERGENCY RESPONSE ORGANIZATION PERSONNEL FUNCTION & RESPONSIBILITIES 1.0 EMERGENCY DIRECTOR 1.1 Reports To President, Wisconsin Electric Power Company 1.2 Location Corporate headquarters.

1.3 Supervises WE general office emergency response and recovery management.

1.4 Basic Functions O' Responsible for the overall management of WE general office emergency response and recovery operations; with the primary objective of pro-viding the necessary management and technical support for the PBNP emergency response and recovery effort. '

1.5 Primary Responsibilities 1.5.1 Coordinates WE general office emergency response and re- '

covery operations in support of the plant's emergency and recovery effort.

1.5.2 Provides the supervision for the administrative and technical support of the emergency response and recovery operations.

4 1.6 Principal Working Relationships l

The Emergency Support Manager for the overall direction and coordi-nation of the emergency response and recovery operations to assist PBNP resources.

2.0 EMERGENCY SUPPORT MANAGER 2.1 Reports To Emergency Director O .

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Appendix A s Page 2

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2.2 Location Emergency suppott center.

2.3 Supervises operation of the ESC.

2.4 Basic Functions Coordinates the PBNP Emergency Plan, with respect to both offsite radiological consequence assessment and the interaction with the remainder cf Emergency Plan arrangements specific to the plant.

2.5 Primary Responsibilities 2.5.1 Establishes communications with the TSC and obtains infor-mation on the diagnosis and prognosis of the accident condition, the estimates of radioactive material releases, and the prevailing meteorological conditions. A communi-cations channel is to remain in use for this information as long as is necessary.

/~'N 2.5.2 Maintains communications with the offsite authorities desig-

%_- nated in the Emergency Plan and relates the accident diagnosis and prognosis information necessary for the offsite author-ities to implement their emergency plans.

2.5.3 Assists in organizing and dispatching onsite and offsite radiological monitoring teams as required.

2.5.4 Interprets the offsite radiological data obtained and updates the TSC and offsite authorities with the results, in terms of both real-time measurements and, to the extent possible, projected radiological exposures.

2.5.5 Arranges for any further onsite and offsite radiological evaluations as required.

2.5.6 Arranges for and dispatches any special assistance or i

service required (e.g. , radiological measurement or pro-tection equipment, onsite emergency medical treatment, etc.).

2.5.7 Maintains control over personnel at the ESC and assesses and provides for any considerations necessary for their safety.

2.5.8 Maintains communications with the ENC and coordinates the flow of information between the plant and corporate head-7s quarters.

2.5.9 Receives any responding representatives from offsite emer-gency agencies and assists in their information and communi-cations needs.

Appendix A s Page 3 1

l 2.5.10 Relates all of these actions to the remainder of the emer-gency response organization.

3.0 ADMINISTRATIVE & LOGISTICS MANAGER 3.1 Reports To Emergency Support Manager 3.2 Location Corporate headquarters.

3.3 Coordinates Adninistration and logistics.

3.4 Basic Functions Provides adminstrative, logistic, communications, and personnel support for the emergency response and recovery operations.

3.5 Primary Responsibilities

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(s_j/ 3.5.1 Administration Provides the general office support functions including typing, reproduction, office supplies, and office furniture.

Special items like photography services and facility / area maps may also be required.

l 3.5.2 Accommodations Handles the arrangements for motel, airline, and trailer.

Performs the functions of registration and general personnel orientation.

3.5.3 Communications Meets the telephone requirements of the overall emergency and recovery organization and provides special radio require-ments such as mobile units and radio pagers. An emergency /

recovery organization telephone directory will be maintained.

3.5.4 Purchasing Functions as the emergency and recovery organization purchasing agent with responsibility for contract negotiation /administra-tion and material control.

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Appendix A p Page 4 3.5.5 Finance Administers the petty cash fund and expense accounts. Provides for handling of payroll matters.

3.5.6 Commissary Provides for food deliveries, operation of the field kitchen, and for trash disposal.

I 3.5.7 Human Resources Meets the manpower request needs of the emergency and recovery organization both in the technical and craft disciplines.

Ensures that clerical support is available and provides labor relations assistance as required.

3.5.8 Transportation Staffs the motor pool facility and provides vehicles for the emergency and recovery organization. Maintains shuttle services between surrounding motels and airports. Supplies

,s special transportation (helicopters, buses), as required.

4.0 EMERGENCY NEWS CENTER DIRECTOR 4.1 Reports To Emergency Support Manager 4.2 Location Emergency news center.

4.3 Coordinates Personnel assigned to Public Affairs & Information.

4.4 Primary Responsibilities 4.4.1 The Emergency News Center Director is the ranking public information representative at the ENC who relays information to other employees at the center, supervises all communi-cations operations at the center, and distributes all news releases and statements. He coordinates information at the ENC with his counterparts from local, State, and Federal agencies and with other companies involved with the emer-gency, and provides a means of meeting the media's needs.

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4.4.2 The Emergency News Center Director is identified as the official company spokesman for the emergency, with the responsibility for arranging interviews, statements quoted in press releases or other announcements, and for presiding at formal press conferences.

Appendix A Page 5 n

d 4.4.3 The Emergency News Center Director ensures that accurate information is distributed to the nuclear power industry through the Atomic Industrial Forum.

4.5 Principal Working Relationships 4.5.1 The Emergency Support Manager for information on all press statements.

4.5.2 The Site Manager, as available, for up-to-date technical information on the plant and plant operations.

5.0 SITE MANAGER 5.1 Reports To Emergency Support Manager 5.2 Location Emergency support center / technical support center.

,, 5.3 Supervises Plant Operations, Technical Support, and RadCon/ Waste Managers.

5.4 Basic Functions Responsible for implementation and management of overall plant emer-gency response and recovery operations; with the primary objective of placing the plant in a safe shutdown condition, and then recovering the plant in a manner which minimizes any adverse health and safety effects on the public, employees, and contractors.

5.5 Primary Responsibilities 5.5.1 Responsible for overall management of all in-plant operating procedures and EPIP's in support of the objectives of the I emergency response and recovery operations.

5.5.2 Approves changes in the emergency classification assessments based on plant conditions, site meteorology and radiological data.

5.5.3 Appears at press conferences as available in support of the Emergency News Center Director to handle technical questions raised by the press.

5.5.4 Approves the analysis and the development of plans and pro-cedures which are conducted in direct support of plant

'N operations personnel.

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Appendix A Page 6 O

5.5.5 Reviews and approves plans and procedures to process and control liquid, gaseous, and solid wastes in a manner consis-f tent with overall emergency response and recovery operations.

5.5.6 Serves as chairman of any plant review committee established for the emergency response and recovery operations.

5.6 Principal Working Relationships 5.6.1 Emergency Support Manager for coordination and direction of implementation of the PBNP Emergency Plan and EPIP's, parti-cularly with respect to offsite radiological consequence assessment as a result of recovery operations.

5.6.2 Emergency News Center Director to provide technical assis-tance for press conferences.

5.6.3 Design, Construction & Planning Manager for coordination of any design, construction, and planning activities required by emergency response and recovery operations.

6.0 PLANT OPERATIONS MANAGER A

6.1 Reports To Site Manager.

l 6.2 Location Technical support center / control room.

. 6.3 Supervises i

f Plant Operations Support Staff, Shift Supervisor, Shift Support Coor-l dinator, Maintenance Supervisor, Security Supervisor, and the Training Supervisor.

6.4 Basic Functions Responsible for l'nplementation of in-plant emergency response and I recovery activities with the objective of taking the plant to a safe shutdown condition in a manner which minimizes any adverse health and safety effects on the public, employees and contractors.

! 6.5 Primary Responsibilities 6.5.1 Responsible for the implementation of all in-plant operating procedures and EPIF's in support of the objectives of the

-'s emergency response operation.

6.5.2 Implements emergency classification procedures by assessing plant conditions, site meteorology, and radiological data.

Appendix A Page 7 G

6.5.3 Responsible for all in-plant maintenance activities utilizing normal plant maintenance and support personnel.

6.5.4 Maintains an effecive in-plant security program in support of the emergency response and recovery operations.

6.5.5 Responsible for training of in-plant personnel on the re-quired emergency operating and maintenance plan and procedures in support of the emergency response and recovery operations.

6.5.6 Provides licensed personnel in direct support of plant shift operations personnel.

6.5.7 Implements in-plant plans and schedules to meet the objectives of the emergency response and recovery operations.

6.5.8 Provides information and recommendations to the Site Manager concerning future operations that could affect the plant or the environment.

6.6 Principal Working Relationships

, f3 6.6.1 Technical Support Manager concerning review and approval of proposed modifications to procedures, systems, and equipment.

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l 6.6.2 RadCon/ Waste Manager concerning plans and procedures to process and control liquid, gaseous, and solid wastes.

7.0 SHIFT SUPERVISOR 7.1 Reports To Plant Operations Manager

! 7.2 Location i

Control room.

7.3 Supervises Normal plant operations personnel and the emergency response organi-zation shift support personnel.

7.4 Basic Functions Responsible for the safe operation of the plant including implemen-tation of normal and emergency procedures and instructions to safely place and maintain the plant in a safe shutdown condition.

N Primary Responsibilities

) 7.5 7.5.1 Directs the activities of the normal plant operations per-sonnel and the emergency response organization shift support personnel.

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Appendix A Page 8 7.5.2 Operation of the plant in compliance with all normal plant procedures, directives, Technical Specifications, and emer-gency procedures.

7.5.3 Provides information and recommendations on accident response to the Plant Operations manager.

7.5.4 Responsible for monitoring plant parameters and plant condi-tions.

7.5.5 Responsible for system valve alignment and equipment opera-tions.

7.5.6 Responsible for interfacing with the emergency response organization in support of the emergency response opera-tions.

7.6 Principal Working Relationships 7.6.1 Maintenance, Instrument & Control, Supt. - Training, and Security Supervisors in support of the emergency response and recovery operations.

rx 7.6.2 Shift Support Coordinator regarding effective utilization of

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the shift support personnel.

8.0 SHIFT SUPPORT COORDINATOR 8.1 Reports To Plant Operations Manager 8.2 Location i

operations support center.

I 8.3 Coordinates l

Emergency support personnel assigned to the plant operations group.

8.4 Basic Functions l

Coordinates with the Shift Supervisor effective utilization of the emergency support personnel assigned to the plant operations group.

8.5 Primary Responsibilities 8.5.1 Provides support to plant operations in monitoring plant

-- parameters and analyzing plant conditions.

8.5.2 Provides support to plant operations in system valve align-ment and equipment operations.

Appendix A Page 9 8.5.3 Assists in coordinating the emergency response and recovery organization objectives requiring implementaton by the plant operations group.

8.6 Principal Working Relationships Shift Supervisor regarding the most effective utilization of support personnel.

9.0 MAINTENANCE SUPERVISOR 9.1 Reports To Plant Operations Manager 9.2 Location Operations support center.

9.3 Supervises Maintenance personnel in support of repair, installation, and modifi-4 cation of maintenance equipment.

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\ ,/ 9.4 Basic Functions Responsible for the repair of installed equipment (other than instru-ment and control equipment), and the installation of modifications to existing equipment in support of the emergency response and recovery operations.

9.5 Primary Responsibilities 9.5.1 Directs maintenance personnel in the repair of defective equipment in support of the emergency response and recovery operations.

9.5.2 Directs the normal maintenance personnel in the installation of modifications to existing equipment in support of the emergency response and recovery operations.

9.5.3 Secures necessary electrical power and mechanical equipment to assist emergency response and recovery operations.

9.6 Prinicipal Working Relationships Shift Supervisor in the repair of maintenance equipment and regarding i the installation of modifications in the maintenance area.

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Appendix A Page 10 10.0 TRAINING SUPERVISOR 10.1 Reports To l

Plant Operations Manager I

10.2 Location operations support center.

10.3 Supervises Training personnel responsible for procedures and other training in support of the emergency response and recovery operations.

10.4 Basic Functions Responsible for coordinating the training requirements of all in-plant personnel associated with the emergency response and recovery operations.

10.5 Primary Responsibilties 10.5.1 Directs the plant training personnel to provide training in

, direct support of the emergency response and recovery opera-tions.

10.5.2 Provides the necessary training equipment and facilities to effectively support the training needs of the plant.

1 10.6 Principal Working Relationships t

10.6.1 shift Supervisor regarding the training needs of the shift personnel in support of the emergency response and recovery I operations.

l 10.6.2 I&C Supervisor, Maintenance Supervisor, Chemistry / Health i Physics Supervisor, Security Supervisor regarding training needs on out-of-normal procedures in their areas.

11.0 SECURITY SUPERVISOR I

11.1 Reports To i

Plant Operations Manager 11.2 Location 1

[ Technical support center / security building.

11.3 Supe rvises Plant security personnel.

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Appendix A Page 11 11.4 Basic Functions i Directs the normal plant security personnel to provide required in-plant security.

11.5 Primary Responsibilities 11.5.1 Directs the normal in-plant security personnel in maintaining the plant security system in support of the emergency response and recovery operations.

i 11.5.2 Responsible for coordinating on-site personnel accountability with assistance from plant supervision during emergency situations.

s 11.5.3 Responsible for personnel evacuation and restricting access i to secured areas. .

, 11.6 Principal Working Relationships 11.6.1 All in-plant supervisors regarding emergency response and recovery activities requiring security protection.

11.6.2 All emergency response organization groups regarding security

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requirements for personnel requiring access to the plant.

11.6.3 Coordinate onsite evacuation routes with Chemistry / Health Physics Supervisor.

11.6.4 Law enforcement agency personnel to maintain control of potential trespassers and to establish appropriate road-blocks.

12.0 TECHNICAL SUPPORT MANAGER 12.1 Reports To Site Manager 12.2 Location i

Technical support center.

12.3 Supervises Technical Support Group personnel.

12.4 Basic Functions i '

Responsible for analysis and the development of plans and procedures

- in direct support of plant operations personnel with the objective of

. - . , - _ . . - - - . . . ,_ .. ~.-.- - ,. .

Appendix A Page 12 O

V placing the plant in a safe shutdown condition in a manner which minimizes any adverse health and safety effects on the public, em-ployees and contractors.

He provides a central facility for the collection, retention, retrieval, and transmitting of plant and local environmental parameters.

12.5 Primary Responsibilities 12.5.1 Analyzes instrument and control problems, determines alter-nates, and designs and coordinates the installation of short-term instrument and control modifications.

12.5.2 Responsible for all chemistry and health physics activities onsite by coordination of onsite sampling programs, dose assessment, dose management, and radiation protection pro-grams.

12.5.3 Analyzes problems, determines alternatives, and developes plans in the area of system operations.

12.5.4 Analyzes conditions and develops guidance for plant shift operations personnel for the protection of the core.

O V 12.'5.5 Developes out-of-normal operating and emergency procedures in direct support of plant shift operations personnel.

12.5.6 Provides a central facility for the collection, retention, retrieval, and transmitting of plant and local environmental parameters.

12.5.7 Helps resolve questions concerning plant licensing require-ments with NRC representatives.

12.6 Principal Working Relationships 12.6.1 Plant Operations Manager regarding implementation of the Emergency Plan and EPIP's.

12.6.2 RadCon/ Waste Manager regarding any plant manipulations that might affect in-plant radiation or waste inventory levels.

13.0 INSTRUMENT & CONTROL SUPERVISOR 13.1 Reports To Technical Support Manager 13.2 Location Technical support center.

Appendix A Page 13 13.3 Supervises Plant Instrument & Control personnel.

13.4 ' Basic Functions Responsible for analyzing problems, determining alternatives, developing emergency plans and the repairing of installed instrument and control equipment, and for the design and installation of modifications to existing equipment in support of the emergency response and recovery operations.

13.5 Primary Responsibilities 13.5.1 Analyzes instrument and control problems and develops plans for how the plant operations personnel can continue to monitor and control plant parameters.

13.5.2 Designs and coordinates the installation of modifications required to allow continued monitoring and control of plant parameters.

13.5.3 Directs the normal instrument and control personnel in the

] repair of defective equipment in support of the emergency

[

sm ,/ response and recovery operations.

13.5.4 Directs the normal instrument and control personnel in the installation of modifications to existing equipment in support of the emergency response and recovery operations.

13.6 Principal Working Relationships 13.6.1 Shift Supervisor in the repair of instrument and control equipment.

13.6.2 Systems Analysis & Procedural Support Coordinator regarding required instrument and control procedure development.

14.0 CHEMISTRY / HEALTH PHYSICS SUPERVISOR 14.1 Reports To Technical Support Manager 14.2 Location Technical support center.

14.3 Supervises

'N / Plant Chemistry / Health Physics personnel in support of health physics / chemistry / meteorology and procedures during the emergency response and recovery operations.

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Appendix A Page 14

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14.4 Basic Functions Responsible for directing the Chemistry / Health Physics Staff in accumulating onsite radiation / chemical data, dose assessments and radiation protection programs in support of the emergency response and recovery operations.

14.5 Primary Responsibilities 14.5.1 Directs the normal in-plant Chemistry / Health Physics personnel in monitoring, controlling, and evaluating plant chemical, radiological, and meteorological conditions.

14.5.2 Provides radiation protection and ALARA training, respiratory equipment training, and in-plant whole body counting, and decontamination.

14.5.3 Performs radiation protection activities as required in support of the emergency response and recovery operations.

14.5.4 Responsible for procedures for reentry into potentially highly contaminated areas or areas with high radiation

- levels.

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\s_// 14.6 Principal Working Relationships 14.6.1 Health Physics Director in matters affecting offsite radia-tion measurement data, dose assessment and waste management processing.

14.6.2 Maintenance and I&C Supervisors in support of maintenance /

instrument and control repair / modifications with radio-logical implications affecting the normal emergency response and recovery operations.

14.6.3 Security Supervisor in providing radiological monitoring in support of evacuation efforts.

15.0 SYSTEMS ANALYSIS & PROCEDURAL SUPPORT COORDINATOR 15.1 Reports To Technical Support Manager.

15.2 Location Technical support center.

15.3 Coordinates 7~

Support personnel analyzing problems and developing plans in the area of systems and equipment operations. Support personnel developing operating and emergency procedures.

Appendix A Page 15

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J 15.4 Basic Functions Analyzes problems and develops plans associated with the operation of plant systems and equipment. Develops out-of-normal operating and emergency procedures for plant operations personnel.

15.5 Primary Responsibilities

, 15.5.1 Analyzes problems associated with the operations of plant systems and equipment and develops plans to mitigate those problems.

15.5.2 Revises or rewrites existing operating and emergency proce-dures as required to reflect existing accident conditions.

15.5.3 Converts plant recovery plans into clear, concise, out-of-normal operating and emergency procedures for use by the plant operations group.

15.6 Principal Working Relationships 15.6.1 Shift Support Coordinator regarding systems and equipment problems that need resolution.

\s_, 15.6.2 Technical Support Manager regarding recommendations on how to contend with systems and equipment problems.

15.6.3 Shif t Support Coordinator regarding required out-of-normal operating and emergency procedures.

15.6.4 Core Physics Coordinator regarding required operating proce-dures to protect the core.

15.6.5 I&C Supervisor regarding procedures on use of modified controls, alternate instruments, and out-of-normal moni-toring and control requirements.

16.0 CORE PHYSICS COORDINATOR I

l 16.1 Reports To t

l Technical Support Manager i

16.2 Location Technical support center.

16.3 Basic Functions

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Analyzes core parameters and develops guidance for the plant shift operations personnel on SIotection of the core.

Appendix A (s

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Page 16 16.4 Primary Responsibilities 16.4.1 Analyzes core parameters to determine current conditions of the core.

16.4.2 Reviews proposed plant operations with respect to the effect on core conditions.

16.4.3 Develops recommendatins for plant operations that would affect safer core conditions.

16.5 Principal Working Relationships Technical Support Manager and Site Manager regarding proposed plant operations to affect safer core conditions.

17.0 ADMINISTRATIVE SUPERVISOR 17.1 Reports To

! Technical Support Manager 17.2 Location Technical support center.

17.3 Basic Functions Supervises clerical personnel assigned to the Technical Support Group

and coordinates the Technical Support Group needs for communications, office supplies, personnel, and office equipment with the Admini-

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stration & Logistics Manager.

17.4 Primary Responsibilities l 17.4.1 Provides typing, filing, and office equipment operations to all areas within the Technical Support Group.

17.4.2 Coordinates with the Administration & Logistics Manager the Technical Support Group needs for additional communications, equipment, office supplies, office equipment, etc.

17.5 Principal Working Relationships 17.5.1 Technical Support Manager and all Technical Support Group Staff regarding administrative support needs and staffing needs.

N 17.5.2 Administration & Logistics Manager regarding filling of the s ) Technical Support Group administrative and staffing needs.

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Appendix A Page 17 18.0 DATA PROCESSING COORDINATOR 18.1 Reports To Technical support Manager 18.2 Location Technical support center.

18.3 Coordinates Data processing.

18.4 Basic Functions Accumulation, retention, retrieval, and retransmittal of information needed by the emergency response organization.

18.5 Primary Responsibilities 18.5.1 Provides for the accumulation, retention, and retrieval of plant information and local environment parameters.

18.5.2 Transmits information needed by the emergency response organization.

18.5.3 Serves as a single location for the acquisition of data resulting in minimum interference with plant operations.

18.6 Principal Working Relationships Plant Operations Manager regarding acquisition of needed plant infor-mation and environmental parameters.

19.0 RADCON/ WASTE MANAGER 19.1 Reports To Site Manager.

19.2 Location Emergency support center.

19.3 Supervises Waste Systems and the RadCon/ Waste Management Group.

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Appendix A Page 18 19.4 Basic Functions Responsible for the development of plans and procedures to process and control liquid, gaseous, and solid wastes in a manner consistent with the emergency response and recovery organization objectives and to minimize any adverse health and safety effects on the public.

19.5 Primary Responsibilities 19.5.1 Develops plans and procedures for sampling and processing liquid, gaseous, and solid wastes.

19.5.2 Develops any required modifications to plant waste systems and conceptual designs of new systems and equipment.

19.5.3 Provides HP support offsite by coordination of offsite sampling programs, dose assessments, dose management, and radiaion protection and ALARA programs.

19.5.4 Provides information and recommendations to the Site Manager concerning future operations that could affect the plant or the environment.

19.6 Principal Working Relationships

( ' >

19.6.1 Site Manager and Technical Support Manager regarding imple-mentation of plans to obtain samples and process liquid, gaseous, and solid wastes, and to obtain data on plant waste systems status.

19.6.2 Design, Construction & Planning Manager for drawings and construction of systems and equipment and regarding planned and scheduled activities of the RadCon/ Waste Management Group.

19.6.3 Technical Support Manager concerning review and approval of proposed modifications to procedures, systems, and equip-ment.

20.0 HEALTH PHYSICS DIRECTOR 20.1 Reports To RadCon/ Waste Manager (out-of-plant responsibilities) and Chemistry /

Health Physics Supervisor (in-plant responsibilities) 20.2 Location Site boundary control center.

Appendix A Page 19 20.3 Supervises Health physics personnel.

20.4 Basic Functions Responsible for directing assigned health physics personnel in accumu-lating offsite radiation measurement data, performing dose assessments, and providing radiation protection assistance as directed to meet the needs of the emergency response and recovery operations.

20.5 Primary Responsibilities 20.5.1 Implementation of offsite radiological survey procedures.

20.5.2 Evaluates offsite doses based on radiation monitoring per-formed by health physics personnel.

20.5.3 Provides radiation protection training for support personnel.

20.5.4 Provides respirator training, fitting, and whole body counting services.

,-~

20.5.5 Develops plans for plant radiation surveys, sampling, shielding,

(? s_-I and special tools in support of waste systems processing and design modification activities.

20.5.6 Performs radiation protection activities as requested by the plant Chemistry / Health Physics Supervisor.

20.6 Principal Working Relationships 20.6.1 Chemistry / Health Physics Supervisor regarding radiation pro-tection support, dose evaluation, and dose management.

20.6.2 Radwaste Technical Support Coordinator regarding sampling and radiation measurements needed as well as protective clothing requirements to perform the work.

20.6.3 Waste group technical support personnel for recommendations regarding methods to reduce exposure.

21.0 LICENSING SUPPORT COORDINATOR 21.0 Reports To RadCon/ Waste Manager 21.2 Location C') Corporate headquarters.

Appendix A Page 20 1

21.3 Coordinates

! ALARA review, plant operations review, and resolution of license requirements with NRC representatives.

21.4 Basic Functions t Resolves questions of FFDSAR and Technical Specification commitments, abnormal operating modes, and other license requirements with NRC representatives.

21.5 Primary Responsibilities l

21.5.1 Works with NRC representatives to resolve questions concerning l

~

FFDSAR and Technical Specification commitments in light of existing plant conditions.

21.5.2 Works with NRC representatives to resolve license require- '

ments associated with proposed abnormal operating modes or plant modifications.

21.5.3 Provides ALARA review of proposed emergency response organi-zation activities.

Q L

s ,j 21.6 Principal Working Relationships l

21.6.1 NRC representatives regarding all license requirement areas.

21.6.2 Technical Support Manager regarding out-of-normal operating modes and modifications to the plant.

21.6.3 Design, Construction & Planning Manager regarding modifi-cations to the plant.

21.6.4 RadCon/ Waste Manager regarding ALARA review.

22.0 RADWASTE TECHNICAL SUPPORT COORDINATOR 22.1 Reports To RadCon/ Waste Manager.

22.2 Location Corporate headquarters.

22.3 Supervises Radwaste technical support.

4

Appendix A Page 21 22.4 Basic Functions Responsible for the development of plans and procedures to process and control liquid, gaseous, and solid wastes in support of the emergency response and recovery operations. Other responsibilities include developing decontamination plans in support of plant opera-tions; conceptual design of systems and equipment to accommodate waste processing needs and to reduce plant and offsite dose rates; and for reviewing the plans and procedures and modifications developed by the RadCon/ Waste Management Group to evaluate their effectiveness in achieving the objectives of expediting waste processing and reducing plant and offsite dose rates.

22.5 Primary Responsibilities 22.5.1 Maintains an updated status of the liquid storage tank, gas system, and solid waste systen inventories.

22.5.2 Develops plans and procedures to process liquid wastes.

22.5.3 Develops plans and procedures for processing gaseous wastes and maintain in-plant charcoal filter exhaust systems.

22.5.4 Develops plans and procedures for solid waste processing.

22.5.5 Assists in development of decontamination plans for affected plant areas.

22.5.6 Develops plans to reduce all liquid, gaseous and solid waste levels to a normal inventory.

22.5.7 Provides recommendations to the plant operating organization on chemistry and radiochemistry problems.

22.6 Principal Working Relationships 22.6.1 Technical Support Manager and the Health Physics Director in regard to technical feasibility of processing plans and their effects on the plant and environment.

22.6.2 Chemistry / Health Physics Supervisor with regard to implemen-tation of plans and procedures for processing wastes and to obtain the status of radwaste volumes.

22.6.3 Health Physics Director regarding in-plant and offsite dose rates and radiation protection and clothing requirements for waste processing; shielding, special tools, and monitoring instrumentation needed in the modification package; and

-s assessment of the effects of waste processing.

\

. 22.6.4 Technical Support Manager for technical advice concerning the adequacy and feasibility of the proposed modifications.

Appendix A Page 22 0 22.6.5 Chemistry / Health Physics Supervisor as requested for recom-mendations concerning plant chemistry and radiochemistry.

23.0 DESIGN, CONSTRUCTION & PLANNING MANAGER 23.1 Reports To Emergency Gupport Manager 23.2 Location Corporate headquarters.

23.3 Supervises Design, Construction & Planning Group.

23.4 Basic Functions coordinates the design, construction, and planning activities of the utility, A/E, NSSS Supplier, construction forces, and outside vendors.

23.5 Primary Responsibilities A

g,,) 23.5.1 Provides the direct contact between the utility and the A/E,

- NSSS Supplier, and Constructor, on administrative matters.

23.5.2 Determines the need for and provides engineering and_ technical i specialists assigned on a preplanned basis to the Technical Support, Plant Operations, and RadCon/ Waste Managers, and the Emergency Support Manager, if required. Ensure that these specialists are present, or their alternates are

( available. Is prepared to provide additional support as required.

23.5.3 Ensures that any design and construction activities are adequately staffed and equipped to provide timely support.

23.5.4 Directs, coordinates, and approves other engineering, design, and construction activities onsite.

23.5.5 Establishes which engineering, design, and construction activities, if any, shall conform to utility formal specifi-cations or be documented by utility quality assurance procedures.

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

23.6 Principal Working Relationships 23.6.1 Site Manager regarding plans for modificatons to systems and l equipment in plant.

l 1

• s y

Appendix A Page 23 O 23.6.2 Technical Support Manager regarding review and approval of proposed modifications to systems and equipment in plant.

23.6.3 RadCon/ Waste Manager regarding modifications to systems and equipment and support of activities in the waste management area.

24.0 DIRECTOR, QUALITY CONTROL 24.1 Reports To Design, Construction & Planning Manager 24.2 Location Corporate headquarters.

24.3 Supe rvises Quality control.

24.5 Basic Functions Responsible for directing and executing the quality control program

(/ for such construction tasks that the Design, Construction & Planning Manager may direct to meet the requirements of emergency response and recovery operations.

24.5 Primary Responsibilities 24.5.1 Ensures that the quality control activity is adequately staffed and equipped to provide timely support.

i 24.5.2 Directs and coordinates the implementation of the quality l control program for approved construction tasks.

25.0 UTILITY ENGINEERING DIRECTOR 25.1 Reports To Design, Construction & Planning Manager l

25.2 Location Corporate headquarters.

(

25.3 Supe rvises Utility engineering.

O O

i

,s- ,

- , ,n

-_w, , , , - - . - ., - - . ,

Appendix A i Page 24 i

,_,/

25.4 Basic Functions 7

Responsible for directing and administratively controlling and per-forming such engineering and design tasks that the Design, Construction

& Planning Manager may direct to meet the requirements of the emer-( gency response and recovery operatior.3.

T f 25.5 Primary Responsibilities

, ,~

25.5.1 Provides the administrative and technical control of any engineers and designers assigned to him.

25.5.2 Ensures that his engineering and design activity is adequately staffed and equipped to provide timely support.

25.5.3 Establishes"for the Design, Construction & Planning Manager which engineering, design, and ccnstruction activities, if

,any', shall conform to the utility's formaIrtechnical require-

'ments. ,

\ <

A l

?

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8 5

CONTROL ROOM PROTECTED TECHNICAL AREA SUPPORT CENTER SITE BOUNDARY EMERGENCY OPERATIONS ON SITE CONTROL CENTER SUPPORT CENTER SUPPORT CENTER EMERGENCY NEAR SITE NEWS CENTER CORPORATE IIEADQUARTERS OFFSITE NSS SUPPLIER ARCllITECT ENGINEER NRC OT!IER SUPPORT FIGURE 1 DIERGENCY FACILITIES s

\

i- . .. . _ _ , _ , . _ . ..___ ..-- _ _ . , . _ _ . _ _ , . _ , _ , _ _ _ _ - - .

1 .

l EMERGENCY DIRECTOR i

EMERGENCY EMERGENCY ADMINISTRATIVE NEWS SUPPORT & LOGISTICS DIRECTOR MANAGER MANAGER SITE DESIGN, i

MANAGER CONSTRUCTION &

PLANNING MANAGER TECHNICAL PLANT RADCON/ WASTE SUPPORT OPERATIONS MANAGER MANAGER MANAGER FIGURE 2 EMERGENCY RESPONSE ORGANIZATION

e PLANT OPERATIONS

' MANAGER 1

i SIIIFT SHIFT SUPPORT MAINTENANCE TRAINING SECURITY SUPERVISOR COORDINATOR SUPERVISOR SUPERVISOR SUPERVISOR i

i FIGURE 3 i

i PLANT OPERATIONS GROUP l

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I R TO R AS O RI O TV C SR I E NP I U MS D

A

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/ UR S U S SE C G G / I R I L LA YSO F A AN RYS C CA THI I I M SPV N N I R I I

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RADCON/ WASTE MANAGER RADWASTE HEALTH LICENSING

(( PHYSICS DIRECTOR SUPPORT COORDINATOR TECHNICAL SUPPORT COORDINATOR FIGURE 5 RADCON/ WASTE MANAGEMENT GROUP o

, ,.w,,,n, , , , , , , , , - , _ _ _ __,.- -,,-,,,,- _ - ,-,. _ ,- - - , , , . . . , - - - . , , - - - , - , , , , - - - , . , _ . _

i i

I l DESIGN, CONSTRUCTION

& PLANNING MANAGER i

i l

l .

j UTILITY ARCilITECT- NSS OTIIER DIRECTOR ENGINEERING ENGINEER SUPPLIER SUBCONTRACTORS QUALITY l

DIRECTOR CONSTRUCTOR & SUPPLIERS CONTROL i

4 i

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'i  :

FIGURE 6

, DESIGN, CONSTRUCTION & PLANNING SUPPORT GROUP i

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... __ =_ . __ . . - . . _ _. . _ _ _ _ _

i Appendix C MINOR

' Revision 2 J

07-30-82 i

MAPS l

J.0 GENERAL This procedure lists maps to show EPZ areas surrounding PBNP. The maps in-clude travel routes and congregate care locations and facilities. In this procedure, population roses are also included to show the population distri-bution within the EPZ areas currounding PBNP.

! 2.0 MAPS 2.1 Figure 1, " Map of PBNP & 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 &

l Travel Routes" h

( 2.4 Figure 4, " Map of Kewaunee County Congregate Care Locations &

! Travel Routes"

! 2.5 Fitfire 5, " Population Rose showing the Population Distribution Within an Area of 0 to 5-Mile Radius" 2.6 Figure 6, " Population Rose showing the Population Distribution Within an Area of 5 to 40-Mile Radius" I

i i

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DEPARTMENT OF TRANSPORTATION ^dd'"' * :

pg o r g,s COMMANDElt(mps)

V r - UNITED STATES COAST GUARD Ninth Coast Guard District (Y* / 1240 East 9th St.

Clevefand. Ohio 44199

, Phone: (216)-522-3913 3441 3 OCT G M

, Point Beach Nuclear Plant Wisconcin Electric Power Company Route 3, Box 48 Two Rivers, WI 54241 ATTN: Mr. REED

Dear Mr. Reed:

This is in reply to your letter of 19 July 1979 concerning response by the U. S. Coast Guard during an emergency situation at the Point Beach Nuclear Power Plant, Two Rivers, Wisconsin.

z Upon notification of any emergency affecting waterborne activities, Coast Guard Captain of the Port Sturgeon Bay'will respond in an appropriate manner consistant with their current operation. In the event of an emer-gency, the Captain of the Port at Sturgeon Bay may be contacted directly by telephone (414)-743-3366. .

Sincerel}'

e

/ A ,r/ ~

'/

,htain,U.S.CoastGuard fChief, Marine Safety Division

// By direction of the Commander, Ninth Coast Guard District Copy: MSO Sturgeon Bay

• Group Hilwaukee d

l er e

9 Hr. Glenn A. Reed 11anager - Nuclear Operations Point Beach Nuclear Plant ~

Wisconsin Electric Power Company Route 3 Box 48 Two Rivers, Wisconsin 54241

Dear Hr. Reed:

By signatdre below I hereby reaffirm and acknowledge the United States Coast Guards's understanding of, and agreement with, actions to be taken upon notification by Wisconsin Electric Power Company of an accident / emergency at Point Beach Nuclear Plant. Copies of the Point Beach Nuclear Plant Emergency Plan have been given to me and are kept readily available for use by persons in my organization who will direct the necessary actions. .

Telephone contact of the United States Coast Guard is as follows:

, I-. k

,'s \s (Please designate after hours contact, if any)

C371 S it.?TCl!, '/.'C T TETE. I41/-703 130/ 3 i

l Correspondence concerning this agency's participation and response should be directed to:

(:ETCtT IN C'T'CE .

CCAS':' GU!.FD S'".'.' TCI?

'7,T ?.TYi?c. . *.:T . r-9.91.1 A Signed: ll-u/jg.U'.W"cCG,CTIC

. ' ',4 WC Date: 72 .TULY lo70

.t

(.

4 .

s .'

Ifr. Glenn A. Reed ,

!!anager - Nuclear Operations Point Beach Nuclear Plant Wisconsin Electric Power Company Route 3 Box 48 .

Two Rivers, Wisconsin 54241

Dear lir. Reed:

By signature below I hereby ' reaffirm and ecknowledge the Division of Emergency Government understanding of, and agreement with, actions to be taken upon notification by Wisconsin Electric Power Company of an accident /cmergency at Point Beach Nuclear Plant. Copies of the Point Beach

!Juclear Plant Emergency Plan have been given to me and are kept readily available for use by persons in ray organization who will direct the necessary actions. -

,(

Telephone contact of the Division of Ettergency Government is as follows:

(Please designate after hours contact, if any) l 608-266-3232 (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) l Correspondence concerning this agency's participation and response should be directed to:

Michael P. Early, Adminis.trator Division of Emergency Government 4802 Sheboygan Avertue, Room 99 A. Madison, HI 53702 signed: (2 #

. ate:

7/ W h

/

! \

r  %

l .

Mr. Glenn A. Reed ..

Manager - Nuclear Operations \

Point Beach Nuclear Plant Wisconsin Electric Power Company Route 3 Box 48 Two Rive'rs, Wisconsin 54241

Dear Mr. Reed:

BysignatdebelowIherebyreaffirmandacknowledgetheRadiation Protection Section, Wisconsin Department of Health and Social Services' understanding of, and agreement with, actions to be taken upon notification by Wisconsin Electric Power Company of an accident / emergency at Point Beach Nuclear Plant. Copies of the Point Beach Nuclear Plant Emergency Plan have been given to me and are kept readily available for use by persons in my organization who will direct the necessary actions.

Telephone contact of the Radiation Protection Section, Wisconsin

.,('

Department of Health and Social Services, is as follows:

(Please designate after hours contact, if any)

Lawrence J. McDonnell Office phone: 608-266-Th614 -

( 214 hour0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br /> number: 608-266-3232 )

( n4 v4 =i nn n e vna,g.nrv nnvemeent )

Correspondence concerning this agency's participation and response should be directed to:

l l Lawrence J. McDonnell, Chief, Section of Radiation Protection P. O. Box 309 Madison, WI 53101 Signe ~

Qfe (i

                                               /

Date: Aurust 21, 1979 i O

I . t b - l Mr. Glenn A. Reed "' i Manager - Nuclear Operations l Point Beach Nuclear Plant l Wisconsin Electric Power Company l Route 3 Box 48 . l Two Rivers, Wisconsin 54241 l

Dear Mr. Reed:

By signatu'-e below I hereby reaffirm and acknowledge the Wisconsin i State Police's understanding of, and agreement with, actions to be taken upon notification by Wisconsin Electric Power Compan-J of an [ = accident / emergency at Point Beach Nuclear Plant. Copies of the Point Beach Nuclear Plant Emergency Plan have been given_to me and are kept readily available for use by persons in my organization who will direct the necessary actions. - Telephone contact of the Wisconsin State Patrol is as follows:

 ;. (-

(Please designate after hours contact, if any) (414) 921-0448 or 921-0442 Correspondence concerning this agency's participation and response should be directed to: Wisconsin State Patrol Jct. Hwy. 41 &.15.1, Route 5 P. O. Box 984 Fond du Lac, WI 54935 _- . Signed: b L'

                                                                     .t._ w s     _

Date: July 23, 1979 0 . w r - - - - e a- -.- . --+

           ~

Mr. Glenn A. Reed

• Manager - Nuclear Operations Point Beach Nuclear Plant Wisconsin Electric Power Company Route 3 Box 48 Two Rivers, Wisconsin'54241'

Dear' Mr. Reed:

By signature below I hereby reaffirm and acknowledge the Manitowoc County Sheriff Department's understanding of, and agreement with, actions to be taken upon notification by Wisconsin Electric Power Company of an accident / emergency at Point Beach Nuclear Plant. Copies of the Point Beach Nuclear Plant Emergency Plan have been given to me and are kept readily available for use by persons in my organization who will direct the necessary actions. . Telephone contact of the Manitowoc County' Sheriff Department ic as

_  %.)

l ' (\ follows: (Please designate after hours contact, if any) Telephone 684-4441 - Correspondence concerning this agency's participation and response should be directed to: Sheriff Thomas H. Kocourek, Manitowoc County l 1025 South 9th Street Manitovoc, S 54220. 3 Signed: Aus.d . Date: July 23, 1979 e

s V Mr. Glenn A. Reed Manager - Nuclear Operations Point Beach Nuclear Plant Wisconsin Electric Power Company Route 3 Box 48 Two Rivers, Wisconsin 54241

Dear Hr. Reed:

By signature below I hereby reaffirm and acknowledge the Two Rivers Community Hospital's understanding of, and agreement with, actions to be taken in the event of an accident / emergency at Point Beach Nuclear Plant. Specifically, the following proposals are agreed to:

1. The special emergency room will be maintained in readiness for use in the event that. an accident or injury complicated by radiation exposure occurs to one of your employees. It will also be available as an auxiliary first aid room for use by the hocpital in the event of a community disaster.

g 2. The Two Rivers Community Hospital will admit a patient from the

   ' /                special first aid room for further care if recommended by the supervising physician.

3. In the event of a serious radiation accident, the hospital will assist in the transfer of the patient to the University Hospitals in Madison, Wisconsin, for further treatment.

4. A Company Health Physicist will be responsible for decontamination of the room, equipment, etc., following its use. Any item which cannot be decontaminated will be replaced by the Company.

5. Annual instruction of the medical staff to maintain familiarity of the procedures will be provided by the Company.

l 6. Disposable articles such as hats, masks, gowns, and floor coverings will be provided by the Company. ~ Copies of the Hospital Assistance Plan have been given to me and are l kept readily available for use by persons in my organization who will l direct the necessary actions. 1 1 e

s ( O Telephone contact for the Two Rivers Community Hospital is as follows: i (Please designate after hours contact, if any) SlVITCHBOARD (414) 793-1178 Correspondence concerning this hospital's participation and response , should be directed to: IfILLARD L. SPERRY. PRESIDENT Tif0 RIVERS COMMUNITY HOSPITAL, 2500 Garfield St. Two Rivers , l'!i . 54241 signed: f4 -

                                                                                 *fuh_P Date:                                  7/23/79          -

f ( A e O

    --s     -   ---

i l

                  ,                                                                                              RECEIVED DOCTORS          C LI N I C,   LTD.                       g 4 4 ,Iw 070  r&

sat. capracto ermCET

• TWO RIVERS. WISCONSIN 84241 __

                                                                                                                    . . , . s .. . T .

g ......s..n...... August 8, 1979

                                                                                                                                        ]

u....u..........

          ....n....                                                                                                                     ,
     ............                                                                                                                       j
     .. u . .. e .u . .. ..

Erwin S. Huston, M.D. Wisconsin Electric Power Company i 231 West Michigan Street Milwaukee, WI 53201 .

Dear Dr. Huston:

By signature below, I hereby reaffirm and acknowledge that I, S. Lawrence'Kaner, M.D., will provide medical supervision and care for employees of.the Point Beach Nuclear Plant who have medical conditions complicated by exposute to radia-tion. I am competent to care for such patients, having Q attended the AEC Seminar.in " Medical Planning and Care in s (j , *\ Radiation Accidents" conducted at Brookhaven National 12boratory, Upton, New York'in 1970. In the event that I am unavailable, my alternate is Stephen L. Weld, M.D. Doctor Weld is also qualified to care for these patients having received similar training in the AEC sponsored seminar at Brookhaven in 1971. f / Signed: MA NM AN - S. Lawrence Kaner, M.D. v 'r !.D , Date: }'9/79 , Signed: S ephen L. Weld, M.D/ h Date: O ~7 4

                                                                                        ~I        /      '

O dd

Center for Health Sciences I I University of Wisconsin-Madison o v UniversityHospitaland Clinics 600 Highland Avenue Madison, Wisconsin $3792 May 28, 1982 Mr. Glenn A. Reed Manager - Nuclear Operations WISCONSIN ELECTRIC POWER COMPANY Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241

Dear Mr. Reed:

I am writing to confirm University of Wisconsin Hospital and Clinics' willingness to continue to serve as a referral resource for the Point Beach Nuclear Plant in case of a radiation accident. University Hospital has treated patients involved in radiation accidents in the past. The University of Wisconsin-Madison has many programs using

    's       radioiosotopes. The expertise and depth in personnel we have on campus
        )    with highly trained radiation physicists and at the Hospital in areas such as hematology, immunology, and blood therapy provide the necessary combin-nation of resources to deal effectively with severely injured patients.

Should a radiation accident occur in your facility, please contact University Hospital and Clinics as follows: Emergency Room University of Wisconsin Hospital & Clinics (608) 262-2398 Frank C. Larson, M.D. Director, Clinical Laboratories (608) 263-7507 Robert F. Schilling, M.D. Chief, Hematology Division Department of Medicine (608) 263-4689 Robert R. Radtke, Ph.D. Health Physicist University of Wisconsin-Madison (608) 262-8769 O!!).u: Jbf4 2 193fhank you very much for your continued interest in working with University y Wisconsin Hospital and Clinics.

. jnce re ly .()

b

            'd,<Ib'      .     .n Superinten eit F 68$ ___ m ___                                                                           UWH sr655 (4/80)

a Hr. Glenn A. Reed , Manager - Nuclear OperationsI Point Beach Nuclear Plant Wisconsin Electric Power Company . Route 3 Box 48 Two Rivers. Wisconsin 54241

Dear Mr. Reed:

By signature below I hereby affirm and acknowledge the Two Creeks Volunteer Fire Department will respond, if called, to provide assistance in'

         ;     the event a major fire occurs at the Point Beach Nuclear Plant.

Telephone contact for the Two Creeks volunteer Department is as follows: , Y. A0 lD W ~O/33 (2xtrAA w u A5*s AO. ) Phhso dilutA> Correspondence concerning the Two Creeks " Volunteer Fire Department's participation and response should be directed to: fd N OALA W AALU 0 N urn 0htL s h . A O K O .s A h lO 9 0 En b S.e.Y kb. um '~k.Abus L].O Abf/ Signed: M Wc syn _, Date: [ 2- 7 ' e d 4 '

a kN llLt. LO.'f

       ./      .                       ~

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                                  .m:;a cy= e e.a                                              ,

I.' M i s .. . W$q Wisconc)) E!acir:c po:.1a co.ri,.s.ir !z(;Gl'* f.V 231 WEST MICHICAti, MILWAUKEE,WISC0tiSirl 53201 u~g &g7g

                                                                                  ,                            p       ..

77

                                                                                                               ^

17_.1./... 7 . G December 18, 1979 k Pc. E. R. !!athews WISCO!!SIM PU3LIC SERVICE COR20 RATIO!! Post Office Box 1200 Green Bay, Wisconsin 54305

Dear Gene:

P Attached is a proposed agreement between Wisconsin Public Service Corporation and Wisconsin Electric Power Company ' s. , to provide back-up analytical capabilities in the event of a nuclear accident er other incident that might render the laboratory facilities at Kousunee or Point Scach inoperable. You will recall that this agreement partially fulfilla a part of the short-term lessons learned requirements that are to be completed by January 1, 1980. - l If you concur with this agreement, I should appreciate your copy to me. signing both copies of the attached form and returning one

                                                      ,             Very truly yours,
                                                                                      -                -m v v            Q-{       _      (

Execu ive Vice President  ; Sol Burstein

         ' Attachment                                                                                                                ,,
                                                                     .. d L.y           b.AYYd.C.,.l--            l       '.    ' S %*

0 I a

                                                                                            . W . j [l+ -
                                 ,                                                            W l Du

O SAMPLE ANALYSIS AGREEMENT Wisconsin Elcetric Power Company, owner and operator of the Point Dcach Nuclear Plant, and Nisconsin Public Scrvice Corporation, owner (together with Misconsin Power and Light Company and Madison Gas and Electric Company) and operator of the Kcwaunce Nuclear Plant, hereby agree to provide mutual assistance for sample analysis. It is understood that, in the

event of an accident which would disabic the laboratory facilitics at one of the aforementioned plants, the unaffected

. plant will make its laboratory facilities available for ! radiological and chemical analyses of air, water, filter, or other samples obtained from the affected plant. It is further understood that the affected plant will take every reasonable precaution to avoid contaminating or otherwise disabling the facilities of the unaffected plant. It is also agreed that

;          the operator of the affected plant will establish other analytical capabilities as expeditiously as possible after an
.          accident in order to avoid prolonged interference with operations i          at the unaffected plant.
,      b N                    This agreement can be revoked by mutual agreement by
   ,/ the parties at any time or by written notice of either of the parties 180 days in advance of the cancellation date.

b d Sol Burstein 2. R. Mdthews Executive Vice President Vice President - Power Supply Wisconsin Electric Power Company and Engineering Wisconsin Public Service Corporatics Date he.* l[ /??f Data k: c. . 2D /9f? g-~) v

CITY OF TWO RIVERS P. O. Ilos 87. Two Rivers. Wisconsin 54241

s R. Granman  !

41 f . 7931191 Counal. Manager sy Manager Government l since i m May 21, 1980 ,

                                                               ~

Glenn A. Reed, Manager Nuclear Operations Point Beach Nuclear Plant Wisconsin Electric Power Company ,. Box 47A Two Rive rs, Wi scon sin 54241 Dea r Mr. Reed: .' , By signature below. I hereby af firm and acknowledge that the City o f Two Rivers will cooperate to the extent possible to make the facilities of the Community House available for use upon noti fication by Wisconsin Electric Power Company of an accident / emergency.at the Point Beach Nuclear Plant. Telephone contact of the Two Rivers Communi ty House is as follows: Howard Perry, Parks and Recreation Di re c to r. O f fi ce : 414-793-1338 Home  : Correspondence concerning this matter should be

 ,                     directed to:

City Manager P. O. Box 87 Two Rivers , Wi sconsin ,54241 Sn erely, ,/

                        ..d@t/c
                      ,J mes R.
                                          ./ ^        A@ *                                           {

Grassman , i ty Mangger ,

                  /                                                        -

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    )

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     . s e

O Mr. Glenn A. Reed Manager - Nuclear Operations Point Beach Nuclear Plant Wisconsin Clectric Power Company 6610 Nuclear Road - Two Rivers, Wisconsin 54241

Dear Hr. Reed:

By signature below I hereby affirm and acknowledge that the Township of Two Creeks will make available to Wisconsin Electric Power Company the Two Creeks Town Hall for temporary use as a backup emergency support facility to be used by Wisconsin Electric Power Company in the unlikely event of a radiological emergency at the Point Beach Nuclear Plant. The telephone contacts to initiate use of the Town Hall as an i emergency center (24 hour availability) are:

                  ] { {~'L 0 4 f - f f

• f - Y / f (

Correspondence concerning this agreement should be directed to: i il2n'T PosFLa/Prcnr

                                        .k              lY k         W$    0 $    fb.l f Y signed:   ,,     /,wa/                xh ____

62 4 J M l a. s-u-Mo

                                                               /

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f .. Rott) 3, Boa 47A e

         -                                                                             Two Rivers. Wiscnnsor. 5424I (414) 755 4334 O        PointBeach EnagWmnuuan Centu                                                  .

Mr. Glenn A. Reed Manager-Nuc1 car Operations Point Beach Nuc1 car Plant -> Wisconsin Electric Power Co. 6610 v.ucicar Rd. Two Rivers, WI 54241

Dear Mr. Reed:

By signature below, I hereby affirm and acknowledge that the Kewaunee High School can be made availabic for use upon notification by Wisconsin Electric Power Company of an accident / emergency at the Point Beach Nuclear Plant. i j /k Telephone contact of the Kewaunee High School is as follows:

l. ( '

(Please designate after hours contact, if any) 388-3230 - Supt. 388-2951 - Principal After Hours -) 388-4462 - Supt. 388-2614 - Principal Correspondence concerning this agency's participation should be directed to: R. F. Plantico. Supt. of Schools 911 Third Street l Kewaunee, WI 54216 l l ~ _A-Signed: .T . Date: /16 [ . /9 9'd 1

                               /G O                                                      .

REdEIVED MAY 8 i3SO

   -   . - . .. - . -  ~ -     --   . _ _     _ -    _ _ . . . .. . . . . _ . . - - _ . ..            _ _ _ _ _ _ -
     ~
           #                                                                               Appendix E                 i MINOR 07-30-82 STATE OF WISCONSIN PEACETIME RADIOLOGICAL                                                   i i                                          EMERGENCY RESPONSE PLAN (ERP) l

\ l t (SEE CONTROLLED COPY IN HEALTH PHYSICIST'S OFFICE) ( I l l I 1 i l l 1 I I I i

          **                                                        Appendix F MINOR 07-30-82 l

l MANITOWOC COUNTY NUCLEAR FACILITY INCIDENT RESPONSE PLAN (SEE CONTROLLED COPY IN HEALTH PHYSICIST'S OFFICE) i i f C t I ( l I e

        .*                                                                                Appendix G MINOR 07-30-82 O

KEWAUNEE COUNTY NUCLEAR FACILITY INCIDENT RESPONSE PLAN r (SEE CONTROLLED COPY IN HEALTH PHYSICIST'S OFFICE) l l (O l i O

Appundix H MINOR Revision 2 07-30-82 V TYPICAL EQUIPMENT LISTS 1.0 GENERAL The procedure provides typical lists of equipment and supplies available for both on and offsite locations which may be required for use during an emergency at PBNP. 2.0 TSC & OSC HEALTH PHYSICS-RELATED EQUIPMENT & SUPPLIES 2.1 Air Sampling Equipment TSC OSC Low volume air sampler 1 1 High volume air sampler 1 1 AMS-2 cart mounted air sampler 1 N/A Particulate filters, low volume, box 1 1 Charcoal filters, Icw volume, box 4 4 Particulate filters, high volume box 1 1 Charcoal filters, high volume box 1 1 j r Silver zeolite filters 15 10 r Plastic bottles, 1 liter 12 12 (j) Q 50' extension cord 2 2 2.1 Dosimetry Equipment TSC OSC Dosimeters (0-5,000 mR) 20 20 Dosimeters (0-200 R) 6 N/A Dosimeter charger 1 1 Batteries, Size AA, pkg. 1 1 2.3 Survey & Mon'itoring Equipment TSC OSC Victoreen Vamp 1 1 Rad Owl II 1 1 Thyac III, side window probe 1 1 Batteries, Size D 12 12 Batteries, Size 9 V 3 3 Smear filters, box 10 10 Smear envelopes, box 1 1

   ,b o

i Appandix H Page 2 N 2.4 Signs TSC OSC Three-pocket placards 12 12

                                               " Radiation Area" inserts                                           12      12 "High Radiation Area" inserts                                       12      12 "RWP Required" inserts                                              12      12
                                               " Airborne Area" inserts                                            12      12
                                               " Contaminated Area" inserts                                        12      12
                                               " Radioactive Materials" inserts                                    12      12 2.5                        Respiratory Protection Equip.m.ent                                  TSC     OSC Clear-Vue respirator                                                 6       6 Ultra-Vue respirator                                                 6       6 Filter cartridges, box                                               1       1 Smoke test kit                                                       1       1 Bio-Pak 60                                                           4       3 2.6                        ':8P-Fo rms                                                         TSC     OSC CHP-02, Iodine Airborne Survey, pad                                  1       1 CHP-21, Miscellaneous Surveys, pad                                   1       1 CHP-22, Air Particulate Sample, and                                  1       1 CHP-31, Radiation Work Permit, pad                                   2       2 C g                                        CHP-34, Dosimeter Rezero, pad                                        1       1
      ,/                                       CHP-37, Irregular or Offscale Dorimeter Report, pad                                                1       1 2.7                        EPIP Forms                                                          TSC     OSC EPIP-01, Emergency Plan Airborne Radiation Survey Form                                              5       5 EPIP-02, Emergency Plan Survey Record                                5       5 EPIP-03, Dose Factor Calculation Sheet                               5       5 EPIP-04, Status Report on Plant Systems                             20      N/A EPIP-05, Worksheet for Status Report on RMS for Unit                                                20      N/A EPIP-06, worksheet for Status Report on RMS for Plant                                               20      N/A EPIP-07, X/Q Determination                                          20      N/A EPIP-08, Estimated Whole Body & Thyroid Prrjected                                                20      N/A EPIP-09, Estimated Whole Body Calculation                                       ;

Worksheet 20 N/A EPIP-10, Estimated Ground Deposition Calcu-lation 20 N/A EPIP-11, Summary of Whole Body Thyroid Dose & Ground Deposition 20 N/A EPIP-17, List of Missing Personnel 20 20 EPIP-18, Assembly Area Rotter 20 20 v Xe-133 Equivalent Release Rate, Worksheet j No. 1 10 N/A

        . _ _ . . -  - . - , _ . _ - _ _ .                    I       __ _ -.           . _ - - _ _ - _ _ r    . .      ,.

Apptndix H Page 3 (% ( ,,) 2.8 EPIP Procedures (Extra) TSC OSC EPIP 1.4, Radiological Dose Evaluation 5 N/A EPIP 1.5, Protective Action Evaluation 5 N/A EPIP 7.1.1, Chemistry & Health Physics Group Personnel Notification & Initial Response when Chemistry & Health Physics Personnel are Onsite 5 N/A EPIP 7.2.1, Activation of Health Physics Facilities at Site Boundary Control Center 5 5 EPIP 7.2.2, Activation of Health Physics Facilities at Operations Support Center N/A 5 EPIP 7.2.3, Activation of Health Physics Facilities at Technical Support Center 5 5 2.9 Miscellaneous TSC OSC Barricade tape, yellow / magenta, roll 5 5 Tuck tape, rolls 2 2 Hot spot tags 50 50 Radiation material hazard tags 50 50 C'/% Radioactive material cont..nination tags 50 50 A ,,) Yellow / magenta tape, roll 6 6 Yellow / black warning tape, roll 5 5 Plastic bags 3 x 5 50 50 Plastic bags 5 x 7 50 50 Potassium iodine use approval list 1 1 3.0 TSC INSTRUMENTATION 3.1 Parameters to be Displayed on Rack Mounted Two-Pen Recorders Th and Tc Loop "A" or "B" - Unit 1 (switched) Th and Tc Loop "A" or "B" - Unit 2 (switched) Pressurizer wide range pressure - Units 1 and 2 Pressurizer level - Units 1 and 2 Steam generator "A" and "B" pressure - Unit 1 Steam generator "A" and "B" level - Unit 1 Steam generator "A" and "B" pressure - Unit 2 Steam generator "A" and "B" level - Unit 2 Containment narrow range pressure - Units 1 and 2 3.2 Parameters to be Datalogged 3.2.1 Unit 1 Incore thermocouples (8-2 per core quadrant)

/  '\                        Auxiliary feedwater flow (2 channels - pump discharge
\s_I                           flow until steam genertar flev is installed)

App;ndix H Page 4 s

          )                     High pressure safety injection flow (2 channels - Train "A" and Train "B")

Containment sump level (one channel) Containment high range radiation monitor (1 channel) Containment purge exhaust vent stack high range effluent monitor (1 channel) 3.2.2 Unit 2 Incore thermocouples (8-2 per core quadrant) Auxiliary feedwater flow (2 channels - pump discharge flcw until steam generator flow is installed) High pressure safety injection flow (2 channels - Train "A" and Train "B") Containment sump level (1 channel) Centainment high range radiation monitor (1 channel) Containment purge exhaust vent stack high range effluent monitor (1 monitor) 3.2.3 Common Auxiliary building vent stack high range effluent monitor

~

Combined air ejector discharge high range effluent monitor Drumming area vent stack high range effluent monitor ( Gas stripper building vent stack high range effluent nonitor 3.2.4 Parameters to be Displayed Only Time Wind speed Wind direction 4.0 SOUTHGATE HEALTH PHYSICS-RELATED EQUIPMENT & SUPPLIES Recommended 4.1 Air Sampling Equipment Quantity Low volume air sampler 1 Particulate filters (low volume), box 1 Charcoal filters (low volume), box 1 Extension cord 1 4.2 Radiation Survey & Monitoring Instruments Vamp area monitor 1 5.0 SBCC EQUIPMENT & SUPPLIES 5.1 Sampling Equipment & Supplies j) Air sampler, gasoline operated 1 ,

  \s ,/                Air sampler, battery operated                                2

AppIndix H Page 5 b Recommended N Quantity Electric high volume air sampler 1 Poly gas sample bottles 12 Charcoal cartridges for air sampler, high volume 48 Charcoal cartridges for air sampler, low volume 50 Silver zeolite cartridges for air sampler, low volume 15 Filters for air samplers 2 pkg. of 100 each Gasoline and oil for air sampler, gallons 2 Sample tags 50 Plastic bags 50 100' extension cord 2 Planchets 20 5.2 Respiratory Protection Equipment Full-face respirators 2 Half-face respirators 2 Full-face filter cartridge 12 Half-face filter cartridge 10 gk 5.3 Fire Protection Equipment Fire extinguisher, dry chemical 1 5.4 Radiat3cn Survey & Monitoring Instrument

,                    Victoreen radgun (.01 mR/hr - 10 kR/hr)                              1 Radector III (.1 mR/hr - 1,000 R/hr)                                 1 Victoreen Model 490 Thyac III                                        1 PIC-6A ttIrvey instrument (1 mR/hr - 1,000 R/hr)                     4 RH3C personnel survey frisker                                        1 Johnson Associates, GSM-5, 0-50K cpm, 0-200 mR/hr                    1 MSC-1 sampler holder for GSM-5                                       1 Check source - CS-137                                                2 Check source - Sr-90                                                 1 Filters for smeers                                         2 pkgs. of 100 each Nuclear Chicago counter scaler                                       1 Coin envelopes, box                                                 1/2 HP-210 probe                                                         2 SH4 probe holder                                                     1 i

Earphones for Thyac III survey instrument 3 Side window probe 2 i Cord, BNC-BNC connector 2 l Cord, amphenol - BNC connector 2 o l l

r- i 9 Appandix H Page 6 ( ) Recommended Quantity 5.6 Personnel Monitoring Equipment Personnel thermoluminescent dosimeters (TLD) 100 Radiological dosimeters, 0-5R 16 Radiological dosimeter charger 2 5.7 First Aid & Decontamination Supplies First aid kit 1 Burn kit 1 Emergency drinking water tablets, bottle (50 tablets / bottle) 5 Water, gallons 30 Decon scap, powder (5 lb.) 1 Decon soap, liquid, quart 1 Hand brush 4 Cotton applicators 1 Potassium permanganate, oz. 4 Sodium bisulfate, pound 1 Kim towels, box 1

         '~~

Masselinn towels, pkgs. 5 e "409" cleaner, bottle 2 f" ( " Spic 'n Span", box 2 Masselinn mop 1 Regular sponge map 2 j Rag mop 1 Wringer 1

!                                            Large mop bucket                                              1 Kim wipes, box                                                1 Plastic bucket                                                2

, Cotton swabs, packets 5 Gauze sponges, 2 x 2 (100 per pkg.) 1 Nail brushes 4 5.8 Radiation Hazard Signs & Supplies Radiation warning tape 1 Radiation placards 10 Radioactive material and radiation hazard signs 10

l. Radiation contamination hazard taps 10 Contamination, high radiation, radioactive materia, and radiation area inserts 10 l Yellow / magenta ribbon, roll 8 Yellow / magenta rope, roll 1 l

l

9 Appendix H Page 7

       )                                                              Recommended Quantity 5.9   Communication Equipment & Supplies Portable 2-way radio KRQ-717                                 1 Telephone, plan PBX-extension with outside line capability                                                 1 WE telephone book                                            1 Two Rivers /Manitowoc telephone book                         1 5.10 Traffic Signs & Equipment Traffic cones for barricades                               20 Traffic lights for barricades                                8 Chains and padlocks for barricades                           4 Traffic flashlight                                           4 Traffic warning lights, batteries                            8
                " Closed Area" placards                                      6 5.11 Clothing & Toiletry Supplies coveralls                                                  25 Rainwear                                                     6 Rubber boots                                               10 Shoe covers, plastic                                       25 overshoes, winter                                            6 Gloves, rubber disposable                                    6 Gloves, cotton disposable                                    6 Mittens, winter                                              6 Towels                                                     12 Washcloths                                                 12 5.12 Stationery & Miscellaneous Supplies Desk, table and chair                                        1 Writing paper, pad                                           1 Pens and pencils                                       Assorted Tape, masking                                                2 Tuck tape, roll                                            10 Logbook                                                      1 Absorbent paper, roll                                         1 Paper cups, bag                                               1 Plastic bags                                                50 Sciscors                                                      1 Pocketknife                                                   1 Screwdrivers, set                                             1 Plastic funnel                                               4 Flashlight                                                    1 Batteries (for flashlight and survey instruments)           50 0

App;ndix H Page 8 7~

   ')

Recommended Quantity Flcshlight bulbs 6 Bulbs, incandescent 8 Electric clock 1 Electric heater 5 Wet / dry vacuum cleaner 1 Metal drum (55 gallon) 1 Dzl-lene gasoline stabilizer, quart 1 Leak bricks 12 Safety solvent, can 1 Metal funnels 2 Pencil sharpener 1 Chalk, bo:: 1 Bulletin board 1 Chalkboard 1 Table (regular) 1 Picnic tables 2 Calculator 1 5.13 Emergency Plan Documents PBNP Emergency Plan 1 (9 Health Physics Administrative Control Policies and Procedures 1 Dose Isopleth/ Map Package ) Personnel roster 10 Potassium iodide use approval list 1 DOE, Region V, Radiological Assistance Handbook 1 State of Wisconsin Peacetime Radiological Response Plan 1 5.14 EPIP Forms EPIP-01, Emergency Plan Airborne Radiation Survey 5 EPIP-02, Emergency Plan Survey Record 5 EPIP-03, Dose Factor Calculation Sheet 5 EPIP-04, Status Report on Plant Systems & Controls 5 EPIP-05, Worksheet for Status Report on RMS for Unit 5 EPIP-06, Worksheet for Status Report on RMS for Plant 5 l EPIP-07, X/Q Determination 5 EPIP-08, Estimated Whole Body & Thyroid Projected 5 EPIP-09, Estimated Whole Body Calculation Worksheet 5 EPIP-10, Estimated Ground Deposition Calculation 5 EPIP-17, List of Missing Personnel 5 EPIP-18, Assembly Area Roster 5 Xe-133 Equivalent Release Rate, Worksheet No. 1 5 se a

Appsndix H Page 9 [\s /I Recommended Quantity 5.15 EPIP Procedures (Extra) EPIP 1.4, Radiological Dose Evaluation 5 EPIP 1.5, Protective Action Evaluation 5 EPIP 7.1.1, Chemistry & Health Physics Group Personnel Notification & Initial . Response when Chemistry & Health Physics Personnel are On-Site 5 EPIP 7.2.1, Activation of Health Physics Facilities at SBCC 5 EPIP 7.2.2, Activation of Health Physics Facilities at OSC 5 EPIP 7.2.3, Activation of Health Physics Facilities at TSC 5 5.16 CHP Forms CHP-02, Iodine Airborne Survey, pad 1 CHP-21, Miscellaneous Surveys, pad 1 CHP-22, Air Particulate Sample, pad 1

   ,                 CHP-25, Counting Log Sheet, pad                              1
  ,  -~g'            CHP-31, Radiation Work Permit, pad                           1 CHP-33b, Visitors Monitored per 10 CFR 20, pad               1 CHP-33c, Visitor Personnel Monitoring Record, pad            1 CHP-34, Dosimeter Rezero, pad                                1 CHP-35, Dosimeter Summary Sheet, pad                         1 CHP-37, Irregular or Offscale Dosimeter Report               1 CHP-38, Lost or Damaged TLD Report, pad                      1 CHP-39, Personnel Contamination Report, pad                  1 CHP-40, Visitor TLD Badge Issue Report, pad                  1 CHP-44, Timekeeping Log - High Radiation Work Location, pad                                        1 CHP-56, Personnel Bioassay Evaluation, pad                   1 CHP-106, Occupational External Radiation Exposure History                                             1

! 6.0 FIRST AID ROOM EQUIPMENT & SUPPLIES 6.1 Furniture & Equipment t l Sink Examination table Examination cabinet Scale

i App;ndix H Page 10 f) sa 6.2 First Aid Supplies Assorted bandages and gauze dressings Tape Splints Scissors, bandage Forceps, splinter Burn kit, portable First aid kit, portable 7.0 TWO RIVERS COMMUNITY HOSPITAL EMERGENCY ROOM Recommended Quantity EQUIPMENT & SUPPLIES NFAR Triage Area 7.1 Decontamination Supplies Cotton applicators, pkg. 1 1 Decon powder 1 1 Decon soap, quart 1 1 Hand brush 2 2 Potassium permanganate (7 cap. pkg.) 1 1 Sodium bisulfate (7 cap. pkg.) 1 1 7.2 Radiation Survey Equipment & Supplies Dosimeter, 0-500 mrem 5 5 , Dosimeter, 0-2 Rem 3 2 Radiation warning signs and tags, assorted 10 10 Radiation warning tape, roll 1 1 Filter paper for smear surveys, box of 100 ea. 2 2 Envelopes, box 1/2 1/2 HP-210 probe 1 N/A 7.3 Protective Clothing Lab coats 6 6 Surgeon's caps 6 6 j Canvas or nylon shoe covers 10 N/A Gloves, rubber disposable 8 8 l Gloves, cotton disposable 8 8 l Plastic shoe covers 25 25 1 7.4 Miscellaneous Supplies Marking pens, pkg. I 1 Absorbent paper, 50' roll 1 N/A l Bags, plastic, assorted sizes 50 50 Bucket, plastic 1 1 Mop, sponge with spare sponge 2 2

 ,o d

l > 1 Apprndix H Page 11 (/>) Masslinn mop 1 1 N' Masslinn, bag 1 N/A Scissors 1 1 Tuck tape, roll 2 2 Masking tape 1", roll 2 2 Masking tape 2", roll 2 2 7.5 Respiratory Protection Equipment Half-face respirators with particulate filters 4 4 Smoke tubes / squeeze bulb 1 N/A 7.6 Documents & Procedures Medical Assistance Plan 1 1 Emergency Call List 1 1 7.7 Forms CHP-21, Survey Forms, pad 1 N/A CHP-34, Dosimetry Rezero Sheet 5 5

       ~

CHP-39, Personnel Contamination Report 5 5 CHP-83, High-Range Dosimeter Issue Sheet 5 5

       /N Y) h_._

   )
       ,. .                                                                                                                                  l AppIndix I MINOR Revision 1 07-30-82 LIST OF EPIP CATEGORIES &

CROSSREFERENCES TO THE EMERGENCY PLAN 1.0 CLASSIFICATION & ASSESSMENT EP 2.0, Sections 2.3 and 2.12 EP 4.0, Section 1.0 EP 5.0, Sections 2.0 and 3.1 EP 6.0, Sections 2.0, 3.0, and Table 6-1 2.0 UNUSUAL EVENT IMPLEMENTING PROCEDURES EP 4.0, Section 1.1 EP 5.0, Sections 3.1, 3.2, 6.0, 7.0 3.0 ALERT IMPLEMENTING PROCEDURES EP 4.0, Section 1.2 EP 5.0, Sections 3.1, 3.2, 6.0, 7.0 g 3 4.0 SITE EMERGENCY I'MPLEMENTING PROCEDURES EP 4.0, Section 1.3 EP 5.0, Sections 3.1, 3.2, 6.0, 7.0 5.0 GENERAL EMERGENCY IMPLEMENTING PROCEDURES EP 4.0, Section 1.4 EP 5.0, Sections 3.1, 3.2, 6.0, 7.0 6.0 EVACUATION EP 6.0, Sections 5.1.1.b, 5.1.1.d, and Table 6-3 ( 7.0 CHP RADIOLOGICAL RESPONSE & PREPAREDNESS ! EP 6.0, Sections 3.0, 4.0, 5.1.1.f, 5.2, 6.1, 6.2, 6.5 and Tables 6-1 and 6-7 EP 7.0, Sections 2.0, 4.0 I EP 8.0, Section 5.0 Appendix "H" t O l

i

          .?.

Appandix I Page 2 8.0 PERSONNEL ACCOUNTABILITY EP 6.0, Section 5.1.1.e 9.0 PLANT SECURITY EP 5.0, Section 4.2 EP 6.0, Section5.1.1.c EP 7.0, Section 2.5 10.0 FIREFIGHTING EP 6.0, Section 4.0 11.0 FIRST AID & MEDICAL CARE EP 5.0, Section 4.2 l EP 6.0, Sections 6.2, 6.3, 6.4 EP 7.0, Section 6.0 12.0 REENTRY EP 6.0, Sections 4.0, 5.3 13.0 RECOVERY EP 9.0 3 14.0 PRESS EP 4.0, Section 1.0 EP 7.0, Section 2.7 l 15.0 COMMUNICATIONS EP 5.0, Section 7.2 EP 7.0, Section 3.0 16.0 TRAINING, DRILLS & EXERCISES EP 8.0, Sections 2.0, 3.1, 3.2 17.0 EMERGENCY CALL LIST l EP 5.0, Figures 5-9 and 5-10 EP 6.0, Section 2.0 l l l l I i s 1

s Appindix J MINOR Revision 2 07-30-82 sJ EVACUATION TIME ESTIMATES FOR THE AREA SURROUNDING THE POINT BEACH NUCLEAR PLANT 1.0 DETERMINATION OF EVACUATION SECTORS For evacuation time estimation purposes, the area in the vicinity of PBNP was divided into the sectors and areas shown in Figure 1. The LPZ area approximates one 180* sector with a 2-mile radius as specified in the reporting format. A second 180*F sector consists of the remainder of the 2-mile radius ataa over Lake Michigan. The land area between the LPZ boundary and the 5-mile and 10-mile radius lines was divided into 6-45* sectors in a manner that would avoid the bisection of the City of Two Rivers and the Village of Mishicot. For evacuation time estimation purposes, it was assumed that any two adjacent 45 sector areas could require evacuation simultaneously depending on the variability of wind direction. Potential combinations of 45' sectors and associated evacuation time estimates are listed in Table A. Table A includes two sets of evacuation time estimates: One set is an estimate C/N for normal weather conditions; the other an estimate for adverse weather conditions. 2.0 NORMAL WEATHER ASSUMPTIONS In order to estimate evacuation times for normal weather conditions, the following assumptions were made: 2.1 The accident occurs during normal weather conditions, e.g., a clear or cloudy day with low or moderate winds, such that traffic flow would be unimpeded by weather conditions. 2.2 All roads and streets in the area are serviceable. 2.3 Residents of the area are involved in their normal everyday activi-ties. 3.0 ADVERSE WEATHER ASSUMPTIONS In order to estimate evacuation times for adverse weather conditions, the following assumptions were made, based on the normal preparedness for snow conditions in Wisconsin. i i l

Appendix J Page 2

    /

3.1 The accident occurs immediately following a heavy snowstorm. An accident during a snowstorm would not require additional time for evacuation; at the same time, it is recognized that radiological impact could be reduced due to radioiodine and particulate washout by snowfall or rainfall. 3.2 Plowing or salting of interstate and State highways and major county roads is in progress to the extent of minimum serviceability. 3.3 Lesser traveled county roads and local town roads and city streets have not been plowed. 3.4 All rural roads are accessible to police and emergency vehicles and private vehicles equipped with snow tires and/or chains. 3.5 The residents of the area normally have their own snow removal equip-ment and have the capability to exit their own property during emergency situations in a reasonable time. 4.0 EVACUATION PROCEDURE ASSUMPTIONS The following evacuation procedure assumptions were made in calculating the estimated times: r' 4.1 All steps required in the PBNP Emergency Plan have been implemented, including the notification of appropriate local and emergency govern-ment authorities. 4.2 The Manitowoc County Sherriff's Office and Division of Emergency Government have been mobilized and have established command posts. 4.3 Emergency personnel and vehicles are available and utilized as shown on Table A. The availability of up to 150 emergency and police vehicles and personnel was assumed for an accident requiring evacu-ation of the LPZ and a 90* sector area encompassing both the City of Two Rivers and the Village of Mishicot. In accordance with the Manitowoc County Evacuation Plan, notifying personnel would be drawn from t.he Sherriff's Department, the Wisconsin State Patrol, Two Rivers Police Department, State of Wisconsin Emergency Government, Manitowoc County Civil Defense and local firefighting agencies. 4.4 Establishment of traffic control measures to maintain the flow of traffic in the area and facilitate evacuation are assumed. These measures include the routing of rural traffic away from the City of Two Rivers and Village of Mishicot to reduce the potential for congestion problems. In the City of Two Rivers, maintenance of flow over the four bridges available for crossing the East and west Twin Rivers is also assumed. i 4 l

g App 7ndix J Page 3

         )       4.5   The primary means of notifying residents would be by police and emer-gency vehicles driving in the area with " yelp" sirens on, mobile public address system, and door-to-door personal contact.

4.6 Other means of notification to be used includ? broadcast media, telephones, and citizen band radio. Warnings to higher and lower eschelons of government include telephone, radio, and wire syc*em", of communication. 4.7 Evacuation takes place as the notification process progresses. A portion of the population will respond to broadcast media notifi-cations and implement evacuation without personal contact notification. 4.8 Most residents respond to instructions to tie a towel, handkerchief, or other form of signal to their door, gate or mailbox to indicate they have left the premises, thereby facilitating confirmation that evacuation has been completed. 4.9 School superintendents are alerted as part of the emergency mobiliza-tion process, and the required number of school buses to be used in the process of driving to or from schools are on standby. 4.10 Residents evacuate the area principally by private automobile, with N an average of about one vehicle per residence. Average driving speeds are assumed to be 25 miles per hour during normal conditions and 15 miles per hour during adverse weather. 5.0 EVACUATION TIME ESTIMATES FOR THE LOW POPULATION ZONE (LPZ) 5.1 Notification of Residents There are approximately 66 residences and 8 commercial or public buildings within the offsite precautionary plan LPZ boundary. The estimated resident population of this area is 265 persons. Assuming 15 emergency or police vehicles available and notification time of about 5 minutes per residence, or commercial or public building, approximately 25 minutes would be required to complete the notification process under normal conditions. During adverse weather conditions, approximately 60 minutes would be required to complete the notification process (see Table A). 5.2 Implementation of Evacuation Evacuation would begin as notification progresses. Evacuation would take place principally by private automobile. With an average of one vehicle per residence and three vehicles per business or other usen, approximately 90 vehicles would be involved- hence, no traffic problems are anticipated. It is estimated that each residence would be evacu-ated approximately 30 minutes after notification during normal conditions and within 60 minutes under adverse weather conditions. Evacuation of C/ s e

AppIndix J Page 4 i the offsite precautionary plan area could be completed approximately l 50 minutes after commencement of notification during normal conditions. I During adverse weather conditions, this evacuation is estimated to l require approximately 110 minutes. 5.3 Estimated Total Fvacuation Time for LPZ The estimated total time to evacuate the LPZ is 55 minutes during normal conditions and 120 minutes, or 2 hours, during adverse weather condi-tions. These estimates allow for the overlap of the types of activities (notification and implementation) involved. 6.0 90' SECTOR AREAS For estimating the evacuation time for the 90* sector areas, it is assumed that two adjacent 45* sector areas (see Figure 1) would require evacuation simultaneously. The various potential combinations of the six 45' sector areas are listed in Table A. Separate evacuation time estimates are shown for the LPZ to 5 mile radius and the 5 to 10 mile radius area. Evacuation time estimates for the City of Two Rivers and the Village of Mishicot are also presented in parenthetical format for the 90' sectors of the 5 to 10 mile radius area within which they are located. Also shown in Table A are evacuation time estimates for a special area, the Point Beach State Forest, located about 3 miles south-southeast of PBNP.

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 +

Evacuation time estimates for the 90* sectors from the LPZ to 5 miles range from 1.0 hours to 1.25 hours during normal weather conditions and 2.0 hours to 2.5 hours during adverse weather conditions. For the 90 sectors from 5 to 10 miles, the estimated range from 1.7 hours to 4.0 hours during normal conditions and 3.3 hours to 8.0 hours during adverse weather conditions. 7.0 SPECIAL FACILITIES It is estimated that the Point Beach State Forest could be evacuated in 2.5 hours during a peak use period when up to 1,200 persons could be using the forest campgrounds, picnic, beach, hiking trails and other facilities. In adverse weather, only approximately 100 persons are estimated to use the Point Beach State Forest, and they could be evacuated in 1 hour. The Two Rivers Community House has indicated a preference for sheltering-in-place. Hence, no special evacuation provisions are required for this facility. I

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D

4 Appendix J Page 5 8.0 EVACUATION ROUTE SEGMENT CAPACITIES All road seguents that would be used as evacuation routes within the 10-mile radius are 2 or 4 lane roads of 12' width per lane, except for two narrow bridges on minor routes in the Town of Two Rivers. Traffic control lights in the City of Two Rivers will result in some slowing of traffic flow during an evacuation; however, Table B has taken these flow restrictions into account. All rural highways have capacities of 1,400 vehicles per hour per lane. There are two exceptions on minor routes with expected' traffic of less than 100 vehicles per hour. These two segments have narrow bridges with 10' lanes and with the outside of the lane only 2' fr'om side ob-structions. The capacity of these bridges is estimated at 1,150 vehicles per hour per lane. All urban streets assume a segment capacity of 1,200 vehicles per lane per hour. There are no bridges that place restrictions upon the segment capacity. However, some traffic control lights may limit flow during peak use to one-half the per lane per hour flow. All light controlled evacuation routes through Two Rivers have four traffic lanes; therefore, two-lane full flow was assumed. 5

               '                                                                                                                                             N
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O . Table A 6 Evacuation Times, Estimates for the Area Near the Point teach Nuclear Plant

                                                                           . Normal Weather Conditions Estimate           Adverse Weather Conditions Estimate Estimated     Est.      Est. Pol. & Ema. Vehicles                     Estimated Evacuation Time                    Ear;m ted Evacuation Time Sactor        Resident     No. of   No. of Total Traffic            Notif.          Imp 1. Conf. Est. Total        Motif. Is 4     Conf.

er Area Population Residences Vehicles Avail Ctr1. Notif. Time Time Time Evac. Time Time Tis g, Time Total Evac. Time i.P.Z. 265 75 90 27 12 15 25 min 52 als 15 min 55 min /1 br 60 ala 110 min 30 min 120 min /2.0 hrs 90' Sector Areas LP2-5 mi Radius NW to N 250 62 67 30 15 15 25 mia 50 min 15 min 55 min /1.0 hr 50 min 110 min 30 mia 120 min /2.0 bre W to NW 440 110 120 30 15 15 40 min 65 min 25 mia 75 min /1.25 hre 90 min 140 min 50 min 150 mis /2.5 bre SW to kW 450 108 120 30 15 15 40 mia 65 min 25 min 75 min /1.25 hrs 90 min 140 min 50 mia 150 min /2.5 bre S to 43W 425 107 120 30 15 15 40 min 65 mia 25 min 75 min /1.25 hrs 90 min 140 min 50 mia 150 min /2.5 hrs SSE to SSW 300 75 80 30 35 15 25 min 50 min 15 mia $5 min /1.0 hr 60 mia 110 min 30 mia 120 min /2.0 hrs 90' Sector Areas 5-10 Mile Radius NW to N 1,275 320 350 40 10 30 60 mia 85 als 40 mia 100 min /1.7 kre 130 mia 180 eia 60 mia 200 mis /3.3 bra W to NW 2,245 565 600 40 10 30 100 mia 125 min 60 min 160 min /2.7 hrs 200 mia 250 mia 100 mia 270 min /4.5 kre SW to kW 3,820 1,280 1,350 55 15 40 140 mia 165 min 70 mia 210 min /3.5 kre 280 aia 330 min 120 min 390 min /6.5 hrs Rural (3,320) (830) (850) (40) (10) (30) (140 mia) (165 min) (70 min) (210 min) (210 mia)(330 min)(120 min) (390 min) Mishicot (1,500) (450) (500) (15) ( 5) (10) ( 50 min) ( 87 min) (40 min) ( 90 min) ( 60 min)(150 min)( 60 min) (170 min) 4

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                                                                                                                                                                      , Table'A cont'd Normal Weather Conditions Estimate         Adverse Weather Conditions Estfeste Estimated                Est.                                        Est. Pol. & Ema. Vehicles Estimated Evacuation Time                  Estimated Evacuation Time Srctor                               Resident         No. of                                             No. of Total Traffic               Notif.            Imp 1. Conf. Est. Totsi      .Notif. Imp 1. Conf.

er Area Population Residences Vehicles Avail Ctr1. Notif. Time Time Time Evac. Time Time Time Time Total Evac. M

                                                                                                                                                                                                                                                                ~

90* Sector Areas 5-10 mile radius (cont'd) , S to WSW 18,850 5,210 5,500 95 25 70 160 min 210 min 120 min 240 min /4.0 hre 300 min 450 min 120 min 480 min /8.0 hrs Rural (3,850) (960) (1,000) (40) (10) (30) (160 min) (185 min) (80 min) (240 min) (300 min)(370 min)(120 min) (420'ain) Hishicot (1,500) (450) (500) (15) ( 5) (10) ( 40 min) ( 80 min) (40 min) ( 90 min) ( 60 min)(160 min)( 60 min) (170 min)

                  .,Two Rive.s (13,500) (3,800)                                                                          (4,000)        (40) (10)     (30)      (100 min) (210 min) (120 min) (240 min)            (150 min)(450 min)(120 min) (480 min)

SSE to SSW 15,350 4,265 4,500 70 20 50 120 min 210 min 120 min 240 min /4.0 hrs 200 min 450 min 120 min 480 min /8.0 bra Rural (1,850) (465) (500) (30) (10) (20) (120 min) (145 min) (60 min) (190 min) (200 min)(300 min)( 80 min) (330 min) Two Rivers (13,500) (3,800) (4,000) (40) (10) (30) (100 min) (210 min) (120 min) (240 min) (150 min)(450 min)(120 min) (480 min) Spscial Area Paint Beach i State Forest Est. Total Est. No. Carppounds Persons Campsites Vehicles F10 a.iles - 60 min ***/1 bc SSE to SSW up to 1,200 150 250 9 2 7** 90 min 135 min 60 min 150 min /2.5 krs 15 min 50 air 10 min

• Estimated maximum State Forest occupancy .,

                     ** State Forest Han8er and staff
                     *** Only about 100 persons and 30 vehicles maximum assumed to be in the State Forest during adverse weather conditions, e

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TABLE B ROADifAY CHARACTERISTICS Segment 4 No. of Lanesl Type 2 Capacity 3 Consnents 1 2 C 1,800 2 2 S 2,900 3 4 U 3,600

i. 4 2 C 2,800 5 2 C 2,800 l 6 2 C 2,300 Narrow Bridge

, 7 2 C 2,800

8 2 C 2,300 Narrow Bridge

! 9 2 C 2,800 i 10 2 C 2,800 ! 11 2 C 2,800 ,,x 12 2 C 2,800 i 13 2 .S 2,900 14 2 S 2,900 1 l 15 2 C 2,800 i 16 2 C 2,800 17 2 C 2,800 I j 18 2 S 2,800 19 2 C 2,800 $ 20 2 C 2,800 1 1 21 2 S 2,800 22 2 S 2,800 l 23 2 S 2,800 24 2 C 2,800 25 2 S 2,800 26 2 S 2,800 27 2 S 2,900 28 2 S 2,900 29 2 C 2,800 j- 30 2 C 2,800 31 2 C 2,800 f I 32 2 C 2,800 1

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             .                                                                                   TABLE B cont'd i

Segment 4 No. of LanesI Type 2 Capacity 3 Comments 33 2 C 2,800 34 2 C 2,800 35 2 C 2,800 36 2 C 2,800 37 2 C 2,800 38 2 S 2,900 39 2 C 2,800 40 2 S 2,800 41 2 S 2,800 42 2 C 2,800 43 2 C 2,800 44 2 S 2,900 r 45 2 S 2,900 l 46 2,800 2 C 47 2 C 2,800 48 2 C 2,800 49 2 C 2,800 50 4 U 3,600 Two Bridges 51 4 C 5,000 1 - Total number of through lanes in both directions 2 - S - State highway; 60 mph limiting C - County highway; 50 mph limiting U - Urban street 3 - Capacity assumes flow approaching unstable speeds _ to 35 mph 4 - See Figure 2 for segment locations o' im isi issi

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                                  '       #                 #                                         4                                                                        LEGEND SCALE IN MILES 000 -Nr.51 DENT POPULATION R ESIDENT POPULATION IN TH E VICIN ITY OF l

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I POINT BEACH NUCLEAR PLANT EMERGENCY PLAN INDEX NOTE: EP 6S3.7 = Emergency Plan Section 6.0 Subsection 3.7. A Section Accident EP2S2.1; see also Spectrum of Postulated Accidents Activation of Emergency Organisation EP6S2.0 Alert EP4SI.2 Assessment Actions EP2S2.3; EP6S3.0 Assessment Equipment Table 7-1 Assessment Facilities EP7S4.0; Table 7-1 1 E Classification System EP4Sl.0 Unusual Event EP4S1.1 Alert EP4Sl.2 Site Emergency EP4S1.3 General Emergency EP4Sl.4 Communication Systems EP7S3.0 Contamination Control Measures EP6S5.3 Plant Site EP6S5.3.1 Offsite Areas EP6S5.3.2 Control Room EP752.4 Corrective Actions EP2S2.7; EP654.0 E Damage Control & Repair EP6S4.2 Decontamination EP656.2 O

Paga 2 Section Department of Energy (DOE) EP5SS.2.3 Dose Plots Appendix B Dose Projections EP653.0 Drills EP8S3.2 Emergency EP2S2.9 Emergency Action Levels EP2S2.11; EP4S1.0 Emergency Exposure Criteria EP6S6.5 Emergency Director EP2S2.13; Appendix A Emergency Facilities EP7; Appendix A Energency News Center EP2S2.14; EP7S2.7 Emergency News Center Director EP2S2.15; Appendix A Emergency Notification EP5 Plant Personnel EP5S3.0; EP5S4.0 Offsite Agencies EP5S7.1 General Public EP5S7.2 Emergency Organization EP5S3.0; Figure 5-8 Emergency Plan Review & Updating EP8S4.0 Emergency Plan Implementing Procedures EP2S2.16; Appendix I Emergency Planning Zone EP2S2.17 Emergency Response Organization Appendix A ~ Equipment & Supplies EP8S5.0 Damage Control EP7S7.0 Equipment & Supplies List Appendix H Fire Equipment EP7S7.0 Onsite Protective Equipment & Supplies EP6S5.2

l fa = 1 1 Page 3 Section Evacuation EP6S5.1 1 Plant Site EP6S5.1.1 Offsite Areas EP6S5.1.2 Exclusion Area EP2S.20 Exercises EP8S3.2 4 1 E Facilities Assessment EP7S4.0 t i Emergency EP7 i

,                                    First Aid                                              EP7S6.0 I

Medical EP7S6.0 i ! Protective EP7SS.0 l First Aid l j Facilities EP7S6.0 Resources EP6S6.2 Fire Fighting Plant EP6S4.1 Two Creeks Volunteer Fire Department EP5S4.2.1 E General Emergency EP4S1.4 l E Hospitals See Medical Facilities l i l

Page 4 Section 1 Implementing Procedures See Emergency Plan Imple-menting Procedures Ingestion Exposure Pathway EP2S2.23 K

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Kewaunee County Nuclear Facility Incident Response Plan Appendix G Kewaunee Nuclear Plant EPSS4.2 L Letters of Agreement Appendix D Local Services Support EP5S4.2 Low Population Zone EP2S2.25 M

 -' )-  Manitowoc county Police                                  EP5S4.2 Nuclear Facility Incident Response Plan Appendix F Maps                                       Appendix C Medical Facilities                         EP5S4.2; EP756.0 Medical Transportation                     EP6S6.3 Medical Treatment                          EP6S6.4 Mutual Aid Agreements                      see Letters of Agreement (Appendix D)

N Nuclear Regulatory Commission (NRC) EP555.2

Page 5 Section Offsite EP2S2.26 Onsite EP2S2.27 Operations Support Center EP2S2.28; EP7S2.3 P Personnel Accountability EP6S5.1.1.e Plant Operations Manager EP2S2.30; Appendix A Plant Organization Figure 5-2 Normal EP5S2.0 Emergency EP5S3.0 Plume Exposure Pathway EP2S2.31 Police O Manitowoc County (Sheriff Department) EP5S4.2 Wisconsin State Patrol EP5S4.2 Protected Area EP2S2.34 Protective Actions EP2S2.35; EP655.1 Plant Site EP6S5.1.1; Table 6-2 Offsite Area EP6S5.1.2 Protective Action Guides EP2S2.36; Table 4-2 Protective Facilities EP7S5.0 R Radiological Emergency EP2S2.38 Radiological Monitoring Evacuees EP655.1.1.f Evironmental Table 6-1 Personnel EP656.1 l

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          -                                                                                                                      Section Recovery                                                                                            EP9 Relocation                                                                                          EP6SS.I.1.d S.
,                            Security Building                                                                                         EP7S2.5 Program                                                                                          EP6S5.1.1.c Sheltering                                                                                          EP6S5.1.2.a.1 Site Boundary Control Center                                                                        EP7S2.6 Site Emergency                                                                                       EP4Sl.3 Site Manager                                                                                         EP2S2.42; Appendix A Spectrum of Postulated Accidents                                                                     EP4S2.0 j                            Staging Area                                                                                         see Operations Support g                                                                                                                                Center State Agencies                                                                                       EP5S5.1

! State of Wisconsin Emergency Organizatinn & Support Agencies EP5S5.1 Peacetime Radiological Emergency Response Plan Appendix E l l j Supplies see Equipment & Supplies i ! T Technical Support Center EP2S2.43; EP7S2.2 Technical Support Manager EP2S2.44; Appendix A Training EP8S3.1 I l l l

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U_ i ! United States Coast Guard EP5S5.2

                                                                                                                                                                            .i Unusual Event                                                            EP4Sl.1                                                              1 I

l .! ! W t I i Water' Supply Utilities EP5S5.1.9 Wisconsin Electric Power Company j Emergency Organization EP554.1 i i Emergency Support EP5S4.1 , 1 I  ; I i f I i e l I

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