ML20112B545

Forwards Rev 4 to Util Generating Station Emergency Plan. Related Correspondence

ML20112B545
Person / Time
Site:	Braidwood
Issue date:	03/15/1985
From:	Gallo J COMMONWEALTH EDISON CO., ISHAM, LINCOLN & BEALE
To:	Brenner L, Callihan A, Cole R Atomic Safety and Licensing Board Panel
References
CON-#185-118 OL, NUDOCS 8503190234
Download: ML20112B545 (112)

Text

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BRANCH Lawrence Brenner, Esq., Chairman Dr. Richard F. Cole Administrative Law Judge - Administrative Law Judge Atomic Safety and Licensing Atomic Safety and Licensing Board Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission . Commission Washington, D.C. ,

20555 Washingto'n, D.C. 20555 Dr. A. Dixon Callihan Administrative Law Judge Union Carbide Corporation P. O. Box "Y" Oak Ridge, TN 37830 Re: In the Matter of Commonwealth Edison Company Units 1 and 2 (Braidwood Docket Nos. Nuclear 50-456 and Power Station, 50-457) -66

Dear Administrative Judges:

Two days ago (March, 13) I served on the Licensing Board and the parties a copy of the Braidwood Station Annex to the Commonwealth Edison Generating Stations Emergency Plan (GSEP).

Inasmuch as that document references and can be best understood in the context of the GSEP, a copy of the base volume of the GSEP is provided herewith. Please be advised that a proprietary telephone directory has been deleted from this copy of the GSEP.

Because of the bulk of the GSEP, only one copy is being served on one representative from each party.

Very truly yours, lldd Joseph Gallo One of the Attorneys for Commonwealth Edison Company JG/mg cc: Service List Enclosure

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9 Commonwealth Edison 6 Addre5S Redly to Post Office Box 767 72 West Adams $lreet CNcago khnois

• Chicago. Hlinois 60690

$ April,'1984 Revision 4 Policy statenent O

This document has been prepared to delineate the requirements and proceoures governing the Commonwealth Edison Company Nuclear Division Generating Stations Emergency Plan (GSEP). Implementation of the GSEP as covered by the Generic Plan and a Site Annex, including both corporate and site Emergency Plan Implementing Procedures (EPIPs), provides a degree of assurance that the number of achoc decisions made during an emergency are minimized. The 3 CSEP ensures that necessary equipment, supplies, and essential services are available to meet the needs of an emergency in order to provide for the health and safety of the public, including Commonwealth Edison employes, the limitation of camage to facilities and property, and the restoration of such facilities.

O Implementaticn of the GSEP provides for compliance with applicable requirements of the Nuclear Regulatory Commission, Federal Emergency Management Agency, States of Illinois, Iowa, Wisconsin and appropriate local governments, and their applicable emergency plans.

The Division Vice President & General Manager, Nuclear Stations, is O assigned the overall responsibility for implementation of the Generating Stations Emergency Plan. Authority and responsibility are assigned to the Technical Services Manager, Nuclear Services, for directing and administering the GSEP with respect to each nuclear generating station and for corporate personnel. Actual development, revisions and conceptual design of the generic GSEP, Site Annexes and EPIPs are responsibilities assigned to the Supervisor of g Emergency Planning.

The scope of the GSEP covers all nuclear generating stations both curing the licensing phase and during their operation.

O Wi tb d Qg/4 C. Reeo Cate vice Presicent Nuclear Operatiens

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Commonwealth Edison O Address Reply to- Post Office Boz 767 72 West Adams Street CNcago Enois _

Chicago. Ilhnois 60690 April,'1984 Revision 4 Policy Statenant

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This document has been prepared to delineate the requirements and procecures governing the Conmonwealth Edison Company Nuclear Division Generating Stations Emerger y Plan (GSEP). Implementation of the GSEP as covered by the Generic P1- and a Site Annex, including both corporate and site Emergency Plan Implementing Procecures (EPIPs), provides a degree of assurance that the number of adhoc decisions made during an emergency are minimized. The 3

GSEP ensures that necessary equipnent, supplies, and essential services are available to meet the needs of an emergency in order to provide for the health and safety of the public, including Commonwealth Edison employes, the limitation of damage to facilities and property, and the restoration of such facilities.

Implementation of the GSEP provides for compliance with applicable requirements of the Nuclear Regulatory Commission, Federal Emergency Management Agency, S*.ates of Illinois, Iowa, Wisconsin and appropriate local governments, and their applicable emergency plans. ,

The Division Vice President & General Manager, Nuclear Stations, is assigned the overall responsibility for implementation of the Generating Stations Emergency Plan. Authority and responsibility are assigned to the Technical Services Manager, Nuclear Services, for directing and administering the GSEP with respect to each nuclear generating station and for corporate personnel. Actual development, revisions and conceptual design of the generic GSEP, Site Annexes and EPIPs are responsibilities assigned to the Supervisor of

Emergency Planning.

The scope of the GSEP covers all nuclear generating stations bot" ouring the licensing phase and during their operation.

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C C. neec kb- Cate h%

vice President Nuclear Operatiens

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n April, 1984 1

Revision 4 Commonwealth Edison Company GENERATING STATION EMERGENCY PLAN (GSEP)

Reviewed by: I 6f

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Syfervisor of Emergency Planning Approved by: a Y [f

/ Date Technical Services Manager Authorized by: hi N )

• 5 Division Vice-President and Da';e I General Manager, Nuclear Stations Division

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July, 1984 Revision 4a GENERATING STATIONS EMERGENCY PLAN (GSEP)

TABLE OF CONTENTS

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Page Number Revision Policy Statement i 4 Signature Page 11 4

) Table of Contents 111 to V 4a l Site Specific Annexes vi 4 Listing of Acronyms vii to viii 4 Listing of Figures ix 4 Listing of Tables x to xi 4 f 1.0 SCOPE AND APPLICABILITY 1-1 to 1-2 4 2.0 DEFINITIONS 2-1 to 2-4 4 3.0 SUpWERY OF GENERATING STATION EMERGENCY PLAN (GSEP) 3-1 4

) 3.1 GSEP Organization 3-2 to 3-3 4 3.2 Classification of Emergencies 3-4 4 3.3 meergency Measures 3-5 4 i/, 3.4 Facilities and Equipment 3-6 to 3-7 4 3.5 Maintaining Emergency Preparedness 3-8 4 4.0 ORGANIZATIONAL CONTROL OF EMERGENCIES 4-1 4

) 4.1 Normal Plant Organization 4-2 to 4-5 4 4.2 Station Group 4-6 to 4-8 4 4-9 4a 4-10 to 4-20 4 3

4.3 offsite GSEP Organization 4-21 to 4-54 4 4.4 Non-c w alth Support Groups 4-55 to 4-56 4 4.5 Institute of Nuclear Power Operations 4-57 4 j 4.6 Participating Federal organizations 4-58 to 4-62 4 til

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' July. 1984 l Revision 4e TABLE OF CONTENTS (Continued)

Paee Number Revision 4.7 The State of Illinois 4-63 to 4-68 4

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4.8 The State of Iowa 4-69 to 4-70 4 4.9 The State of Wisconsin 4-71 to 4-72 4 4.10 American Nuclear Insurers (ANI) 4-73 to 4-74 4 6

5.0 CLASSIFICATION OF EMEGENCY CONDITIONE 5-1 to 5-12 4 5.1 Guidance for Down-Grading of Classification 5-13 4 5.2 Guidance for Termination of energency 5-14 to 5-15 4  :

6.0 EMERGENCY MASURES 6-1 4 6.1 Commonwealth Ehergency Response Actions 6-2 to 6-4 4 6-5 to 6-7 4a 6-8 to 6-19 4 6.2 Assessment Actions 6-20 to 6-21 4 6.3 Protective Actions for the offsite Public 6-22 4 6-23 to 6-26 4a l 6-27 to 6-32 4 I

6.4 Protective Actions for Onsite Personnel 6-33 to 6-35 4 6.5 Aid to Affected Onsite Personnel 6-36 to 6-39 4 ,

7.0 EMERGENCY FACILITIEE AND BQUIPMNT 7-1 4 i 7.1 asergency control Centers 7-1 to 7-5 4  !

7.2 Communication Systems 7-6 to 7-7 4 f l

j 7-8 4a i 7-9 to 7-12 4 '

7.3 Assessment Facilities 7-13 to 7-15 4 7.4 Protective Facilities and Equipment 7-16 4 f 7.5 First Aid and Medical Facilities 7-16 4 l

7.6 Damage Control Equipment and Supplies 7-17 4  !

7.7 Facilities and Equipment for Monitoring 7-17 to 7-20 4 i

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July, 1984 Revision 4a TABt.E OF CONTENTS (Continued)

Pace Number Revision 8.0 DEINTAINING EIERGENCY PREPAREDNESS 8-1 4

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8.1 Organizational Preparedness 8-1 to 8-3 4 8.2 Training 4-4 to 8-5 4 8.3 Exercises and Drills 8-6 to 8-8 4 8.4 Public Education and Information 8-9 4 8.5 Review and Updating of the GSEP and 8-10 to 8-11 4 Corresponding EPIPs

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8.6 Ehergency Equipment and Supplies 8-11 4 9.0 APPENDIX 9-1 4 9.1 Required Content of Site Specific Annexes 9-1 to 9-3 4 y 9.2 Required Content of Energency Plan 9-4 to 9-5 4 Implementing Procedures 9.3 Additional,Reergency Response / Notification 9-6 to 9-11 4 Requirements 9.4 References / Supporting Plans 9-12 to 9-14 4

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a April, 1984 Revision 4 SITE SPECIFIC ANNEXES A. Oresden Station Emergency Plan Annex

8. Quad Cities Station Emergency Plan Annex C. Zion Station Emergency Plan Annex D. LaSalle Station Emergency Plan Amex E. Byron Station Emergency Plan Amex F. Braidwood Station Emergency Plan Annex (Later)

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i April,1984 Revision 4 LISTING OF ACRONYMS A/E Architect / Engineer ALARA As Low As Reasonably Achievable ANI American Nuclear Insurers ASL8 Atomic Safety Licensing Board BEOF Backup Emergency Operations Facility BWR Boiling Water Reactor CCC Corporate Command Center CCP Community Command Post i CECO Commonwealth Edison Company CEOC County Emergency Operation Center CFR Code of Federal Regulations DEG Department of Emergency Government (Wisconsin)

DEQ Oepartment of Environmental Quality ONS Department of Nuclear Safety (Illinois) 00E Department of Energy EAL Emergency Action Level EBS Emergency Broadcast System l ECCS Emergency Core Cooling System ENC Emergency News Center l ENS Emergency Notification System (NRC)

EOC Emergency Operations (or Operating) Center

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EOF Emergency Operations Facility EPA Environmental Protection Agency EPIP Emergency Plan Implementing Procedure EPZ Emergency Planning Zone ERF Emergency Response Facility ERP Emergency Restoration of Power ESDA Emergency Services and Disaster Agency .(Illinois)

FBI FederaI Bureau of Investigation FEMA Federal Emergency Management Agency FDA Food and Drug Administration FRMAP Federal Radiological Monitoring and Assessment Plan FRPCC Federal Radiological Preparedness Coordinating Committee GSEP Generating Stations Emergency Plan

) IPN Health Physics Network (NRC)

INPO Institute of Nuclear Power Operations o IPRA Illinois Plan for Radiological Accidents IRAP Interagency Radiological Assistance Plan l' JPIC Joint Public Information Center KI Potassium Iodide LCEOC Local Government Emergency Operations Center MAELU Mutual Atomic Energy Liability Underwriters NARS Nuclear Accident Reporting System IMWAS National Warning System NCRP National Council on Radiation Protection NOL Nuclear Data Link POO Nuclear Outy Officer

' l NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System OBE Operating Basis Earthquake vil

April, 1984 Revision A LISTING OF ACRONYMS (Continued)  ;

00CS Offsite Dose Calculation System 00S Office of Disaster Services (Iowa)

OSC Operational Support Center i OSC On-Scene Coordinator (Coast-Guard)

PA Public Address l  ;

PAG Protective Action Guide P&ID Piping and Instrument Diagram PNS Prompt Notification System l Pressurized Water Reactor 1

PWR RAC Regional Advisory Committee RAFT Radiological Assistance Field Team RAP Radiological Assistance Plan REAC Radiological Emergency Assessment Center RF Radio Frequency SCP State Command Post SCRE Station Control Room Engineer '

SEOC State Emergency Operations Center SHL State Hygienic Laboratcry SPCC Spill Prevention Control and Countermeasure SPDS Safety Parameter Display System

,- SPSO System Power Supply Office N. SRC State Radiological Coordinator SRO Senior Reactor Operator (NRC Licensed)

SSC State Staging Center SSE Safe Shutdown Earthquake STA Shift Technical Advisor TLD Thermoluminescent Dosimeter TS Technical Specification TSC Technical Support Center WB Whole Body a

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July, 1984  !

Revision 4a  !

, LISTING OF FIGURES Page Figure 1.0-1 1-2 Commonwealth Edison Electric Service Territory i Figure 4.1-1 4-5 Normal Nuclear Elant Organization l Figure 4.2-1 4-8 GSEP Station Group Organization i Figure 4.2-2 4-9 Minimum Shift Manning Requirements for Nuclear Power Plant Beergencies Figure 4.2-3 4-10 Guidance for Augmentation of the Onsite Emergency 1

Organization within 60 minutes '

Figure 4.3-1 4-23 Limited Response Offsite GSEP Organization I Figure 4.3-2 4-26 Full Response Offsite GSEP Organization l Figure 4.7-1 4-68 IPRA Concept of Operations l Figure 5.1-1 5-15 Beergency Classifications Change Flow Chart Figure 6.1-1 6-4 to 6-7 Simplified Emergency Notification Scheme (A),

(B), (C) fr (D) l Figure 6.1-2 6-8 Sector and Zone Designators Figure 6.3-1 6-23 and 6-24 Actions from Control Room Indications and/or I i Plant Conditions - Initial MARS Notification l (

Figure 7.1-1 7-5 Ceaumonwealth Emergency Control Centers and .

Communications Flow '

Figure 7.2-1 7-8 Nuclear Accident Reporting System (MARS)

Figure 7.2-2 7-9 NARS Form Figure 7.2-3 7-10 Communications for en=marut and Control Figure 7.2-4 7-11 Environmental Assessment Cgaununications '

-( Figure 7.2-5 7-12 NRC Comununications i I

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April, 1984 Revision 4 LISTING DF TABLES Page l t

Table 4.2 4-11 Station Director (Plant Operations Manager)'

Table 4.2-2 4-12 Operations Director Table 4.2-3 4-13 Technical Director i Table 4.2-4 4-14 Maintenance Director Table 4.2-5 4-15 Stores Director t Table 4.2-6 4-16 Administrative Director Table 4.2-7 4-17 Security Director Table 4.2-8 4-18 Rad / Chem Director i Table 4.2-9 4-19 Operational Support Center Director Table 4.2 4-20 Shift Engineer Table 4.3-1 4-27 Recovery Marsger Table 4.3-2 4-28 Station Director (Plant Operations Manager)

Table 4.3-3 4-29 Advisory Support Director Table 4.3-4 4-30 Technical Support Manager Table 4.3-5 4-31 Environmental / Emergency Coordinator i; Table 4.3-6 4-32 Design & Construction Support Manager Table 4.3-7 4-33 Scheduling Planning Manager Table 4.3-8 4-34 Waste Systems / Radiation Control Manager Table 4.3-9 4-35 Administration / Logistics Manager

-( Table 4.3-10 4-36 Emergency News Center Director-

' '- J Table 4.'-ll Corporate Command Center Director

. 4-37 Table 4.3-12 4-38 System Power Dispatcher Table 4.3-13 4-39 Medical Director Table 4.3-14 4-40 Legal Consultant Table 4.3-15 4-41 Engineering Director Table 4.3-16 4-42 Intelligence Director Table 4.3-17 4-43 Health Physics Director Table 4.3-18, 4-44 Information Director Table 4.3-19 4-45 Environmental Director.

Table 4.3-20 4-46 Manpower / Logistics Director Table 4.3-21 4-47 Accounting Director Table 4.3-22 4-48 Communications Director Table 4.3-23 4-49 ERP Director "

Table 4.3-24 4-50 Division Director Table 4.3-25 4-51 Environs Director 1 Table 4.3-26 4-52 Training Director Table 4.3-27 4-53 Waste Systems Director Table 4.3-28 4-54 Access Control Director

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Table 5.D-1 5-2 Description of Transportation Accident Table 5.0-2 5-3 to 5-4 Description of Unusual Event

' Table'5.D-3 . 5-5 to 5-6 Description of Alert

. Table 5.0-4 5-7 to 5-8 Description of Site Emergency .

Table 5.D-5 5-9 Description of General Emergency X

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m April, 1984 Revision 4 LISTING OF TABLES (Continued)

Page Table 5.0-6 5-10 to 5-11 Description of Recovery Table 5.0-7 5-12 Emergency Action Levels for Radioactivity in Liquid Effluents Table 6.1-1 6-9 to 6-10 Commonwealth Actions for Transportation Accident Table 6.1-2 6-11 Commonwealth Actions for Unusual Event Table 6.1-3 6-12 to 6-13 Commonwealth Actions for Alert Table 6.1-4 6-14 to 6-15 Commonwealth Actions for Site Emergency Table 6.1-5 6-16 to 6-17 Commonwealth Actions for General Emergency Table 6.1-6 6-18 Commonwealth Actions for Recovery Table 6.1-7 6-19 Commonwealth Actions for Downgrading of Classification Table 6.3-1 6-26 Recommended Protective Actions for Gaseous Release Table 6.3-2 6-27 GSEP Guidelines for Protection Against Ingestion of Contamination for the Public Table 6.3-3 6-28 Summary of Possible Protective Actions to be Recommended or Implemented during an Emergency Table 7.7-1 7-18 to 7-19 Minimum Requirements for Emergency Monitoring Equipment for Each Nuclear Station

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April, 1984 Revision 4 GENERATING STATIONS EMERGENCY PLAN (GSEP) 1.0 SCOPE AND APPLICABILITY Comonwealth Edison Company (Commonwealth) provides electrical services to three million customers within a service area covering 11,525 square miles. Most of this territory is in northern Illinois and includes about one-fifth of the State. Refer to Figure 1.0-1. In providing its electrical service, Commonwealth is committed to the use of nuclear power and is licensed by the Nuclear Regulatory Commission (NRC) to operate several nuclear generating units within the State of Illinois.

In order to minimize the number of adhoc decisions made during an emergency and to ensure that necessary equipment, supplies, and essential services are available to meet the needs of an emergency, Commonwealth has developed the Generating Stations Emergency Plan (GSEP). The GSEP is an emergency plan applicable to all nuclear generating stations operated by Commonwealth and considers the consequences of radiological emergencies, as required by 10 CFR 50, Paragraph 50.47 and Appendix E. Additionally, the GSEP addresses the supplemental guidance provided by the NRC in the form of NUREG-0654/ FEMA-REP-1 (Revision 1, November, 1980). The GSEP also considers the consequences of nonradiological emergencies.

The GSEP provides for the protection of the health and safety of the public, Commonwealth employes, the limitation of damage to facilities and property, and the restoration of such facilities in the event of an emergency. Described in the GSEP is the emergency organization, including assignments of authority and responsibility. These GSEP guidelines provide for: identification and evaluation of emergency situations, protective measures, communications, coordination and notifications of governmental authorities, document review and control, emergency preparedness assessment, and training of all emergency personnel.

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April, 1984 Revision 4 2.0 OEFINITIONS 2.1 Assessment Actions '

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

'2.2 Dedicated Communications A communications link between two or more locations, access to which is limited to designated locations, and used only for the purpose intended. The communications link may be either telephone or radio.

2.3 Dose A general term denoting the quantity of radiation or energy absorbed.

2.4 Dose Commitment The radiation dose equivalent received by an exposed individual to the organ cited over a lifetime from a single event.

2.5 Dose Eaulvalent A quantity that expresses all radiation on a common scale for calculating the effective absorbed dose. It is defined as the product of the absorbed dose in rads and certain modifying factors. The unit of dose equivalent is the rem.

2.6 Drill A supervised instruction period aimed at testing, developing, and maintaining skills in a particular operation. A drill is often a component of an exercise.

2.7 Emeraency Action Levels (EAL)

Radiological dose rates, specific concentration levels of airborne, waterborne, or surface-deposited radioactive materials, or specific instrument indications that may be used as thresholds for initiating such specific emergency measures as designating a particular class of emergency, initiating a notification procecure, or initiating a particular protective action.

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April,1984 Revision 4 2.8 Emergency Personnel Those organizational groups that perform a functional role during an emergency condition. Within Commonwealth, emergency personnel include the directors of the GSEP organization, accident assessment personnel, radiological monitoring teams, fire brigades, first aid teams, and security personnel.

2.9 Emergency Plannina Zone (EPZ)

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

2.10 Essential Personnel Essential personnel are those needed to achieve the GSEP goals and tasks as deemed necessary by the CCC Director, Recovery Manager and/or Station Director. Identification of essential personnel is l

circumstance-oriented as determined by the Station Director and/or Recovery Manager.

Personnel identified as essential will vary with time, emergency classification, and circumstances at each generating station or emergency response facility.

2.11 Exercise An event that tests the integrated capability and a ma,jor portion of the basic elements existing within an emergency plan. An exercise usually involves participation of personnel from State and local governments, utility personnel, and may involve participation of Federal government personnel.

2.12 GSEP A document called the Generating Stations Emergency Plan that consists of two parts:

1) A generic plan that contains emergency planning information common to all Commonwealth nuclear stations; and

2) Site specific annexes that contain detailed emergency planning information unique to each nuclear station.

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April, 1984 Revision 4 2.13 Hazardous Material A substance or material which has been determined by the United '

States Secretary of Transportation to be capable of posing an unreasonable risk to health, safety, and property when transported in commerce, and which has been so designated in 49 CFR 172.

2.14 Imminent Ready to take place; an event that will happen in the near future. i The probability that an event will occur is projected to be 1004. .

2.15 Non-essential site personnel f i

Those personnel not needed for the continuing existence or [

functioning of the GSEP response organization. They are personnel not required to fill certain positions in the GSEP organization. ,

Identification of non-essential personnel is circumstance-orientated as determined by the Station Director, Recovery Manager and/or CCC Director. '

Examples of non-essential personnel might be:  !

- Non-station CECO personnel <

- Contractor personnel  !

- Vendor (Sales) personnel t

- Delivery persons '

- Public

- Non-emergency government personnel

- Non-emergency CECO personnel 2.16 Nuclear Station

" Nuclear Station" as used herein refers to Commonwealth Edison nuclear generating stations.

2.17 Offsite That area around a nuclear generating station which lies outside the "

station's " site boundary".

2.18 Onsite The area around a nuclear generating station which lies within the station's " site boundary".

2.19 Potential Existing in possibility; an event that may or may not occur; the probability that an event will occur is less than 50%.

2.20 Probable Supported by evidence strong enough to establish presumption but not proof; an event that is likely to occur; the probability that an event will occur is greater than or equal to 50%.

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April, 1984 Revision 4 2.21 Projected Dose That calculated dose commitment that some individuals in the population group may receive if no protective actions are implemented.

Projected doses are calculated to establish an upper limit boundary.

2.22 Protected Area l

That onsite area within the security boundary as defined in each {

station's Security Plan.

2.23 Protective Action Guides (PAG)

Projected radiological dose or dose commitment values to individuals in the general population that warrant protective action.

Protective Action Guidelines are criteria used to determine if the general population needs protective action regarding projected radiological doses, or from actual committed (measured) dose values.

2.24 Protective Actions Those emergency measures taken for the purpose of preventing or

, minimizing radiological exposures to affected population groups.

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

2.26 Thyroid Blockino Acent -

An agent which when properly administered to an individual will result in sufficient accumulation of stable iodine in the thyroid to prevent significant uptake of radiolodine. Potassium Iodine is such an agent.

2.27 Worst Case Meteorolooy Atmospheric dispersion conditions which are expected to occur only 5% of the time, i.e., conditions should be more favorable 95% of the time.

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April, 1984 -

Revision 4 3.0 SlM4ARY OF ENERATING STATION EMERGENCY PLAN (GSEP)

The Division Vice-President and General Manager, Nuclear Stations, is l -

responsible for the safe and reliable operation and maintenance of nuclear  ;

generating stations within Commonwealth Edison. This individual reports to '

tne Vice-President Nuclear Operations and has line responsibility for the l administration, management, and direction of all Nuclear Stations Division

activities at operating nuclear stations. The Division Vice-President and General Manager, Nuclear Stations, is also responsible for radiological i emergency planning within Commonwealth Edison.

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The Generating Stations Emergency Plan (GSEP) is a written emergency plan that establishes the concepts, evaluation and assessment criteria, and protective actions that are necessary in order to limit and mitigate the consequences of potential or actual radiological emergencies. The GSEP ,

provides the necessary prearrangements, directions, and organization so that all nuclear emergencies can be effectively and efficiently resolved in order i

to safeguard station personnel, property, and the general' public.

The GSEP consists of two parts, a generic plan applicable to all generating stations, and a site specific annex for each nuclear generating '

station containing information and guidance that is unique to a particular station.

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April, 1984 Revision 4 l

3.1 GSEP Oroanization -

The GSEP organization consists of directors and staff personnel who shall ensure timely activation and implementation of emergency responses. The GSEP organization can be divided into two functional areas: onsite and offsite.

3.1.1 Onsite Emeroency Oroanization The onsite GSEP organization consists of a Station Group that i is primarily concerned with emergency response efforts necessary to cont:U1 the plant during an incident.

The Station Group functions under a Station Director for organizing cod coordinating the emergency efforts at and within the immediate vicinity of the station. Collectively, members of the j

Station emergency:

Group pmvide for the following activities curing an l

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1) Plant systems operations i

, 2) Radiological survey and monitoring

! 3) Firefighting L

l 4) Rescue operations

5) First aid

6) Decontamination

7) Security of plant and access control

8) Repair and damage control

9) Personnel accountability

10) Record Keeping

11) Communications The responsibility for initial assessment of and response to an emergency rests with the Shift Engineer. The Shift Engineer is the initial Station Director and has the Station Director's responsibilities and authority until relieved of thase responsibilities by the designated Station Director or his alternate (See Section 4.2). The Station Director is responsible for making the initial determination of the severity of the emergency and for activation of the GSEP as appropriate in accordance with the guidance provided in the generic GSEP, the site specific annex, and the station's implementing procedures.

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April, 1984 Revision 4 3.1.2 Offsite Emeroency Oraanization

. The offsite GSEP organization consists of corporate and division personnel. This offsite organization is supported by l envirt wental assessment staff and monitoring teams that provide l

t long 'sta support to the affected station. These organizations cons;.t of a Corporate Command Center Group and/or an Emergency

, Opericions Facility Recovery Group. This Offsite GSEP organization also have liaison responsibilities - with Federal, State, and local authorities.

During the less serious emergencies, the GSEP Corporate Command Center Group is responsible for evaluating, coordinating, and directing the overall company activities involved in coping with the emergency. The Corporate Command Center Group functions under a Director and its responsibilities include command and control, intelligence, logistics, engineering support, medical care, manpower requirements, communications, accounting, legal, health physics, environmental, and news information. I Ouring the more serious emergencies the GSEP Recovery Group at the affected station's Emergency Operations Facility (EOF) is j

lg responsible for evaluating, coordinating and directing the overall company activities both at. the Corporate Command Center and j Technical Support Center. Once the Recovery Group is activated, the CCC Gro @ becomes a s@ port staff. (See Section 4.3).

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April,1984 Revision 4 3.2 Classification of Emergencies The GSEP provides for classification of emergencies into six (6) categories. The first category, Transportation Accident, concerns an emergency involving the transportation of radioactive or other hazardous material from a generating station. The next four (4) categories:

Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency address emergencies of increasing severity (See Section 5.0).

The sixth category is Recovery: that period when the emergency phase is over and activities are being taken to return the situation to a normal state (acceptable condition). Herein, Notification of Unusual Event will be referred to as Unusual Event, and Site Area Emergency will be referred to as Site Emeraency.

An emergency condition may be classified for purposes of reporting to offsite agencies, by the following persons:

1. Shift Engineer or alternate in line of succession as defined i i

in Section 4.2 while acting as the initial Station Director;  !

2. Station Director while in the Control Room or TSC until the  !

Corporate Command Center Director or Recovery Manager l assumes responsibility for the emergency situation, j

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3. Corporate Command Center Director'while at the CCC until the  ;

Recovery Manager assumes responsibility for the emergency '

situation.  !

4. Recovery Manager while at the EOF or other emergency i response facility l i

Following an event classification (reference Section 5.0), the t emergency measures described in Section 6.0 shall be taken if not already i underway. The. Initial notification of cognizant offsite government I agencies shall be made within fifteen (15) minutes of classification or  :

reclassification of the event. Regarding rapidly developing emergency l conditions, classification or reclassifications by the (Acting) Station Director may be made with consultation with the designated CCC Director  :

or Recovery Manager, as appropriate. Nevertheless this ;

decision / consulting time shall be used expeditiously to prevent, l excessive delay between occurrence of the event and declaration of the classification or change.

Regardless of who makes the classification, the time spent in consultation with technical advisors, governmental agencies, administrative assistants, or any other support personnel supplying information to the decision maker prior to making the classification  ;

decision IS NOT included in the fifteen (15) minute time requirement for notification.

i Emergency Action Levels (EAL's) are for unplanned events.

Controlled activities designed to test systems and equipment that create an EAL are not subject to GSEP reporting and activation requirements as long as the test proceeds as planned. This condition may be subject to .

the reporting requirements of 10CFR50.72 effective January 1, 1984 ,

3-4 l

April,1984 Revision 4 3.3 Emeraency Measures Emergency measures to be taken for each class / category of emergency l

are identified in the GSEP. Emergency measures begin with activation of the emergency organization. Subsequent measures are generally organized into assessment actions, corrective actions, protective actions, and aid to affected persons (See Section 6.0).

3-5

April,1984 Revision 4 3.4 Facilities and Equipment  !

The GSEP identifies onsite and offsite facilities available for emergency assessment, communications, first aid and medical care, and damage control. Of particular importance are the emergency support centers: the Technical Support Center (TSC), the Operational Support Center (OSC), the Corporate Command Center (CCC) and the Emergency Operations Facility (EOF) and appropriate Backup Emergency Operations Facility. (BEOF) (Refer to Section 7.0).

3.4.1 Technical Support Center (TSC) l The Technical Support Center (TSC) is the onsite location l utilized by plant management, technical, and engineering support personnel to support the Control Room command and control flinction, for assessment of plant status and potential offsite impac'., and for inplementation of emergency actions.

3.4.2 Operation Support Center (OSC) l The Operational Support Center (OSC) is the onsite location l where support personnel will report to during an emergency and where they will be dispatched for assignment or duties in support of emergency operations.

4 3.4.3 Corporate Command Center (CCC) l The Corporate Command Center (CCC), located at 72 West l Adams, Chicago, is the location where the Corporate Command Center Director will normally direct a staff in evaluating, coordinating, and directing the overall company activities involved with an emergency. If the Recovery Group is activated at the ECF, then the l CCC will be the location for a support staff reporting to the Recovery Group.

If the EOF facility for the station is declared to be inoperative then the CCC facility and organization may be designated by the appropriate CECO officials as the location and where overall company emergency response activities will be directed.

3-6

i l

l April, 1984 Revision 4 3.4.4 Emeroency Operations Facility (EOF) l The Emergency Operations Facility (EOF) that is located near the station provides for the management of overall emergency response, coordination of radiological assessments, and management ,

of recovery operations. The organizations at this EOF function '

under a Recovery Manager and are activated for all Site and General Emergency situations. Activation of any EOF for other emergency situations is optional per the directions of CECO Station Director /CCC Director or Recovery Manager. I All EOF's are physically designed to function in a similar manner regarding voice communication and data transmission. Thus each EOF may be used as a back-up for an inoperative EOF.

3.4.5 Back-up Emeroency Goerations Facility (BEOF) l The Zion Back-up EOF, a facility located approximately 15 '

miles from the Zion plant in a portion of the Lake County Emergency Operations Center, provides the functions of the EOF if evacuation of personnel from the Zion EOF is required. Only Zion Nuclear Power Station has a back-up EOF.

Relocation from the Zion EOF to the Zion 8 EOF is determined by the Recovery Manager at the Zion EOF. The Recovery Manager determines the essential personnel to be relocated to the BEOF and the staging- area to which the rammining personnel (non-essential) are to be relocated.

a r

1 3-7

April, 1984 Revision 4 3.5 Maintainino Emeraency Preparedness '

The GSEP describes the means to ensure that this plan will continue to be effective throughout the lifetimes of Commonwealth nuclear stations. Emergency preparedness includes training, exercises and drills, review and updating of the GSEP and procedures, as well as the administration of public information programs (See Section 8.0).

D 9

3-8

' April,1984 Revision 4 4.0 ORGANIZATIONAL CONTROL OF EMERENCIES

, Emergency planning must consider the capabilities of the normal plant organization, the onsite and offsite emergency organizations of Commonwealth Edison, and the offsite non-Commonwealth Edison emergency response agencies.

The initial phases of an emergency situation at a nuclear station shall involve a relatively small number of individuals. These individuals must be capable of: (1) determining that an emergency exists; (2) providing initial classification and assessment; and (3) progtly notifying other groups and individuals in the emergency organization. The subsequent phases of the emergency situation may require an increasing augmentation to the emergency organization. ,

4-1

April,1984 Revision 4 4.1 Normal Plant Organization The normal plant organization is basically the same for all

) Commonwealth nuclear stations and is depicted in Figure 4.1-1.

4.1.1 Station Superintendent Each Commonwealth nuclear station is managed by a Station Superintendent who is responsible for management of the station, l including Industrial Relations, planning, coordination, direction of the operation, maintenance, refueling, and technical activities.

The Station Superintendent is responsible for compliance with the station NRC operating license, government regulations, ASME Code requirements, and the Commonwealth Quality Assurance Program. He also authorizes the use of procedures contained in the station procedures manuals and is responsible for final approval and distribution, and retention of documentation of station reports. l The Station Superintendent authorizes all modifications to the station after the issuance of an Operating License and completion of preoperational testing. He forwards requests for modifications to the Commonwealth Edison Station Nuclear Engineering Department. The Superintendent supervises the Station's onsite review function as provided in the station Technical Specifications.

Ouring an emergency situation, the Station Superintendent normally acts as the GSEP Station Group Director.

4.1.2 Succession of Authority The Station Superintendent has overall responsibility for station operation. During periods when the Superintendent is unavailable, this responsiblity is designated to alternates who satisfy the requirements of ANSI N18.1-1971, " Experience Requirements for Plant Manager."

l 4-2

April, 1984 4.1.3 Shift Enoineer Revision 4 plant in compliance with the station NRC operating station operating procedures. j lice is in charge of the entire plant operation and is responsible forDu the plant being operated in a safe and reliable condition.

receives direction from the Operating Assistant Superintendent. The He authority and responsibility of the operating shift engineer / foremen and shift crews include:

1) The reactor operator's authority and responsibility for shutting down the reactor when he determines that the safety of the reactor is in jeopardy or when operating parameters exceed any of the reactor protection circuit setpoints and automatic shutdown does not occur; 2)

The responsibility to determine the circumstance, cause, and limits under which operations can safely proceed before the reactor is returned to power followin or an unscheduled or unexplained power reduction; g a trip 3)

The Shift Engineer's responsibility to be present at the '

plant and to provide direction for returning the reactor l to power following a trip or an unscheduled or unexplained power reduction;

4) The responsibility to adhere to the station Technical Specifications;'

5) The responsibility to review zoutine operating data to assure safe operation; and

6) The responsibility to adhere to plant operating pIccedures and the requirements for their use (However, during an emergency, operations personnel are authorized to depart from approved l procedures where necessary to prevent damage to injury to personnel, including the public, or the facility).

A Shift Engineer is on duty 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day and is the initial GSEP Station Director. While serving in this capacity the Shift Engineer has the authority for deciating an emergency and recommending pIntective actions to State authorities (Reference Section 6.3.1 and Figure 6.3-1 (a) & (b)).

l 4-3

r I

l l

l April, 1984 Revision 4 -

4.1.4 Station Control Room Enoineer (SCRE)

Aovisor (5TA)

Snift Technical the During normal plant operation the SCRE/STA, who reports to Shift Engineer, directly supervises the licensed Reactors Operators and all activities in the control room. During an abnormal. event of sufficient seriousness to require detached technical assesament, of personnel and .the Shift Engineer assumes direct supervision all activities in the control room while the SDIE/STA steps back and assumes a role of overview as an STA with l the specific responsibility of monitoring the maintenance of core cooling and containment integrity.

4.1.5 Minimum Shaft Mannino times All to Commonwealth nuclear stations have the capability at all perform detection, classification, acx3 notification functkns required in the early phases of an emergency. Minimum shift manning Figure 4.2-2.

at each nuclear generating station is soecified in l Specification. and in accordance with each station's Technical l l 4.1.6 Health Physics Oroanization physicsThe Station program Red / Chem Supervisor is responsible for the health and meterials. Included for in handling and annitoring of radioactive this organization are health physicists, chemists, foremen, and technicians.

6 i

l 4-4

( FIGURE 4.1-1 NORMAL NUCLEAR PLANT ORGANIZATION STATION i

SUPERINTENDENT I

I I I I -

ADMINISTRATIVE S OPERATING MAINTENANCE PERSomenEL SUPPORT SERVICES = ASSISTANT ASSISTANT -

ADMINISTRATOR ASSISTANT SUPERINTENDENT SUPERINTENDENT SUPERINTENDENT l I I I TRAINING OUALITY OPERATiteG MASTER MASTER MASTER SUPERVISOR OFFICE CONTROL EneGlesEERS ELECTRICIAN lhSTRUMENT MECHANIC YI StPERVISOR E MECHANIC I u -

a I TECH STAFF RAD-CHEM SHIFT SUPERVISOR SUPERylSOR ENGINEERS

• FEM Nm ON-SHE REVIEW A telVESTIGATIVE l

• FUNCil0N STAT 40ef SCRE

, STORES -

== SECURITY .

SUPERVISOR

,,,,I A0MiNiSTRAr0R -

ADellNISTRATIVE F N .

= = = = = = FUteCTIONAL g gg

. . . . . . . . , IMERENCY CONDIT1001 .....,, SHIFT TECHellCAL ,g OPERATORS ADVISOR

• THIS TA8tE IS DERIVED FROM lelFORMATION CONTAINED IN THE C0tus0NWEALTH EDIS001 COMPANY QUALITY ASSURA4eCE MANUAL.

ANY CHANGES IN THAT MA460AL WILL SUPERSEDE l# FORMAT 10ll CoelTAlleED IN THIS GSEP.

f April, 1984 Revision 4 4.2 station Grous The ossP station Group is the onsite emergency organization which is activated during an emergency. The station Group functions under a station Director responsible for carrying out all onsite emergency efforts as well as for carrying out the commonwealth initial offsite environs monitoring efforts which are necessary for assessing plant releases. A diagram of the osar station Group organization is shown in Figure 4.2-1.

The shif t sngineer, as initial station Director, will take ismediate action during an emergency and will activate the OssP station Group as appropriate. In the shif t sngineer's absence or incapacitation, the line of succession is:

1) shift Forement

2) station control noom Engineer;

3) Nuclear station operator. (senior experience personnel)

The shift Engineer, or his alternate, may be relieved of the station Director position of responsibility when it is assumed by the designated s

station Director or the station Director's alternate.

An individual assigned the duty as a station Control Room Engineer (sCRs) shall be available to the control Room at all times, unless relieved by responsible individuals. It is the responsibility of the SCRs/sTA to diagnose off-normal events and advise the operating shif t accordingly.

NUROG-0454 Criterion II.s.S states that the " licensee must be able to supent on-shift capabilities within a short period af ter declaration of an emergency." It further defines that short period as 30 and 60 minutes. Commonwealth Edison corporate management, including the NRC as stated in the October 24, 1981 letter of W. J. Dircks, NRC Executive Director for operations to Dr. D. F. Knuth, President of IGIC, Inc.,

agrees that the time frames for rapid augmentation of a nuclear power plant staff in the event of an emergency are not rigid inviolate requirements but rather goals. It is Commonwealth Edison's intent to expend its best efforts to meet the augmentation criteria (goals) regarding manning station fact 11 ties with sufficient skilled individuals capable of handling an emergency. Both the NRC and Commonwealth Edison realize that due to diversity of normal residential patterns for the stations' staff, possible adverse weather conditions, and road congestion, these time frames might be exceeded.

4-6

April, 1984 Revision 4 i Commonwealth Edison has established a 24-Hour duty-call indivicual i at each station entitled "the Station Outy Officer" who will be rutified '

first after the Shift Engineer has declarea a GSEP emergency. This '

Station Outy Officer will initiate a prioritized notification (call-list) procedure. The procedure identifies individuals wro are capable of .

fulfilling the specific response functions which are listed in GSEP Figure 4.2-3, " Guidance for Augmentation of the Onsite Emergency Organization Within 60 Minutes". GSEP Figure 4.2-3 was developed based on the functions listed in Table 8-1 of NUREG-0654. The call-list procedures are prioritized considering least travel time of station staff.

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

The major responsibilities and duties of the Station Group directors are given in the following tables:

1) Table 4.2.1 - Station Director (Plant Operations Manager)* l

2) Table 4.2 Operations Director;

3) Table 4.2 Technical Director;

4) Table 4.2 Maintenance Director;

5) Table 4.2 Stores Director;

6) Table 4.2 Administrative 01 rector;

7) Table 4.2 Security Director;

8) Table 4.2 Rad / Chem Director; '

9) Table 4.2 Operational Support Center Director.

10) Table 4.2 Shift Engineer In addition to the onsite emergency organization (Station Group),

the station's resources are augmented by the offsite GSEP organization and non-Commonwealth support groups.

The designation is to be consistent with INPO guidelines, however this " Plant Operations Manager" title will not be used within the GSEP.

4-7

FIGURE 4.2-1 GSEP STATION GROUP ORGANIZATION STATION DIRECTOR -

(Plant Operatises Manager) 1 I I I OPERATIONS TECHNICAL MAINTENANCE STORES DIRECTOR DIRECTOR DIRECTOR DIRECTOR I I I I STAFF STAFF STAFF STAFF SHIFT EleGlieEER mw I I I EE

• O0 OSC DIRECTOR ADMINISTRATIVE DIRECTOR SECURITY RAD - CHEM [w DIRECTOR D! RECTOR

• h 1 I I STAFF STAFF STAFF

• OSC Director reports to Ogerations Supgsort Center

July, 19g4 Revision 4e FIOURg 4.2-2 MINIMUM SHIFT MAtefING REQUIREMENTS FOR NUCLEAR POWER PLANT EMERGENCIES Number of Units Operating (e) (f) '

(Single Control Room)

One Two Shift Engineer 1 (f) 1 (f)

Shift Foreman (c) 1 (f) 1 (f)

Nuclear Station Operator 2 (f) 3 (f)

Squipment Operator / Attendant (c) 3 (f) 4 (f)

Red /Chen Technicians 2 (f) 2 (f) shift Tect.nical Advisor (d) 1 (f) 1 (f)

Radweste Operators (c) 1 (b) (f) 1 (b) (f) meergency coordinator / 1 (b) (f) 1 (b) (f)

Station Director Notificetlon/Communicatlon 1 (b) 1 (b)

( Rescue Operations /First Aid 2 (b) 2 (b)

TOTA 1. 10 (f) (g) 12 (f) (g)

Minimum (a) 9 (f) (g) 11 (f) (g)

Notes (a) The minimum number refers only to the case of shift shortage caused by a sudden sickness or home emergency.

(b) May be provided by shift personnel assigned other functions.

(c) These personnel are capable of performing emergency electrical, instrument or mechanical corrective actions and temporary repairs.

(d) STA function is accomplished at each generating station by the Station Control Room Engineer (SCRE) who performs line duties during normal operation, but assumes an STA advisory position during an emergency.

(e) Manning requirements do not consider Dresden Unit #1 which is in an estended outage and whose return to service date is indefinite.

(f) sach station Technical specifications govern the number of persons in these positions if greater than the specified number.

(g) The totals do not include positions affected by footnote (b).

4-9

April,1984 Revision 4 FIGURE 4.2-3

• GUIDANCE FOR AUGMENTATION OF THE ONSITE EMERGENCY ORGANIZATION WITHIN 60 MINUTES Auomentation within 60 Minutes Functional Area Unusual Event Alert Site & General Emergency

1. Comend & Control Notification Only Station Director 1 1 1 Oper. Director 1 1 1 Maint. Director *1 1 1 Tech Director +1 1 1 Admin. Director *1 *1 1 Stores Director *1 +1 1 Rad-Chem Director *1 1 1 Security Director +1 *1 1 OSC Director *1 1 1 l Environs Director *1 1 1

2. Notifications &

( Communications 1 1 Accident Assessment Offsite *2 4 Onsite *1 1 In-Plant *1 1 Rad / Chem (Lab) *1 1

4. Technical Support Nuclear (Core) *1 1 Electrical *1 1 Mechanical *1 1

5. Repair & Correction Mechanical *1 1 Electrical *1 1 Radweste *1 1 Inst. & Control *1 1

6. Protective Actions Radiation Protection *2 4

• 2-10 *8-25 29

*As needed depencing upon the nature of the emergency NOTE: Additional support in the areas of Command & Control; Communications; and Accident Assessment will be available from the offsite GSEP organization. It is reasonable to expect partial manning of the CCC or EOF within 60 minutes for the Site & General Emergencies.

4-10

April, 1984 Revision 4 TABLE 4.2-1 STATION DIRECTOR l The Station Director reports to the Corporate Command Center Director. He supervises and directs the GSEP Station Group in organizing and coordinatin activities)g onsite

. If theemergency Recovery Gro@effortsis(as well as at activated directing all other the EOF, plant the Station Director; will report to the Recovery Manager at the EOF but will not relocate from the TSC to the EOF.

The Station Director is responsible for performing the following l functions:

o Classify emergencies in accordance with Section 5.0 of this plan.

o Ensure that notifications are made as outlined in Section 6.0.

(System Pbwer Dispatcher, NRC, and State / local agencies in a General Emergency).

o Activate the GSEP Station Group as outlined by Figure 4.2 3 of this plan o Notify local support agencies, including ambulance service,._ as.

required in order to expedite their response to the emergency.

o Provide for an assembly and evacuation of nonessential personnel from the site for a Site and Ceneral- Emergency, or when other .

conditions warrant (refer to Section 6.4).

o Keep the CCC Director, Recovery Manager, and Nuclear Regulatory l Commission informed as to the status of the plant as determined by the station staff.

o Request from the offsite GSEP organization, additional material, manpower, and equipment as1necessary to perform decontamination, repair, and restoration work, o Ensure adequate manning and access control of the TSC when activated.

o Implement emergency and recovery efforts as directed by the Corporate Command Center Director / Recovery Manager, o If the emergency involves a hazardous substance and/or oil discharges (per the Spill Prevention Control Countermeasure Plan),

ensure that the appropriate notifications and responses have been made (Additional information is given in Section 9.3).

o Maintain a record of the GSEP related activities.

4-11 r

ed April,1984 Revision 4 TABLE 4.2-2  ;

OPERATIONS DIRECTOR initiates The Operations Director determines the extent of station emergencies, corrective actions, and implements protective actions for onsite personnel. Specifically, the Operations Director shall: I '

o Verify that the System Power Dispatcher and the Station Stperintendent have been notified of an emergency.

o Direct a staff in determining the nature and extent of emergencies pertaining to equipment and plant facilities. .

o Initiate immediate emergency. corrective actions to limit or contain the o

Direct switching and valving operations, equipment operations, equipment checking, and miscellaneous operations as required.

o Implement protective actions for onsita personnel, to include site assembly and evacuation (when ordered by the Station Director).

o Organize and direct rescue operations of injured personnel.

Verify that ambulance- services have been notified, as required.

Coordinate the transfer of injured personnel offsite.

o Ensure adequate manning of the OSC if not already occupied and Control Room. Designate an individual as the OSC Director and have the individual report to the Shift Engineer.

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

o Maintain a record of the GSEP related activities.

9 4-12

April,1984 Revision 4 TABLE 4.2-3 TEClf4ICAL DIRECTOR TheofTechnical assesments station Director directs a staff in performing technical emergencies and assists in recovery planning.

Specifically,. the Technical Director shall:

l o

Accunulate, tabulate, and evaluate data on plant conditions such as plant operating data and inspection reports.

o Evaluate vital plant parameters during an emergency to determine the overall fission condition product barriers,of safety related systems, the core, and o Identify critical data points and control parameters that the Operations staff should monitor.

o Identify special procedures needed to effect recovery.

o Supervise the total onsite technical staff effort. Acquire sufficient technical personnel to provide assistance during the

( stabilization and restoration phases.

o Assist matters, the Rad / Chem Director for onsite radiological / technical o

Maintain a record of the GSEP related activities.

I 4-13'

s April,1984

. Revision 4 TABLE 4.2-4 MAINTENANCE DIRECTOR The Maintenance Director directs a staff in providing labor, tools, protective equipment, and parts needed for emergency repair, damage control, i and recovery efforts to return the plant to its pre-accident status. 1 Specifically, the Maintenance Director shall: l o Direct the total onsite maintenance and equipment restoration effort.

o Request additional equipment through the GSEP organization in order to expedite recovery and restoration. Equipment such as trucks, cranes, or pumps may be required.

o Assist in rescue operations by providing labor, tools, and equipment.

o Identify required steps or procedures that need to be written or  !

implemented in support of recovery efforts. I

, o Maintain a record of the GSEP related activities.

b 4-14

f L

April,1984 TABLE 4.2-5  !

STORES DIRECTOR i The Stores Director directs- a staff in obtaining and delivering all  !

parts, protective equipment, and materials needed in recovery operations.

Specifically, the Stores Director shall:

l o Identify what materials and supplies are available onsite and  ;

time frames for delivery of other materials and supplies from '

offsite.

o Expedite delivery of needed materials from offsite.

o Inventory required emergency materials so that necessary supplies  ;

are not depleted and uninterrupted work can continue.

I o Provide adequate respiratory equipment and protective clothing to emergency personnel, o Maintain a record of the GSEP related activities. I f

a t

i I I

e 4

4-15 w wv--o . -.* .- y -- . , --._, , , . . y = .. -.,..=,y,w g- ,_,,.- ,. .-_c w.p-9.w9,. popww,

4 April,1984 Revision 4 TABLE 4.2-6

~

ADMINISTRATIVE DIRECTOR The Administrative Director provides administrative services in support of emergency / recovery operations. Specifically, the Administrative Director shall:

l o Direct a staff in preparation of emergency procedures and interim reports during an emergency.

o Coordinate recordkeeping efforts at the Station.

o Assist the Station Director in arranging for shift reliefs and continual maming of the station.

o Arrange for food and sleeping facilities for onsite emergency workers.

o Arrange for clerical staff at the EOF.

o Maintain a record of the GSEP related activities.

9 4-16 f

-- , , ---e-e .n., -- -----g-, - , , , - . , , , . , .- - - - - ., - - . - , ----,--g , . . - - - ,

4 April,1984 Revision 4 TABLE 4.2-7 SECURITY DIRECTOR The Security Director maintains plant security and personnel accountability at the nuclear station. Specifically, the Security Director shall: l o Maintain plant security and account for all personnel within the protected area. In the event of an onsite assembly of all persomel, Security Director shall account for all individuals l within the protected area at the time that the assembly was announced and should be able to as;ertain the names of missing individuals within 30 minutes.

o Identify to the Station Director any non-routine security procedures and/or contingencies that are in effect or that require a response.

o Coordinate with Rad / Chem Director in controlling ingress and egress to and from the protected. area if radiological concerns are present, o Initiate security at the EOF 'if it is requested by the Co'rporate Command Center Director or the Station Director. It shall be the responsibility of the Security Director to implement Commonwealth Edison Corporate Nuclear Security Administrator's Call Out list when the Security Director determines the potential for EOF activation. This list identifies the Access Control Director for the EOF.

o Maintain a record of the GSEP related activities.

4-17

April,1984 Revision 4 TABLE 4.2-8 l

RAD /CFEM DIRECTOR The Rad / Chem Director directs a staff in determining the extent and nature of radiological or hazardous material problems onsite (and initially  :

offsite). Specifically, the Rad / Chem Director shall: l o Accumulate, tabulate, and evaluate data on plant conditions such l as meteorological and radiological monitoring readings, hazardous material surveys, and other pertinent data.

o Ensure use of protective clothing, respiratory protection, and access control within the plant as deemed appropriate to control persomel exposures. ,

o Ensure that appropriate bicassay procedures have been implemented r for onsite persomel when a radioactivity incident has occurred.

o Ensure that personnel are decontaminated, if necessary.  !

o Assist in planning rescue operations and provide monitoring

, services as required for hazardous material accidents.

Set up, as appropriate, a group qualified to receive contaminated o

and injured persomel and perform first aid duties.

o Assist.in the transfer of injured snd non-essential personnel, o Decide which of the predetermined personnel evacuation routes is to be used when deemed necessary.

o Request through the offsite GSEP organization the following as necessary:

Additional or special personnel monitoring devices i (TLDs, whole body counters, etc.)

-- Engineering evaluations of temporary shielding or special equipment and tools. ~

Aoditional health physics support personnel.

Additional instrumentation and equipment, as required.

o Cooroinate initial offsite monitoring efforts until such activities can be directed by a designated Environs Director.

o Maintain a record of the GSEP related activities.

4-18

1 April, 1984 Revision 4 TABLE 4.2-9 OPERATIONAL SUPPORT CENTER DIRECTOR Upon activation of the station's Operational Support Center (OSC) the Operations Director shall designate an individual to become the OSC Director ,

if not already designated by the Shift Engineer. The OSC Director is located j in the OSC to manage and supervise the activities of personnel reporting to -

the OSC as directed by the Shift Engineer.  ! -

Personnel who may report to the OSC include but are not limited to:

o Operating personnel not assigned to the Control Room; -

I o Radwaste personnel. I o Rad / Chem Technicians.  !

o Maintenance personnel.  !

Specifically the OSC Director shall:

o Receive messages from the Shift Engineer or Operations Director.

o Assign tasks to individuals in the OSC with approval of the Shift  !

Engineer.

o Maintain OSC resources including manpower, material, and equipment, f a Maintain accumulated exposure records for personnel working from the i

OSC and report these values to the Rad / Chem Director after each shift.

o Maintain records of GSEP related activites.

4-19

• 4

)

April, 1984 Revision 4 TABLE 4.2-10 SHIFT ENGINEER o

! Thespecified as Shift Engineer in Tableacts as Station Director and shall perform the duties 4.2-1.

O The Shift Engineer after being properly relieved by the Station Director shall report to the Operations Director and shall perform such duties- as those described mitigate emergencyin Section 4.1.3 and such actions as necessary to conditions.

4 4-20

April,1984 Revision 4 4.3 Offsite GSEP Organization The size of the offsite GSEP organization will vary depending upon the nature and extent of the emergency. For planning purposes, two separate organizational arrangements will be defined.

For activation of the EOF, Commonwealth Edison has developed a prioritized Nuclear Outy Officer / Recovery Manager notification list.

This call list shall enable the responsible corporate Nuclear Outy Officer to notify a Recovery Manager who would require the least travel time to a particular EOF. Consistent with the onsite augmentation goal, the EOF sNill be activated as promptly as possible when necessary.

Once the Emergency Operations Facility is activated, aJ1 Comonwealth recovery efforts shall be directed, coordinated, and controlled from that location. There shall be three major emergency ,

control functions (centers) at the EOF. They are: (1) the Recovery l

' Center, (2) the Environmental Control Center; and (3) the Emergency News l Center. Refer to Section 7.1.5 for a description of these centers.  !

4.3.1 Offsite GSEP Organization for Emercencies of Limited Extent-During a Transportation Accident or during incidents at l i nuclear stations that are classified as Unusual Events or Alerts, it is unlikely that the. Emergency Operations Facility would be activated. In these instances, the Corporate Command Center may be activated. Corporate Command Center personnel are indicated on Figure 4.3-1. The Corporate Command Center Director will activate only those directors and personnel deemed appropriate.

1) Table 4.3-11 Corporate Command Center Director

2) Table 4.3-12 System Power Dispatcher

3) Table 4.3-13 Medical Director

4) Table 4.3-14 Legal Consultant

5) Table 4.3-15 Engineering Director i

L

[

4-21

--,-r, - - - . , - - - , - - - - - - .

/

April, 1984 Revision 4

6) Table 4.3-16 Intelligence Director

7) Table 4.3-17 Health Physics Director

8) Table 4.3-18 Information Director

9) Table 4.3-19 Environmental Director

10) Table 4.3-20 Manpower and Logistics Director

11) Table 4.3-21 Accounting Director

12) Table 4.3-22 Communications Director

13) Table 4.3-23 ERP Director

14) Table 4.3-24 Division Director

15) Table 4.3-25 Environs Director

(.

4-22

i i

1 FIGURE 4.3-1 ==

<n u LIMITED RESPONSE OFFSITE GSEP ORGANIZATION I

N.

CORPORATE COMMAND j , CENTER DIRECTOR

&k*

I w

SYSTEM POWER l

DISPATCHERS LEGAL i "

CONSULTANT l MEDICAL DIRECTOR i

I I I I

ENGINEERING INTELLIGENCE ENVIRONMENTAL MANPOWER AND DIRECTOR DIRECTOR l DIRECTOR LOGISTICS DIRECTOR

! I I I I I HEALTH PHYSICS INFORMATION ACCOUNTING COMMUNICATIONS i DIRECTOR DIRECTOR DIRECTOR DIRECTOR g.-- - - - g .- - -. - -

1 l ENVIRONS ERP DIRECTOR I l

DIRECTOR lll l _, l 11 8 i I I

DIVISION

..........,............. l ll DIRECTOR l

i STATION GROUP i  !

ii l

! ORGANIZATION i l l STAFF STAFF STAFF j (ONSITE) l STAFF g STAFF ll STAFF STAFF l

l ll i ' FlGURE 4.2-1 3.e.....................

g g____jg_______g et TSC or EOF of Technical Center Maywood Office i.__. _ . . . _ . . . _ . _ . . . _._ , _. - .- - 2.Z ~~Z - - - - - - - - - - - - - - -

April,1984 Revision 4 4.3.2 Offsite GSEP Organization for Emergencies of Great Extent During incidents at nuclear stations that are classified as Site or General Emergencies, the GSEP Recovery Group will be activated at the Emergency Operations Facility. In many instances, activation of the Recovery Group requires that designated directors of the Corporate Command Center staff relocate to the EOF and assume additional responsibilities for assigned positions. The Recovery Group functions under a Recovery Manager who is responsible for the overall company activities aimed at restoring the affected station to a safe status. The Corporate Command Center staff provides support to the Recovery Group under this organizational arrangement. The offsite GSEP organization for serious emergencies -

(e.g., Site and General Emergency) is depicted in Figure 4.3-2.

This organization consists of the following directors whose major ,

duties are delineated in the referenced tables:

1) Table 4.3-1 Recovery Manager

2) Table 4.3-2 Station Director (Plant Operations Manager)* l

3) Table 4.3-3 Advisory Support Director

4) Table 4.3-4 Technical Support Manager

5) Table 4.3-5 Environmental / Emergency Coordinator

6) Table 4.3-6 Design & Construction Support Manager

7) Table 4.3-7 Scheduling Planning Manager

8) Table 4.3-8 Waste Systems / Radiation Control Manager

9) Table 4.3-9 Administration / Logistics Manager l

10) Table 4.3-10 Emergency News Center Director

11) Table 4.3-11 Corporate Command Center Director

12) Table 4.3-12 System Power Dispatcher

13) Table 4.3-13 Medical Director

14) Table 4.3-14 Legal Consultant

15) Table 4.3-15 Engineering Director

16) Table 4.3-16 Intelligence Director

17) Table 4.3-17 Health Physics Director

• The designation is to be consistent with INFO guidelines; however, this

" Plant Operations Manager" title will not be used within the GSEP.

4-24

April, 1984 Revision 4

18) Table 4.3-18 Information Director

19) Table 4.3-19 Environmental Director

20) Table 4.3-20 Manpower and Logistics Director i

21) Table 4.3-21 Accounting Director t

22) Table 4.3-22 Communications Director

23) Table 4.3-23 ERP Director

24) Table 4.3-24 Division Director i

25) Table 4.3-25 Environs Director

26) Table 4.3-26 Training Director

27) Table 4.3-27 Waste Systems Director '

28) Table 4.3-28 Access Control Director 4

t

+

e e

1 4-25

1 FIGURE 4.3-2 FULL RESPONSE OFFSITE GSEP ORGANIZATION Recovery Manager l Staff l -

I I I I ,-__1__, I I I I Advisory Emergency Technical Weste System i i Station Administration / Scheduling Environmentol/ Design and Support News Center Support Rod. Control Logistics l Director Planning Emergency Const. Support Director Director Manager Manager li i Monager Monoger Coordinator Monoger j l l r-1 lTSC,___~1(Fig. l 4.2-1) l l l g-- d Staff Staff I L Staff Staff Stoff Staff Il Staff

l I l j Health Physics l l _

_ Training Environs i Director l Director Director i ' g l Staff ,_ Access Control l g

l Director l l _

Weste System I i

l Direetor Communications l '

l Director l .

E0F Stan g_____,

l  ! j -

CCC i I

r----------- , ~l I

l l Corporate Command Center!

l Environmental Director i

l l

Director g l8 3,,g j l ENVIRONMENTAL l g L___7__;______J CENT R

!I I I I  ! I Ii

! Information Intelligence Legal System Power Medicci Manpower 8 Logistic Engineering j Director Director Consultant Dispatcher Director Director

_ 39,,,

' Director l i ',_ _ _ ,(f.if. 4 3-Il

~ Staff

• Accounting l ERP -

Staff MAYED l p Director i Director TECH CENTER

,g

, g -

1 l 1g-l Division j Director Staff  !*$

i t____________________;

April, 1984 Revision 4 TABLE 4.3-1 RECOVERY MANAGER The Recovery Manager is the designated individual from Commonwealth Edison who has authority, management ability, and technical knowledge to manage the overall nuclear plant recovery operations whenever the Recovery Group is activated at the EOF Recovery Center. The primary individual designated as the Recovery Manager is the Division Vice-President and General Manager, Nuclear Stations.

Specifically, the Recovery Manager shall: l o Direct the Recovery GIoup and coordinate all company and industry support activities in coping with an emergency.

o Ensure notification of Federal, State, and appropriate local agencies of emergency declarations or re-classifications in accordance with Section 6.0 of this plan, o Ensure that Federal, State, and local authorities remain cognizant of the status of the emergency situation. If requested, dispatch informed individuals to State governmental emergency operations centers, o Review for factual content all information intended for conveyance to the news media by the Emergency News Center Director or his desigree, o Ensure that appropriate rteasures are promptly taken ansite to:

Terminate the condition causing the emergency.

Protect employees and the public.

Minimize damage to the plant.

Effect post-accident recovery and deactivate the GSEP organization when appropriate.

l o Request assistance from outside emergency response organizations, such as the Department of Energy Chicago Operations Office, if required.

o Determine after consultation with appropriate GSEP personnel when to evacuate the EOF and to determine who are ESSENTIAL and NON-ESSENTIAL personnel. He also determines where the evacuated personnel are to be reassembled.

o Maintain a record of the GSEP related activities.

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April, 1984 Revision 4 TABLE 4.3-2 STATION DIRECTOR The Station Director is the oesignated individual from Commonwealth the authority, who has requisite plant operating experience, and qualifications to implement in-plant recovery operations. The Station i Director will normally not relocate to the EOF, but should remain at the TSC. I Responsibilities assigned to the Station Director are to: l o Supervise the onsite operations support staff and the onsite Station GIoup organization.

o Implement plans and schedules to meet recovery operations objectives, o Provide training of personnel for off-normal instructions, plans, and procedures.

o PIovide information and recommendations to the Recovery Manager, o Oetermine if the OSC is to remain activated. l o Maintain a record of the GSEP related activities.

b 4-28

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

April,1984 Revision 4 '

TABLE 4.3-3 i ADVISORY SUPPORT DIRECTOR  ;

The Advisory Support Director is the designated individual from  :

Commonwealth who will coordinate the efforts of an advisory support group ,

composed of the NSSS s(pplier, the PRC, authoritative consultants and a public i information expert who have requisite authority to commit resources and resolve technical issues for their respective . organizations. This director 1

located at the EOF reports directly to the Recovery Manager.

Responsibilities assigned to the Advisory Support Director are to:

o Establish contact and maintain communications with appropriate non-Commonwealth Edison technical personnel whose assistance may be required to terminate the emergency conditions and to expedite

, the recovery.

o Establish an advisory support panel composed of representatives from organizations such as the NSSS Supplier, the NRC, authoritative consultants, and public information experts, .to

> analyze the emergency and make recommendations to be considered by the Recovery Manager.

o Maintain a record of the GSEP related activities.

t

?

9 e

e e

4-29

e i

April,1984 Revision 4 TABLE 4.3-4

^

TECINICAL SUPPORT MANAGER t The Technical Support Manager is the designated . individual from  :

Commonwealth who has requisite authority, nuclear experience, and technical expertise recovery operations.

to manage a technical staff in support of nuclear power plant t

i Manager shall: The Technical Support Manager who reports directly to the Recovery l o Develop plans and procedures in direct support of. plant i operations personnel with the objective of taking the plant to '

and maintaining a safe shutdown condition.

o 1

Provide a central facility for collection, retention, retrieval, and transmission of plant and local environmental parameters.

o Provide experienced licensed personnel for direct support of plant shift operations personnel.

1 o

Analyze conditions, develop guidance and _out-of-normal operating A

and emergency procedures for direct support of plant shift operations personnel.

o Analyze instrumentation and control problems, develop emergency

, procedures or alternate control schemes, and design and coordinate the installation of short-term modifications.

o Direct a staff of personnel having technical expertise and formal education in transient analysis and system interactions, nuclear i engineering and fuel management, core physics, electrical '

engineering, process computers, instrumentation and control systems, refueling operations, engineering mechanics, thermal hydraulics, plant structural and containment: design, and  ;

metallurgy. Some of this expertise may have to be provided by '

non-Commonwealth personnel, o Coordinate and assist the activities of the Intelligence Director located at the CCC. The Technical Support Manager has functional control of the Intelligence Director, while the CCC Director has line control. -

o Maintain a record of the GSEP related activities. ,

r h

4-30 i

r e

. m .. . _ _ _ _ _ . _ _ _ _ _ . _ _. ._ _ _ . _ . . . _ _ _ . - - . _

I;

• r I

April,1984 [

Revisjon 4  ;

TABLE 4.3-5 t

ENVIROPMENTAL/ EMERGENCY COORDINATOR ,

t The Environmental / Emergency Coordinator is the designated individual 4 from Commonwealth who is specifically qualified in the = coordination and  :

management of radiological. consequence assessment and who is authorized to  !

interact with supporting agencies. This individual will s'pervise u the Environmental Control Center at the EOF and will serve as the official contact  !

with State and Feoeral raciological assessment personnel.  ;

t Responsibilities assigned to the Environmental / Emergency Coordinator  ;

who reports to the EOF Recovery Manager are to: l [

l I

o Establish communications with the Corporate Environmental Center, the TSC, and/or the EOF Recovery Center and obtain information on l j the accident conditions, meteorological conditions, and estimates of radioactive material releases.

o Establish communication with offsite authorities and relay information necessary for the respective authorities to implement their emergency plans.

( o Direct the activities of the Environs Director and the environmental staff. Coordinate the activities of' .

environmental contractors.

o Interpret radiological data and based upon calculated dose projections, make recommendations for protective actions offsite

, consistent with Tables 6.3-1, 6.3-2, and 6.3-3 of this plan. ,

o When the EOF is activated direct the activities of the Environmental Director located at the CCC.

o Maintain a record of the GSEP related actitivies.

i ,.

i  ;

L i 4-31  !

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

April,1984 Revision 4 TABLE 4.3-6 DESIGN AND CONSTRUCTION SUPPORT MANAGER The Design and Construction Support Manager is the designated individual from Connonwealth who has the requisite authority to interface with the A/E, NSSS supplier, and the conJtruction forces on design or construction modifications required for recovery activities.

Responsibilities assigned to the Design and Construction Support Manager who reports to the EOF Recovery Manager are to: l 0 Provide for direct centact between Commonwealth, the A/E, NSSS supplier, and the ccnstruction representatives on administrative matters.

o Anticipate the need for and supply engineering and technical specialists to the GSEP organization.

o Direct, coordinate, and approve other engineering, design, and construction activities onsite.

o Establish which if any engineering, design, and construction activities shall be required to be controlled by the Quality Assurance Program.

o Functionally coordinate the activities of the Engineering Director located at the CCC.

o Maintain a record of the GSEP related activities.

4-32

April, 1984 '

Revision 4 TABLE 4.3-7

,SOEDULING PLANNING MANAGER The Scheduling Planning Manager is the designated individual from Commonwealth who has the requisite authority to coordinate and expedite plans and schedules to assist the Recovery Manager in recovery operations.-

Responsibilities assigned to the Scheduling Planning Manager who reports to the EDF Recovery Manager are to:

o Respond to specific directives of the Recovery Manager for the scheduling of activities.

o Take the measures necessary to- identify key problems, resource limitations, and the status of scheduled milestones.

o Develop agendas for Recovery Group staff meetings and follow-up to expedite commitment compliance.

o Maintain a record of the GSEP related activities.

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April,1984 Revision 4 TABLE 4.3-8 WASTE SYSTEMS / RADIATION CONTROL MANAGER l

The. Weste Systems / Radiation Control Manager is the designated individual . who, has requisite - authority, nuclear experience, and technical expertise' to manage the radioactive waste and radiological control aspects of the recovery operations.

The responsibilities . assigned to the- Weste Systems / Radiation Control Manager who reports to the EOF Recovery Manager are to:

o Maintain an todeted status report of onsite liquid, solid, and gaseous waste volumes, with particular interest given to systems or , tanks that are approaching or have exceeded their rated capacities. (This includes the plant charcoal filter exhaust system.)

l o Recommend sampling programs to the affacted station that will i allow an evaluation of radweste system status.

o Develop plans and. procedures for processing liquid, gaseous, and solid westes with a long-term goal of reducing all waste levels

to a normal pre-accident status and which maintains personnel l~ exposures as low as reasonably achievable.

i.

o Develop plans for modifications to plant systems that will allow large scale weste processing in a way that will keep personnel and public radiation exposures as low as possible.

l o Provide information and recommendations to the Recovery Manager concerning future operations that could affect the plant, equipment, or environment.

o Direct the activities of the Health Physics Director when that individual has bcen relocated to the EOF.

o Directs the activities of the Wasta Systems Director.

? .

j- o Maintain a record of the GSEP related activities.

1

[* 4-34 l

April, 1984 Revision 4 TABLE 4.3 9 ADMINISTRATION / LOGISTICS MANAGER l The Administration / Logistics Manager is the designated individual from Commonwealth who is responsible for providing administrative, logistic, communications, and personnel support for the recovery operations.

Responsibilities assigned to the Administration / Logistics Manager who reports to the EOF Recovery Manager are to:

o Serve as purchasing agent for the Recovery group with the responsibility for contract negotiation / administration and material control.

o Obtain the following services as appropriate:

-- Accommodations for lodging, trailer setups, airline and auto transportation (shuttle services).

-- Office support services such as typing, copying, office supplies, furniture, photography, and supply of area maps.

( -- Food services and necessary (non-radioactive) waste disposal.

o Provide for any necessary aerial services.

o Provide any extra communication equipment.

o Provide financial and accounting service, o Direct the activities of the Communications Director, Access Control Director, and the Training Director. Also functionally direct the activities of the Manpower and Logistics Director located at the CCC to obtain assistance in fulfilling the responsibilities listed above. The CCC Director has functional responsibility for the Manpower and Logistics Director.

o Provide a processing center for the registration of all incoming personnel; provide security to the EOF or Back-up EOF through the Access Control Director.

o Maintain a record of the GSEP related activities.

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April,1984 Revision 4 TABLE 4.3-10 EMERENCY NEWS CENTER DIRECTOR The Emergency News Center Director, upon activation of the Emergency News Center Group at the EOF, is responsible for all recovery-related information intended to be conveyed from CECO to the news media.

The responsibilities of the Emergency News Center Director who reports to the EOF Recovery Manager are to:

o Assure the operability of, and supervise the activities in the Joint Public Information Center (JPIC).

o Effect a smooth transition of the news media point-of-contact from CCC to JPIC, and of news information responsibilities from CCC/Information Director to EOF / ENC Director.

o Maintain the primary interface between CECO and the news media, including, as necessary, briefings, news conferences, interviews, and response to information reQJests.

o Keep up-to-date on conditions of the plant and environment, and actions of CECO personnel and outside agencies.

o Obtain approval of the Recovery Manager, or his designee of all information intended to be conveyed to the news media.

o Coordinate with Federal, State, and local agenies, as well as with other organizations involved in the recovery, to maintain factual consistency of information to be conveyed to the news media.

o Direct the activities of the CCC/Information Director, o Participate, as needed, in rumor-control activities managed by State agencies.

o Maintain a record of GSEP-related activities.

1 4-36

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

[

1 r April, 1984 Revision 4 TABLE 4.3-11 l

CORPORATE COMMAND CENTER DIRECTOR The Corporate, Command Center Director will direct company GSEP activities until such time - when (and if) the. Recovery Group at the EOF is  :

activated. After: the Recovery Group is activated, the CCC Director and .his '

staff become a support group to the Recovery Manager.

Responsibilities assigned to the CCC Director (prior to activation of the Recovery Group) are to:

o Direct the GSEP organization shown in Figure 4.3-1 and coordinate . l all company activities involved in coping with the emergency, o Notify appropriate Federal, State, and local agencies of l emergency conditions in accordance with Section 6.0 of this plan. ,

o Notify American Nuclear and Transportation Insurers of any emergency classification- l Accident.  !

i o Ensure that appropriate measures are promptly taken onsite to:

,b -

Terminate the condition caesing the emergency.

l' --

Protect employees and the public.

- Minimize the damage to the plant. ,

-- Effect post accident recovery and deactivate the GSEP

organization. ,

o Approve the factual content of CECO press releases to the public. l f o Request assistance from outside emergency response organizations, such as INPO and the Department of Energy Chicago Operations Office, if required.

t o Maintain a record of the GSEP related activities, o Activate the Recovery Group if the emergency escalates to a Site or General Emergency or if otherwise deemed appropriate.

Following Recovery Group activation at the EOF:  ;

o Remain at the CCC and provide assistance to the Recovery Manager, as requested.

1 o Direct the CCC organization shown in Figure 4.3-2. l o Maintain a record of the GSEP related activities.

4-37 l

April, 1984 Revision 4 TABLE 4.3-12 SYSTEM POWER DISPATCHER The System Power Dispatcher is the designated individual located at the System Power Supply Office (SPS0) who is responsible for performing normal duties and providing notification to the Nuclear Outy Officer, as outlined in Section 6.0.

to the CCCResponsibilities assigned to the System Power Dispatcher who reports l Director are to:

o Notify the Nuclear Outy Officer in the event of a Transportation l Accident, an Unusual Event, an Alert, a Site Emergency, a General Emergency, or a loss of communications with a nuclear station as reported from the nuclear station.

l o In the event of an Unusual Event, Alert or Site Emergency and if the Nuclear Duty Officer cannot be contacted within five minutes, immediately notify the Illinois ESDA, Illinois Department of Nuclear Safety and appropriate contiguous State authorities of the emergency situation.

o Maintain a record of the GSEP related activities.

4-38

April,1984 I

Revision 4 TABLE 4.3-13

_ MEDICAL DIRECTOR The- Medical Director is the company physician or other medically .

qualified individual who is responsible for providing recommendations to the Corporate Command Center Director (both prior to and during the Recovery phase) for medical treatment and for specifying medical supplies necessary for decontamination treatment and general first aid. ,

Responsibilities assigned to the Medical Director who reports to the CCC Director are to:

o Ensure that arrangements with appropriate hospitals have been made for the emergency care and admission of patients involved in l hazardous materials / radiation incidents, o

Recommend first aid and decontamination techniques for personnel requiring aid in the emergency area. '

o Coordinate the activities of contracted radiological medical assistance personnel.

o Analyze all available. health information data pertaining to persons who have received injuries or, excessive exposure to hazardous materials, including radioactivity.

o Ensure that procedures governing the use of thyroid blocking agents have been followed by Commonwealth emergency personnel, o

Consult with the Corporate Command Center Director regarding measures to protect onsite personnel and the offsite public.

O Maintain a record of the GSEP related activities.

e e /

4-39

April, 1984 Revision 4 TABLE 4.3 14 ,

LEGAL CONSULTANT -

The Legal Consultant is a representative of Comonwealth's - legal staff who is responsible for providing counsel on all legal matters. Prior to and during the recovery phase of the emergency, he will report to the Corporate Comand Center Director.

Responsibilities assigned to the Legal Consultant are to:

o Provide legal assistance to Comonwealth.

o Provide counsel to the CCC Director regarding Federal, State, and local regulations pertaining to emergency plans.

o Maintain a record of the GSEP related activities.  ;

P 9

4-40

L I

E April, 1984 l Revision 4 i TABLE 4.3-15 ENGINEERING DIRECTOR

- The Engineering Director who reports to the CCC Director at the CCC l  ;

. will coordinate - the engineering services necessary for . plant modifications, special equipment arrangement, shielding, containers, or other devices needed 4

during the emergency. Upon activation of the EOF Recovery Group, the.l ,

Engineering Director will functionally serve as a support individual for. the

• Design and Construction Support Manager. t i

Responsibilities assigned to the Engineering Director - (prior to i Recovery Group activation) are to: '

o Assist in the development of post-accident recovery measures. .

o Provide technical information on the facility design.

o Ensure that modifications needed for - plant recovery are implemented in a timely manner.

o Enlist the aid of consultants-as necessary. ~

o Maintain a record of the GSEP related activities.

t Following EOF Recovery Group activation, the Engineering Director  :

shall perform activities similar to those listed above, ex' cept that they shall  !

be done -in coordination with and in support of the Design and Construction Support Manager who is located at the EOF.

1 I

l l

i a

i a

4-41 l l

h

, . - - . . ~ . . . . . . _ . . _ . - _ . . . . _ . , , . . - . - . , . . , _ . , - _ . . - _ . . , , __I.-._--....--.._ , . - . _ . .

i i

April,1984 Revision 4 TABLE 4.3-16 INTELLIGENCE DIRECTDR The Intelligence Director will coordinate activities relating to health physics evaluations and information distribution to inform and make recommendations to the CCC Director. The Intelligence Director will serve as CCC Director in the event that the CCC Director or an alternate is not available. Upon activation of the EDF Recovery Group, he will functionally l t

serve as a support individual for the Technical Support Manager while remaining at the CCC.

RecoveryResponsibilities Group activation)assigned are to: to the Intelligence Director (prior to EDF l ,

o Assist the CCC Director in the evaluation of the significance of an emergency with respect to the public.

o Direct the activities of the Health Physics Director and the Information Director when located in the CCC. l ;

o Review and concur with press releases proposed by the Information Director.

o Maintain records of information obtained from the other directors within the CCC organization, including contacts with offsite agencies, contractors and other support forces.

o Serve as the CCC Director in the event that the CCC Director or an alternate is not available.  :

o Provide for access control to the CCC with designated individuals.

O Maintain a record of the GSEP related activities.

Following EDF Recovery Group activation, the Intelligence Director shall perform functional activities at the CCC in support of the Technical Support Manager.

4-42

April, 1984 Revision 4 TABLE 4.3-17 IEALTH PHYSICS DIRECTOR The Health Physics Director shall serve as support from the. CCC to the onsite health physics activities by providing additional instrumentation or persomel as necessary, under the direction of the Intelligence Director.

He shall make recommendations on dose management techniques for both onsite l and offsite activities - for maintaining personnel exposures as low as reasonably achievable. Upon activation of the EOF- Recovery Group, he shall serve as a support individual for the Waste Systems / Radiation Control Manager at the EOF.

Responsibilities assigned to the Health Physics Director (prior to Recovery Group activation) are to:

o Determine the need for additional radiological support personnel.

-o Determine the need. for additional health physics instrumentation, dosimetry, and protective equipment.

o Review plant health physics information and make recommendations to the Intelligence Director. To the extent possible, make recommendations that will ensure that emergency and. recovery operations are performed in accordance with Commonwealth radiation protection standards. Especially . during reentry situations, normal 10 CFR 20 exposure limits are not to be exceeded, and in all situations personnel exposures should be maintained as low as reasonably achievable.

o Assist the affected station in the development of plans'for plant surveys, sampling, - shielding, and special tools in support of waste systems processing and design modification activities.

o Keep informed of the activities of offsite environmental monitoring teams. Make recommendations that will assist those teams maintain their exposures as low as reasonably achievable.

o Maintain a record of the GSEP related activities.

Following an EOF Recovery Group activation, the Health Physics Director shall perform activities similar to those listed above, except that

'they shall be done at the EOF in coordination with and in support of the Waste Systems / Radiation Control Manager. The Health Physics Director shall also provide for the radiation protection of personnel at the EOF.

4-43

__ ~ ._. . _ _ _

April,1984 TABLE 4.3-18 Revision 4

! _INFORMATION DIRECTOR

! The. Information Director is responsible for collecting, verifying, i

and disseminating information on emergency situations to . the public via th news media, under the direction of the Intelligence Director. Upon the Emergency News Center Director. activation of the Recovery Group, the RecoveryResponsibilities assigned Group activation) are to: to the Information Director (prior to o

Obtain information.

of the emer Through GSEP personnel, determine the nature operations, gency and its effect on the public and other company o

Release information.

as soon as possible. Take steps to release accurate information other involved agencies and companies. Coordinate the release of in interviews and comments from CommonwealthThe news media seeking given full cooperation. officials should be o

Distribute internal information. Information should be promptly disseminated to Commonwealth employees through appropriate communications channels. as soon as possible O

t Maintain a record of the GSEP related activities.

becomes a support individual to the Emergency News release information only when directed by the Emergency News Center D The Information Director is to maintain his office in either t appropriate CECO locations.

1 e

4-44

. i

April,1984 Revision 4 TABLE .4.3-19 ENVIROPMENTAL bIRECTOR

' The Environmental Director is responsible for initially coordinating all offsite sampling / monitoring activities of Commonwealth personnel and for interfacing with State . personnel regarding dose assessment programs. Upon activation of the EOF Recovery Group, he shall serve as a support Individual for the EnvironmentalNmergency Coordinator at the EOF.

Responsibilities assigned to the Environmental Director (prior to Recovery Group activation) are to:

o Direct the environmental sampling activities of the Environs Director.

o Coordinate the environmental contractor's assistance in the collection of environmental data.

o Cooperate with the Illinois Department of Nuclear Safety (and contiguous State agencies) in the implementation of an offsite dose assessment program.

o Based on environmental sanpling or known plant releases, calculate ' projected dose' values for affected areas; based on-these- projections, advise the CCC Director of protective action recommendations for plant personnel and members of the public.

These recommendations should be consistent with Tables 6.3-1, t

6.3-2, and 6.3-3 of this plan.

o Maintain) record of the GSEP related activities.

Following a Recovery Group activation:

o Obtain infomation . and perform activities at the Corporate Environmental Center at the direction of the Environmental /

Emergency Coordinator.

4-45

i , -

April,1984 Revision 4 TABLE 4.3-20 MANPOWER / LOGISTICS DIRECTOR The Nanpower/ Logistics Director is responsible for directing a staff f of me@ower, logistics,- communications, aerial assistance, and accounting '

personnel in support of the station as required by the Corporate Command Center Director. Upon activation of the Recovery Group, he shall serve as a support individual for the Administration / Logistics Manager.

Responsibilities to Recovery assigned Group Activation) are to:to the Manpower / Logistics Director (prior l o Ensure that emergency communications equipment is kept operable during the course of the emergency.

i o Provide personnel, equipment, and services as required, primarily from the . appropriate Division. Services may include transportation of personnel and equipment, o Keep the CCC Director informed of support services available to assist.the station.

'5 o' Direct the activities of the Accounting Director, and- the ERP Oirector.

o Maintain a record of the GSEP related activities.

Following a Recovery Groy) activation, the Manpower / Logistics Director shall perform activities at the CCC under the functional direction of the Administration / Logistics Manager who is located at the EOF.

4-46

April,1984 Revision 4 TABLE 4.3-21 ACCOUNTING DIRECTOR The Accounting Director is responsible for accounting and related cost monitoring practices related to the emergency. He shall remain at the I CCC or other designated location throughout the emergency and recovery activities, functioning under the direction of the Manpower / Logistics Director. I Responsibilities assigned to the Accounting Director are to:

o Seek counsel of Industrial Relations, the comptroller's office, and others as required.

o Initiate use of the special GSEP function number to accrue GSEP l costs.

o Make provisions to establish a proper method of accounting for costs of contractual services and other expenditures related to the emergency.

o Fulfill the clerical requirements for the other directors of the Corporate Command Center.

o Maintain a record of the GSEP related activities, f

I 4-47

b -

April, 1984 Revision 4 TABLE 4.3-22 COMMUNICATIONS DIRECTOR The Communications Director is responsible for the procurement of required telephone and radio communications services and facilities as specified by the Manpower / Logistics Director and maintenance of these communications as required. Upon activation of the EOF Recovery Grcup, the Communications Director reports to the Administration / Logistics Manager.

Responsibilities assigned to the Communicaticns Director are to:

o Obtain additional radio and telephone equipment as necessary to meet the needs of the emergency.

o Obtain sufficient personnel to maintain communications ecuicment in an operable condition.

Io o Maintain a record of the GSEP related activities.

i

)

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April,1984 Revision 4 TABLE 4.3-23 ERP OIRECTOR The Corporate Command Center ERP Director, located in the CECO Technical Center Office in Maywood, Illinois, shall coordinate the activities of Division persomel and equipment. Under the direction of the Manpower / Logistics Director, he shall provide for Division support to the affected station.

Responsibilities assigned to the ERP Oirector are to:

o Activate the Emergency Restoration of Power Program as necessary to suppctt the station activities.

o Infom the respective Division Director of support service required by the Station or the EOF.

o Obtain additional support from the other Division Directors, as the level of requirements increases.

o Maintain a record of the GSEP related activities.

i 1

l 4-49

6 April,1984 Revision 4 TABLE 4.3-24 DIVISION DIRECTOR The Division Director shall direct the GSEP Division personnel to \

provide support services required by the Corporate Command Center ERP Director.

Responsibilities assigned to the Division Director (s) are to:

o Activate the Division resources for emergency support and coordinate all activities.

o Provide the required personnel, instruments, equipment, and material to the station as specified by the CCC ERP Director.

o Assist government agencies, if required, with the movement and evacuation of the public from a defined area. .

o Maintain a record of the GSEP related activities.

+(

e 4-50

April, 19'84 Revision 4 TABLE 4.3-25 ENVIRONS DIRECTOR -

The Environs Director is the member of the offsite GSEP organization who will supervise the activities of Commonwealth environmental sampling teams in an emergency. He shall carry out his activities at the direction of the l Environmental Director at the CCC. Subsequent to-a Recovery Group activation, he shall serve under the Environmental / Emergency Coordinator.

Responsibilities assigned to the Environs Director are to:

o Establish a headquarters at either the affected station's TSC or EOF.

o Assemble one or more environmental monitoring teams. During an actual or suspected gaseous release situation from the plant, two teams should be dispatched. If sufficient manpower is available, there should be three persons per team.

o Dispatch and coordinate the activities of Commonwealth Edison environmental monitoring teams in order to determine the extent and nature of offsite releases of radioactive or other hazardous materials. Activities of the teams may include:

-- Dose rate surveys ~(including plume tracking);

-- Air sampling;

-- Soil, water, and vegetation sampling;

-- Contamination surveys; and

-- Exchange of TLDs and filter cartridges from fixed environmental stations.

o Request through the GSEP organization:

-- Assistance for road blocks and security until State, County l and Local personnel are available;

-- Communications equipment as necessary. Telephones, mobile radios, and portable radios may be required;

-- Required transportation for personnel; and

-- Sufficient technical and non-technical personnel to expand the operation as necessary.

, o Maintain a record of the GSEP related activities.

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April,1984 TABLE 4.3-26 Revision 4 TRAINING OIRECTOR needed to support recovery operations.The Training Director shall coord Administration / Logistics Manager The Training Director reports to th Responsibilities assigned to the Training Director include:

o l Provide tha coordination necessary to train large numbers of nuclear station. personnel needed to support recovery operations at an affec o Ensure that training given to incoming personnel descriptions of the station layout includes status of systems, and emergency pro,cedures, basic radiation protection, o

Ensure that training is given on out-of-normal procedures for shift operators, maintenance, health physics, personnel. and chemistry o

( Determine areas of abnormal radiation levels and provide specific instructions to personnel on how to limit exposures in such areas.

o Maintain a record of the GSEP related activities.

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April,1984 Revision 4 Table 4.3 27 WASTE SYSTEMS DIRECTOR The Waste Systems Director who reports to the Waste Systems / Radiation Control Manager shall support the onsite radwaste activities by providing technical assistance in the form of manpower, equiprent, supplies, and recommendations for both onsite and offsite activities.

Responsibilities assigned to the Waste System Director are:

o Maintain an updated status report on onsite radwaste systems regarding solid, liquid, and gaseous materials.

o Recommend sampling programs to the affected station that shall allow evaluation of radwaste system status, o Develop plans and procedures for processing contaminated materials for both short and long term reduction programs.

o Develop plans and procedures for shipment of contaminated materials to authorized burial locations.

o Develop plans for modifications to plant systems that will allow waste processing in keeping with the "ALARA" concept.

o Provide infctmation and recommendations to the Waste Systems /

Radiation Control Manager concerning future operations that could affect the plant, equipment, or environment.

o Direct a radwaste system operations staff.

o Maintain a record of the GSEP related activites.

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I l

April, 1984 TABLE 4.3-28 ACCESS CONTROL DIRECTOR The Access Control Director reports to the Administration / Logistics Manager. Initially the Security Director working from the TSC may be the acting Access Control Director. The responsibilities of the Access Control Director are to:

o Control access to the EOF or Back-up EOF.

o C.mrdinate with the Administration / Logistics Manager or his designee to control ingress and egress of the EJ personnel, o Report to the CCC Director or Station Director during early stages of EOF activation to control access until the Administration / Logistics Manager arrives at the EOF.

o Maintain a record of the GSEP related activities.

I t

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April, 1984 Revision 4 4.4 Non-Commonwealth SUDoort Groups Agreements are maintained with support agencies for each nuclear station.- These support agencies (to be named in each site specific annex) provide services of:

L

1) law enforcement;

2) fire protection;

3) ambulance services;.

4) medical and hospital support; and

5) ' radiological assistance.

Support groups providing transportation and treatment of injured station personnel are described in Section 6.5 of this plan.

Commonwealth retains contractors to provide supporting services to

. nuclear generating stations. Among services currently provided are the.

following:

• 1) Teledyne Isotopes provides environmental radiological monitoring, '

bionssay and radiochemical analysis services. In an emergency situation, Teledyne field personnel, at a minimum, would continue ~

to maintain Commonwealth air samplers and exchange TLDs under the s@ervision of either the Environmental / Emergency Coordinator or the Environs Director.

Illinois would analyze the Theenvironmental Teledyne laboratory in Northbrook,theirl samples for radioactivity content and report results to Commonwealth Edison.-

• 2) Radiation Meningement Corporation (RMC) provides services of medical and health physics support. RMC advises on the health physics aspects of situations- requiring medical assistance, provides and maintains whole body counters at Commonwealth l nuclear stations, and interprets bioassay results.

• 3) Murray- and Trettel, Inc. provides meteorological - monitoring services, including - weather forecasts. Murray and Trettel maintains all Commmonwealth nuclear station meteorological facilities. Murray- and Trettel has computer capability to pool remotely the meteorological facilities to ascertain local conditions and to detect instrument failure. -

• 4) R. S. Landauer, Jr., Company provides personnel dosimetry services. Landauer provides film badges and TLD rings to personnel at the nuclear stations; processes the dosimetry; and

• NOTE: The specific contractors may change but the functions are maintained.

4-55 1

' April,1984 Revision 4 reports the results in hardcopy and computer card format. In an emergency, Landauer would provide additional dosimetry to the affected nuclear station and to the Environmental / Emergency Coordinator, and to the Health Physics Director, if needed.

+

• NOTE: The specific contractors may change but the functions are maintained.

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April, 1984 Revision 4 4.5 Institute of Nuclear Power Operations (INPO)

Experience has shown that a utility may need resources beyond in-house capabilities for the recovery from a nuclear plant emergency.

One of the roles of the Institute of Nuclear Power Operations is to assist affected utilities by quickly applying the resources of the nuclear industry to meet the needs of an emergency.

INPO has an emergency response plan that enables it to provide the following emergency support functions:

o Assistance to the affected utility in locating sources of emergency manpower and equipment; o Analysis of the operational aspects of an incident; o The dissemination of information to member utilities concerning aspects of the incident that are applicable to their operations; and o Organizing the support of industry experts who could advise the utility on technical matters.

To support these functions, INPO maintains the following emergency support capabilities:

o A dedicated emergency call number; o Designated INPO representative (s) who can be quickly dispatched to the utility emergency response organization to coordinate INPO support activities and information flow; and o The 24 hour-per-day operation of an Emergency Response Center at INPO headquarters.

Comonwealth Edison will notify INPO (via the designated emergency call number) for all situations involving an Alert, Site Emergency, or General Emergency declaration.

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

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F April, 1984 Revision 4 4.6 Participatino Federal Organizations 4.6.1 Nuclear Reculatory Commission The Nuclear Regulatory Commission (NRC) is responsible for licensing and regulating nuclear facilities and materials and for conducting research in support of the licensing and regulatory process. These responsibilities include protecting the public health and safety, protecting the environment, protecting and safeguarding materials and plants in the interest of national security and assuring conformity with anti-trust laws.

The NRC Office of Inspection and Enforcement has the responsibility for auditing of nuclear power stations, special nuclear material, source material, and byproduct material licensees.

It is responsible for ensuring that such activities are conducted in accordance with the terms and conditions of such NRC licenses and that as a result of such operations, there is no undue risk to the health and safety of the public.

The MC Office of Nuclear Reactor Regulation, established by the Energy Reorganization Act of 1974, as amended, performs licensing functions associated with the construction and operation of nuclear reactors and with the receipt, possession, ownership, and use of special nuclear and byproduct materials used at reactor facilities.

With regard to emergency preparedness, the NRC shall:

1) Assess licensee emergency plans for adequacy:

2) Review the Federal Emergency Management Agency findings and determinations on the adequacy and capability of implementation of State and local plans; and 3). Make decisions with regard to the overall state of emergency preparedness and issuance of operating licenses.

The NRC shall respond to incldents at licensed facilities or l vehicular accidents involving licensed materials, including l

radionuclides, in transit. The NRC shall act as the lead Federal agency with regard to technical matters during a nuclear incident including radiological assistance. The NRC shall be prepared to  ;

recommend appropriate protective actions for the public and technical actions to the licensee. FEMA shall act as the lead Feceral agency for of fsite, non-technical concern 3.

Durirg an incioent the Chairman of the Commission is the senior NRC i authority for all aspects of a response. The Chairman shall transfer control of emergency response activities to the Director of Site Operations when deemed appropriate by the Chairman.

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April,1984 Revision 4 All MC Regions as well as Headquarters are prepared to respond to potential emergencies. All Regions and Headquarters have develcped plans and procedures for responding to radiological incidents !

involving m C licensees. Headquarters has developed the NRC Incident Response Plans and Implementing Procedures. Each NRC Region has developed Regional Supplements that detail how the Region will fulfill all of the responsibilities assigned in the NRC Incident l Response Plan. All NRC organizations are responsible for maintaining I an effective state of preparedness through periodic training, drills, ,

and exercises.

Each Region and Headquarters has established and maintains an Incident Response Center designed to centralize and coordinate the emergency response function. Adequate communications are established to link the licensee, Headquarters, and the Region. The NRC has !

established lines of communications with local government, State I government, other Federal agencies, Congress, and the White House. I Public information will be disseminated in a timely manner and periodically, i

Each Region is prepared to send a team of qualified specialists to l the scene expediently. All of the necessary supplies and eculpment -

needed for emergency response will be provided and maintained by the MC.

The NRC's Incident Response Plan objectives are to provide for protection of the public health and safety, property, and the environment, from the effects of radiological incidents which may '

occur at licensed facilities or which involve licensed materials, including radionuclides in transit.

The objectives of the agency plan set forth the organizational and  :

management concepts and responsibilities needed to assure that WC l has an effective emergency response program. -

l The plan is intended to ensure NRC preparedness:

l o To receive and evaluate notificaton ' information of incidents, accidents and unusual events and determine the extent of WC response necessary to meet NRC responsibilities for mitigating the consequences of these events; o To determine the cause of incidents, accidents, and unusual events in order to ensure that apprcpriate corrective actions are taken b the licensee to minimize the consequences of these events; y o To provide on-site expertise in a timely manner, to evaluate the a nature and extent of the incident, ascertain plant status (for reactors and fuel facilities), monitor licensee activities, determine compliance, make recommendations, and, if necessary, issue oroers relative to the event; 4-59 -

April, 1984 Revision 4 o To inform the public and others of plant status and technical details concerning the incident; o To recommend adequate protective actions to the responsible local and/or State agencies; o To provide technical assistance; o To ensure the plant is returned to a safe condition; and o To return the NRC Headquarters and Regional office to normal operations.

4.6.2 Federal Emeraency Manacement Acency (FEMA)

The Federal Emergency Management Agency (FEMA) establishes policy and coordinates the civil emergency planning, management, mitigation, and assistance functions of the executive agencies of the United States. FEMA is also responsible for establishing a program of federal disaster preparedness and for providing technical assistance to states in developing comprehensive plans and practical programs for preparation against disaster.

With regard to radiological emergency preparedness, FEMA will:

1) Establish policy and provide leadership via the Federal Radiological Preparedness Coordinating Committee (FRPCC) in the coordination of all Federal assistance to State and local governments for developing,. reviewing, assessing, and testing the State and local radiological emergency response plans;

. 2) Review and approve State and local radiological emergency response plans and preparedness in accordance with FEMA regulations;

3) Develop, with the NRC, scenarios for use by NRC licensed facility operators and State and local governments in testing and exercising radiological emergency plans; and

4) Develop, implement, and maintain a training program to support State and local radiological emergency response plans.

The role of FEMA during an emergency is that of coordinating and i

directing the offsite activities of all Federal agencies during a radiological accicent.

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April, 1984 Revision 4 4.6.3 Federal Radioloalcal Preparedness Coordinatino Committee (FRPCC)

The Federal Radiological Preparedness Coordinating Comittee consists of the Federal Emergency Management Agency, which chairs the Comittee, the Nuclear Regulatory Comission, the Environmental Protection Agency, the Department of Health and Human Services, the Department of Energy, the Department of Transportation, the Department of Defense, the Department of Agriculture, the Department of Commerce, and where appropriate and on an ad hoc basis, other Federal departments and agencies. The FRPCC shall assist FEMA in l provioing policy direction for the program of Federal assistance to l State and local governments in their radiological emergency planning l l and preparedness activities. I 4.6.4 Department of Eneroy Chicsoo coerations Office l The Department of Energy has extensive radiological monitoring i equipment and personnel resources that it can assemble and dispatch to the scene of a radiological incident.

l Upon request, the Department of Energy (00E) Chicago Operations Office will provide assistance to Commonwealth Edison following 'a radiological incident as outlined in the Federal

' Radiological Monitoring and Assessment Plan (FRMAP). The objective of the DOE Chicago Operations Office would be to rapidly dispatch a l

team of specialists to the incident site where the team would:

1) Make needed radiological assistance available to the general public, State and local governments, and Federal i agencies; .

2) Provide a framework through which Federal agencies will cuordinate their emergency monitoring and assessment l

activities in support of State and local governments radiological monitoring and assessment activities; and

3) Assist State and local governments in preparing for radiological emergencies ey des:ribing Federal radiological assistance responsibilities and capabilities.

If Comonwealth Edison deems that assistance from 00E is necessary or desirable, the Recovery Manager, the Corporate Command Center Director, or the Station Director would notify the 00E Chicago Operations Office. Assistance provided by 00E shall not abridge State or local authority.

t 4-61

April, 1984 Revision 4 4.6.5 The U.S. Coast Guard The U.S. Coast Guard patrols and ensures the safety of navigable waterways in the United States. The U.S. Coast Guard shall be promptly notified of any oil or hazardous substance discharges into rivers or lakes or radioactive contamination of rivers or lakes under Coast Guard jurisdiction at levels requiring assistance to effect protective actions (Refer to Section 9.3).

The U.S. Coast Guard will be contacted by the Illinois  ;

Department of Conservation in the event of an incident at a nuclear power plant. The Coast Guard will be responsible for officially closin i

plan).g the waterways to all commercial traffic (Refer to the State  :

4.6.6 U.S. Army Corps of Enoineers The U.S. Army Corps of Engineers controls barge and boat

• traffic at locks and dams on navigable waterways in the United States.

l The Corps of Engineers will be contacted by the Illinois Department of Conservation in the event of an incident at a nuclear power plant. The Corps will be responsible for closing their locks l and dame to all waterway traffic leading to the arfected area, '

l allowing only traffic leaving the area (Refer to the State Plan "The Illinois Plan for Radiological Accidents" (IPRA) Volume 1 & 2).

l 4.6.7 Federal Bureau of Investication (FBI) l Support from the Federal Bureau of Investigation (FBI) is avellable through its statutory responsibility based in Public Law and the US code, and through a memorandum of understanding for cooperation with the Nuclear Regulatory Commission. Notification to the FBI of emergencies in which they would have an interest will be through provisions of the Nuclear Station's Security Plan, or by the MC.

4-62

April,1984 4.7 The State of Illinois Revision 4 The State of Illinois has the statutory responsibility and authority i

for protecting the health and safety of the public in Illinois, The State of Illinois has developed an " Illinois Plan for Radiological Accidents" (IPRA). This plan was developed in accordance with the guidance suggested by NUREG 0396 and NUREC 0654.

This section provides a summary of the essential elements of the State Plan.

The Illinois Plan for Radiological Accidents (IPRA) is based upon the implementation of five basic functions:

o Command and Coordination o Notification and Warning o Accident Assessment o Protective Actions o Parallel Actions Figure 4.7-1 depicts the overall concept of operations for the Illinois Plan for Radiological Accidents (IPRA).

4.7.1 Governor of the State of Illinois The Governor of the State of Illinois 'has overall command authority for both the radiological and nonradiological aspects of a nuclear incident. The Governor shall make the final recommendation for protective actions, and shall serve as the State's primary spokesperson.

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April, 1984 Revision 4 4.7.2 Illinois " Department of Nuclear Safety" (ONS) l The Illinois Department of Nuclear Safety (ONS) has both the l command authority for _r-11olacical aspects of a nuclear incident and the responsibility for performing various radiological functions.

These functions include food, water and milk control, radiation exposure control for the general public, and confirmatory accident assessment. During an emergency situation, the DNS shall make protective action recommendations to the Governor and the Illinois Emergency Services and Disaster Agency.

The State of Illinois Department of Nuclear Safety has the responsibility to inform the State of Wisconsin Department of Emergency Government with respect to GSEP emergency classifications at Byron Nuclear Power Station that impacts the 50 mile ingestion pathway zone.

The DNS response to a nuclear incident utilizes two functional sub-groups. They are the Radiological Emergency Assessment Center (REAC) and the Radiological Assessment Field Team (RAFT).

4.7.2.1 Radiolooical Emercency Assessment Center (REAC)

The CNS has established REAC at its Springfield headquarters. REAC will serve as the command location for all (State-related) radiological aspects of a nuclear incident.

The Associate Director of DNS, or his designated alternate, is in command of REAC.

4.7.2.2 Radioloalcal Assessment Field Team (RAFT)

RAFT has been organized to perform the fleid radiological functions of confirmatory accident assessments during a nuclear emergency. RAFT consists of a Mobile Command Center, a Mobile Nuclear Laboratory, and monitoring and sampling teams.

4.7.3 Illinois "Emercency Services and Disaster Acency" (ESDA)

The Illinois Emergency Services and Disaster Agency (ESDA) has command authority for the non-radiological aspects of a nuclear incident and provides the _overall coordination of the emergency response. The Illinois ESDA has the programmatic responsibility to implement protective actions as recommended for the public by the DNS and the Governor.

The State of Illinois has defined four levels of operational response; each level requires increasing degrees of response from State and local agencies. An. immediate level of cperational response for a given emergency (GSEP) classification shall be recuired so that i the level of response shall accord with the accident classification.

The minimum operational response levels for given incident classifi-cations can be sumarized as follows:

4-64

i

/

April,1984 Revision 4 Level 1 Unusual Event Notification of ESDA and DNS Level 2 Alert Notification of ESOA and its key personnel, DNS and its key personnel, and key local governments. REAC shall be activated.

Level 3 Site Emergency Same as Level 2 plus the following: RAFT shall be dispatched to the affected site; ESDA shall activate the State EOC; county and local governments shall activate their EOCs and activate their public notification system.

Leyel 4 General Emergency Notification of all parties involved in the operational response. Activation of all operations and command centers associated with the operational response. REAC shall be activated and RAFT shall be dispatched. Local governments shall activate their public notification system and implement protective l action.

'(

The operational response level for the Unusual Event, Alert, and Site Emergency may be increased to a higher level if deemed necessary.

The State's operational response to an emergency utilizes six (6), operational centers:

o State Emergency Operations Center (SEOC) o State Command Post (SCP) o State Staging Center (SSC) o Community Command Post (CCP) o County Emergency Operations Center (CEOC) o Local Government Emergency Operations Center (LGEOC)

The following sections shall discuss the role of these operational l centers.' Depending upon the nature of the emergency, one at more of these centers may not be activated.

t e

4-65 l

i L

April,1984 4.7.3.1 Revision 4 State Emeroency Operations Center (SEOC)

The SEOC (manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day) is located in Springfield, Illinois and is the central command post for state agencies. The primary function of the SEOC is to e coordinate the State's response with local governments. For this purpose the SEOC is staffed during emergencies by representative,s of State agencies under the overall direction of the ESDA Internal S@ port Coordinator.

4.7.3.2 State Command Post (SCP)

The SCP shall be located near or within the affected plume exposure EPZ and is responsible for the allocation of state agency resources and personnel in support of local government actions.

4.7.3.3 State Stacino Center (SSC)

The SSC shall be located near the affected plume exposure EPZ and shall serve as an extension of the SEOC.

Staging center personnel shall be responsible for summarizing personnel assignments. The SSC shall also be used to store

( state resources, such as TLDs and potassium iodide.

4.7.3.4 Community Command Post (CCP)

For certain sites, particularly those near major metropolitan areas and/or contiguous states, a Community Command Post shall be utilized. The CCP shall be similar to the SEOC in that it shall provide a central meeting place for representatives from local governments and contiguous states for tasks like response management and radiological assessment updates.

4.7.3.5 County Emeroency Operations Center (CEOC)

In those areas without a CCP, the County EOC shall serve as the primary' coordinating center for local government resconse within the county's jurisdiction and for coordination between counties.

4. 7.3. 6 Local Government Emeroency Ocerations Center (LEOC)

The LEOC shall serve as the command post for organizing each local government's implementation of protective actions.

4-66

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l 5

April, 1964 l Revision 4 4.7.4 Notification  !

Following the preliminary notification by the affected nuclear station, the State shall initiate a notification procedurr commen- i surate with the reported emergency (Refer to the State Plan)  ;

4.7.5 Accident Assessment Upon notification of an emergency, the .DNS shall conduct a confirmatory accident assensment.

This assessment shall involve the determination of the source term, the projection of the atmospheric dispersion of the release, and the deposition of the radioactive material if appropriate.

4.7.6 Protective Actions The recomendation for protective actions for the public during the preliminary phase of a fixed nuclear facility incident I

shall, of necessity, be based upon the preliminary assessment made by the facility. After the confirmatory accident assessment, the recommendation for protective actions, if appropriate, shall be made by the Dirt.: tor of DNS to the Governor and the Director of ESDA.

Such a recommendation shall be based upon the projected population

,('

t dose as determined through the confirmatory accident assessment and/or the potential for such exposure.-

Following the determination of _ appropriate protective actions, iglementation of these actions shall be under the command and control of the ESDA which shall ensure completion in accordance with the State plan. Protective actions include: evacuation; shelter; J access control; food, water, and milk control; and protective actions for emergency workers.

4.7.7 Parallel Actions Parallel actions are performed by the State after or in

- conjunction with protective , actions. Parallel actions consist of

1) Law enforcement;

2) Social services; c 3) Emergercy medical services;

4) Radiation exposure control; and

). 5) Re-entry.

v 4-67

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I April 1984 ,

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i April, 1984 g Revision 4 4.8 The State of Iowa Much of the Emergency Planning Zone for the Quad Cities Nuclear Station lies within the State of Iowa. The State of Iowa has developed an " Iowa Emergency Plan". This plan is now under formal review by the Federal Emergency Management Agency, Regional and National offices. This

+

section provides a summary of the essential elements of the Iowa Emergency Plan, specifically outlining the specific responsibilities of certain " key" Iowa State Agency players in a response operational mode.

4.8.1 Protective Actions The State of Iowa uses the following criteria in deciding upon specific protective actions during a radiological emergency:

1) EPA Manual of Protective Actions Guices and Protective Actions for Nuclear Incidents; and

2) Food and Drug Administration guidance regarding contamination of human food and animal feeds published in the Federal Register on l October 22, 1982.

The Governor, or in his absence, his designee, will make all protective action decisions (sheltering, evacuation) . These l 1( decisions will be coordinated with the local government entities involved.

4.8.2 Iowa Office of Disaster Services I The Iowa Office of Disaster Services shall coordinate all activities of State agencies and departments, all local governments, and the utility l In support of emergency response activities. These activities shall be coordinated fIom the Iowa State EOC in Des Moines.

4.8.3 - The Iowa Commissioner of Public Health, or his designee, from the l Iowa State Department of Health.

The Iowa State Department of Health shall alert the State Hygienic >

Lab when emergency action conditions are reported by a commercial nuclear power - reactor, which impacts upon the public health and safety in Iowa, and when emergency team response has been determined to be necessary or imminent. They shall perform necessary calculation and evaluate the impact of existing and projected radioactivity releases in terms of public health risk. They shall translate the evaluation of existing and '

projected environmental contamination and resulting dose into terms of i alternative protective actions. They shall recommend appropriate protective actions to the Governor's Office, the Iowa Office of Disaster Services, and other State agencies as appIcpriate.

s.

. 4-69

i

~

l i

April, 1984 4.8.4 State Hyclenic Lab (SHL) Revision 4 The State Hygienic Lab, located in Iowa City, Iowa shall: conduct  ;

and coordinate all field surveillance and monitoring activities directed c

L toward measuring radiation exposure and radioactivity contamination in i f the environment resulting from an accident at a commercial nuclear power >

reactt samplingr; provide and coordinate laboratory support of all environmental !

and radiological monitoring activities during a emergency; communicate all relevant data and protective nuclearaction l

recommendations to the State Department of Health of the Des Moines EOC; provide radiological laboratory support for environmental samples ,

analysis; and provide recommendations for decontamination of contaminated area. .

1 i

4.8.5 Iowa Department of Water, Air, and Waste Management the This agency shall provide first and primary alert notification to Federal EPA; prepare environmental advisories to public -water stoplies; provide primary coordination of disposal of contaminated ,

materials; and provide primary control of public water supplies.

During a serious radiological emergency at the Quad Cities Nuclear Power Station, an Emergency Operating Center shall be activated at the Scott County Courthouse, basement, in Davenport, Iowa. The Director, .or

\

designee, of the State Hygienic Lab shall contIo1 environmental sampling, conducted by a number of radiological monitoring teams from this emergency operations center. Also, during an emergency co,mmunications shall be established and ongoing between the Iowa Office of Disaster Services in Des Moines, the Illinois Department of Nuclear Safety in Springfield, Illinois, the Scott and Clinton County EOC's, and the Utility, for the purpose of mutual cooperation between Illinois and Iowa with regard to radiological assessment efforts.

4.8.6 Local Government Local governments are responsible for overall emergency preparedness at the local level. This includes' preparation of emergency plans, and designation of assembly areas and congregate care facilities within jurisdictional areas. The local governments are responsible for l inplementing the actual protective actions taken, including evacuation.

f .

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April, 1984 Revision 4 4.9 The State of Wisconsin A portion of the Emergency Planning Zone for the Zion Nuclear Station lies within the State of Wisconsin. The State of Wisconsin has developed a " State of Wisconsin Peacetime Radiological Emergency Response Plan." This section provides a summary of the essential elements of the Wisconsin emergency plan.

4.9.1 Concept of Operations Initially, responsibility for responding to a radiological emergency, including evacuation, rests with local governments and

their emergency services. Notification, by either local authorities or legal possessors of uncontrolled materials, to the Division of Emergency Government (DEG) that a radiological emergency exists will bring in the resources of the Division of Health, Radiation Protection Section to assess and evaluate the situation and determine protective action. State agency . notification for assistance and coordination of response operations of the state agencies in support of local government will be performed by- the DEG as determined by the Governor.

4.9.2 Division of Emergency Government 4

The OEG is to provide the principal support response to emergencies in the State of Wisconsin, coordinate the responses of other state agencies, brief the Governor of emergency situations, and= activate the State Emergency Operating Center in Madison, if necessary.

4.9.3 Division of Health

'For peace time radiological emergencies, the Bureau of Health has designated the Chief of the Radiation Protection Section as the State Raolological Cooroinator (SRC) for the State Radiological Response (RAD RESP) Team. Team members are personnel of the section, as designated by the SRC, augmented by selected personnel from the DEG and other state and local agencies trained specifically for radiological incidents.

" Environmental sampling conducted by the State of Wisconsin following a serious radiological emergency will be coordinated from the Madison EOC by the SFtC or his designated alternate. In the case-of a serious radiological emergency at Zion Station, communications  !

shall be maintained between the Madison ECC and the Illinois Department of Nuclear Safety, in Springfield, Illinois for the

, purpose of mutual cooperation between Illinois and Wisconsin with regard to radiological assessment efforts.  !

k 4-71 1 ,

April, 1984 Revision 4 The State of Wisconsin utilizes guidance promulgated by the U.S. Environmental Protection Agency and the U.S. Department of Health and Human Services as the basis for determining what protective actions are necessary during a radiological incident.

4.9.4 Kenosha County Kenosha County will provide a coordinated local government response in conjunction with State, from the County Emergency Operating Center in Kenocha.

4

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t 4-72 b

, .. _ _ , _ _ - . . . - - . - - _ _- -y-- . _ _

April, 1984 Revision 4 4.10 American Nuclear Insurers (ANI) '

In early 1982, American Nuclear Insurers (ANI) issued Bulletin

1. 58 (81) " Accident Notification Procedures for Liability Insureds" ;

which provides revised criteria for the notification of the Pools in the event of a nuclear emergency at one of the liability insured nuclear power reactor sites. This revision brings the ANI/MAELU I (Mutual Atomic Energy Liability Underwriters) notification criteria !

into alignment with the standard emergency classificaton system I

, adopted by the nuclear industry. This document also identifies a i suitable channel for follow-up communication by ANI after initial '

notification.

4.10.1 ANI/MAELU Emercency Assistance In the event of an extraordinary nuclear occurrence (as i defined in the Price-Anderson Law) ANI and MAELU (the pools) have plans prepared to provide prompt emergency funding to affected

, members of the public.

4.10.2 ANI/MAELU Emergency Assistance (Claims Handling Procedures) 4 The pools' emergency assistance arrangements contemplate the

• i mobilization and dispatch of emergency claims teams to directly dispense emergen' c y assistance funds to affected members of the public.

i

The pools should be notified in the event of a nuclear emergency requiring notification of State - or Feoeral governmental agencies, or if the insured believes that off-site' persons may be i affacted and finarrial assistance of a nature discussed may be -

1 required. In these instances ANI expects notification as soon as.

possible after the initiation of the emergency. To be consistent with industry classificaton systems, the Commonwealth Edison GSEP notification of the pools in the event of an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY should be within eight (8) nours.

To assure operability of communication techniques and !

equipment ANI will also be notified of exercise scenarios that use '

the same type of classifications. Even if it appears to be remote !

that off-site persons will be affected, the pools should be notified !

in order that response plans can be initiated to the point of alerting teams of adjusters to stand by. Response activity can be '

discontinued if it proves less severe and does not reqJire pool ;

response.  !

All nuclear occurrences of an emergency or non-emergency nature which fall under the nuclear liability policy should be reported formally in writing to ANI by the Commonwealth Edison Insurance Administrator.

-l v

4-73

April, 1984 Revision 4 4.10.4 Emergency Notification and Follow-up Procedures In the event of an emergency clear lines of communication have been established between each station Emergency Operations Facility / Corporate Command Center and ANI in order to exchange all required information during a developing emergency situation.

ANI maintains 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> coverage of an emergency notification number. During normal office hours (8:00 am - 4:00 pm) their number will be answered by the receptionist who will transfer an incoming l emergency call to an appropriate individual in the office. Outside of normal office hours this phone line is covered by an answering service. The answering service will intercept the call and obtain j the name, affiliation and phone number of the caller. They will then -

notify a designated ANI staff member who will in turn call back the '

facility to obtain appropriate information regarding the nuclear j accident. ,

i In order that follow-up information is available to the pool !

Commonwealth Edison Company has established the Recovery '

Manager / Corporate Command Center Director or their designee as a point of contact that ANI personnel may use to update themselves regarding the status of the emergency.

Q, Am 4-74 e

April, 1984 Revision 4 5.0 CLASSIFICATION OF EMERENCY C0tOITIONS Tre GSEP describes six mutually exclusive classifications for emergency l conditions, covering the postulated spectrum of emergency situations.

Each of the five (5) emergency classifications are characterized by Emergency Action Levels, or initiating conditions. These initiating conditions for the most part, have been selected so as to not infer any 1 mediate need to implement protective actions, but rather to ensure adecuate time is available to confirm inplant readings by implementing assessment measures.

This section describes the GSEP emergency classification system and gives generic example initiating conditions for each class. Additionally, the GSEP Station Director / Corporate Command Center Director / Recovery Manager may declare an incident to fall within a specific emergency classification if it is decided that the incident is of equivalent magnitude to the criteria used to define the emergency class. Each of the first five classifications is associated with a particular set of imediate actions to be taken to cope with situations (These actions are described in Section 6.0).

In accition to the emergency classifications used to describe a developing emergency, guidance is provided for downgrading an accident classification, if warranted, until TERMINATION of the incident is possible. ,

When the emergency - condition no longer exists and return to normal plant operation status is imminent, then the emergency. shall be TERMINATED.

Termination may be performed from any of ,the five classifications .or the Recovery Phase.

Refer to the following tables:

1) Table 5.0 Description of Transportation Accident

2) Table 5.0 Description of Unusual Event

3) Table 5.0 Description of Alert

4) Table 5.0 Description of Site Emergency

5) Table 5.0 Description of General Emergency

6) Table 5.0 Description of Recovery

7) Taole 5.0 Emergency Action Levels fer Radioachvity In Licuid Effluents.

As a minimum, site specific annexes conditions given in tables 5.0-1 to 5.0-5, shall ano whe- includewill possible, apolicable relate initiatin those ccnditions with plant instrumentation reach,4. In soce instances, it i may be inapprcpriate for a particular station t acept initiating conoitiens

~ s' exactly. equivalent to those conditions speci ad in this generic plan. In adcition to the initiating conoitions giv' in this generic GSEP, site specific annexes snould categorize postu ueo accicents contained in the

• Stations' Final Safety Analysis Reports.

5'

-s April, 1984

. TABLE 5.0-1 OESCRIPTION OF TRANSPORTATION ACCIDENT A. CLASS DESCRIPTION

, This class involves an accident involving the transportation of radioactive or other hazardous material from a nuclear station or other location where CECO is the shipper.

B. RELEASE POTENTIAL Depending on the materials involved and the type of accident, there is a wide range of possible releases, i.e., the accident could be of almost any severity.

C. INITIATING CONDITIONS

1. A vehicle transporting radioactive materials or nonradioactive hazardous materials from a nuclear station is involved in a situation in which:

a. Fire, breakage, or suspected radioactive contamination occurs f involving a shipment of radioactive material; or

b. As a cirect result of any hazardous haterials:

o A person is killed o A person receives injuries requiring hospitalization a Estimated carrier or other property damage exceeds $50,000.

2. Any other condition of equivalent magnitude to the criteria used to define this category, as determined by the Station Director or the Corporate Command Center Director.

e L .

i 5-2

April, 1984 Revision 4 TABLE 5.0-2 DESCRIPTION OF UNUSUAL EVENT A. CLASS DESCRIPTION 1

This class involves events which indicate a potential degradation of the level of safety at a nuclear station. The situation may or may not '

have caused damage to the plant, but if there is damage, it does not necessarily require an immediate change in plant operating status.

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

C. INITIATING COPOITIONS

1. An aircraft crash or other missile impacting onsite from whatever source.

2. Earthquake being experienced at less than or equal to Opereting Basis

• Earthquake (OBE) levels.

3. Explosion causing damage onsite but not affecting plant operation.

4. Fire requiring offsite assistance but not affecting plant operation.

5. Flood being experienced (e.g., rupture of cooling pond dike affecting '

offsite property).

6. Tornado nearby that cou15 potentially strike the facility.

7. Toxic gas incident observed near or onsite.

8. Security threat (event) which also poses a radiological threat, or has i the potential for substantial degradation of the level of physical security at the station (Refer to Section 9.3 for more information with regard to the Station Security Plan).

9. Loss of required systems to the extent that a unit shutdown is required due to a Technical Specifications ACTION statement (such as for ECCS, fire protection systems, etc).

10. Loss of primary coolant indicated or probable due to:

a. An urplanned initiation of ECCS resulting in injection of coolant; or

b. Failure of a primary system safety valve to close; or 5-3

April, 1984 Revision 4 TABLE 5.0-2 (CONT)

c. Exceeding either primary / secondary leakage or primary sistem leakage rate limits as specified in the Technical Specification.

11. Rapid depressurization of PWR secondary side.

12. A gaseous effluent release greater than 10 UR 20 instantaneous I release limits but less than ten times the 10 CFR 20 instantaneous release limits (per 10 TR 20.105).

13. A liquid effluent release at levels indicated in Table 5.0-6,

14. Transportation of a radioactivity contaminated injured person to an offsite medical facility.

15. An incident in which, as a . direct result of hazardous materials, a person is killed or hospitalized or estimated property damage exceeds

$50,000.

16. Any other condition of equivalent magnitude to the criteria used to define this category, as determined by the Station Director /CCC l c Director / Recovery Manager.

5-4

n April, 1984 Revision 4 TABLE 5.0-3 OESCRIPTION OF ALERT A. CLASS DESCRIPTION This class describes events which involve actual or potential substantial degradation of the level of safety at a nuclear station. An Alert situation may be brought on by either manmade or natural phenomena and can reasonably be expected to occur-during the life of the plant.

B. RELEASE POTENTIAL Dose equivalents up to the lower EPA Protective Action Guides (1.0 rem whole body or 5.0 rem thyIoid) are possible.

C. INITIATING CONDITIONS

1. Aircraft crash or other missile impacting onsite and affecting plant operation (e.g., requiring a unit shutdown due to an ACTION statement of the Technical Specifications).

2. Earthquake being experienced at levels greater than Operating Basis Earthquake (OBE) levels. *

3. Explosion causing damage to facility and affecting plant operation (e.g., requiring a unit shutdown due to an ACTION statement of the Technical Specifications).

4.

Fire requiring offsite assistance and affecting plant operation (e.g.,

requiring a unit shutdown due to an ACTION statement of the Technical Specifications).

5. Flood near design levels.

6. Tornado striking facility or sustained winds near design levels.

7. Toxic gas entry into the facility at life threatening levels but not affecting vital areas.

8. Evacuation of Control Room anticipated or required with ccntrol of shutdown systems established from local stations within 15 minutes.

9. An ongoing security threat (event) of ircreasing severity, or a different threat, which involves actual or potential substantial degracation of the level of safety of the station from either the radiological or abysical security point of view.

4

10. Loss of cffsite power to the onsite Class I (one) 'E' distribution systems and all diesel generators inoperable as per the Technical

% Specifications for less than or equal to fifteen (15) minutes. l 5-5 t

f April, 1984 Revision 4 TABLE 5.0 3 (CONT)

11. Loss of vital DC power for less than 15 minutes.

12. Loss of plant shutdown systems:

a. Loss of all systems capable of maintaining cold shutdown; or

b. Failure of the Reactor Protection System to initiate and complete a reactor trip which brings the reactor subcritical.

13. Loss of required systems addressed in the Technical Specifications to the extent that an immediate unit shutdown is required.

14 Loss of one of the following three fission pIoduct barriers:

a. Cladding

b. Reactor Coolant System

c. Primary Containment

, 15. Loss of primary coolant indicated by a reactor coolant system leakage

( increase greater than 50 gpm.

16. Significant primary to secondary leakage for a PWR due to a failure of steam generator tubes (Significant per Tech. Spec. Limits). l

17. Fuel damage accident with release of radioactivity to containment or fuel handling building. *

18. A gaseous effluent release greater than ten times the 10 CFR 20 instantaneous release limits (per 10 CFR 20.105).

19. A 11guld effluent release at levels indicatet.1. Table 5.0-6.

20. An activity in the containment which, if released under erst case meteorological conditons, muld result in an offsite dose equivalent of greater than 50% but less than or eocal to the lower EPA Protective Action Guides (1.0 rem whole body or 5.0 rem thyroid).

21. Any other condition of equivalent magnitude to the criteria used to define this category, as determined by the Station Director /CCC [.

Director / Recovery Manager. I

\ .#

5-6

l l April, 1984 i Revision 4 TABLE 5.0-4 DESCRIPTION OF SITE EMERGENCY A. CLASS DESCRIPTION This class describes events which involve major failures of plant functions needed for the protection of the public.

8. RELEASE POTENTIAL Dose equivalents up to the upper EPA Protective Action Guides (5 rem l whole body or 25 rem thyroid) are possible.

C. INITIATING C0tOITIONS

1. Aircraft crash or other missile impacting onsite, affecting vital structures, and requiring an immediate unit shutdown.

2. Earthquake being experienced at levels greater than Safe Shutdown Earthquake (SSE) levels with a unit not in cold shutdown or refueling.

3. Explosion causing severe damage and requiring intnediate unit shutdown.

4. Fire requiring offsite assistance and requiring immediate unit shut-down.

5. Flood exceeding design levels.

6. Sustained winds exceeding design levels.

7. Toxic gas entry into vital areas at life threatening levels.

8. Evacuation of Control Room and control of shutdown systems not established from local stations within 15 minutes.

9. Security threat involving an imminent loss of physical control of the facility.

10. Loss of offsite power to the onsite Class. I (one) 'E' distribution systems and all diesel generators inoperable as per the Technical Specifications for greater than fifteen (15) minutes.

11. Loss of vital DC power for more tnan 15 minutes. ,

12. Loss of all systems capable of naintaining hot shutdown.

• \

5-7

._. _ - / _ _ - -_ _ _ _ . - . _. _. . ,_

r_

April, 1984 Revision 4 TABLE 5.0-4 (CONT)

13. Loss of two of the following three fission product barriers:

a. Cladding

b. Reactor Coolant System

c. Primary Containment

14. Loss of primary coolant

a. (8WR) reactor coolant system leakage increase greater than 500 gpm; or

b. (BWR) main steam line break outside containment without isolation; or

c. (PWR) reactor coolant system leakage increase greater than make-up capacity; or

d. (PWR) steam line break with greater than. 50 gpm primary to

seconday leakage and indication of fuel damage.

15. Severe primary to secondary leakage for a PWR due to a failure of steam generator tubes.

16. Major damage to spent fuel in containment or fuel handling building.

17. Effluent monitors-detect levels corresponding to greater than 50 mR/hr

, for 1/2 hour g greater than 500 mR/hr whole body for two minutes at the site boundary for worst case meteorological conditions.

18. A liquid effluent release at levels indicated in Table 5.0-6.

19. An activity in the containment which, if released under worst case meteorological conditions, would result in an offsite dose ecuivalent greater than the lower EPA Protective Action Guides (1.0 rem whole body or 5.0 rem thyroid) but less than or ecual to the upper EPA PIotective Action Guides (5.0 rem whole body or 25 rem thyroid).

20. Any other condition of ecuivalent magnitude to the ~ criteria used to define this category, as determined by the Station Director /CCC l Director / Recovery Manager. I 5-8

April, 1984 Revision 4 TABLE 5.0-5 DESCRIPTION OF GENERAL EMERGENCY A. CLASS DESCRIPTION This class involves events which involve actual or imminent substan-tial core degradation or melting with the likelihood of a related release of appreciable quantitles of fission products to the environment. This class is characterized by offsite consequences requiring protective measures as a matter of prudence or necessity.

8. RELEASE POTENTIAL Oose equivalents greater than the upper EPA Protective Action Guides (5 rem whole body or 25 rem thyroid) are possible for the offsite public.

C. INITIATING CONDITIONS

1. Security threat involving a loss of physical control of the facility.

2. Loss of tw of the three fission product barriers with an imminent loss of the third fission product barrier:

a. Cladding

b. Reactor Coolant System

c. Primary Containment

3. Effluent monitors detect levels corresponding to greater than 1 rem /hr whole body at the site boundary under actual meteoIological conditions.

4. A 11guld effluent release at levels indicated in Table 5.0-6.

5. Concurrent with a potential failure of containment which, activity in the containment, if released under wrst case meteorological conditions would result in an offsite dose equivalent greater than the upper EPA Protectiv'e Action Guides (5.0 rem whole body or 25 rem thyroid).

6. Any other condition of equivalent magnitude to the criteria used to define this category, as determined by the Station Director /CCC Director / Recovery Manager.

A 5-9

April, 1984 Revision 4 TABLE 5.0-6  !

DESCRIPTION OF RECOVERY A. CLASS DESCRIPTION This section describes criteria to be considered prior to reclassification of the emergency class to RECOVERY PHASE.

Emergency classifications are used to protect the health and safety of the public, the environment, the emergency workers and the plant equipment by ensuring that commensurate levels of response personnel are activated. They are declared as the emergency develoos.

However, once the public and environment have been adequately protected, the plant has been stab 11 zed, contained, and contIulled, the Recovery phase can be established.

The Recovery phase is that period when major repairs are being performed to return the plant to operation. The emergency condition no longer exists. It is the responsibility of the -

Recovery Manager, plant conditions warranting, to establish the Recovery phase after consultation with cognizant governmental agencies and other parties.

Establishment of a Recovery phase can occur frorf, any '

Emergency Classification Level. When normal operations are ready to resume the emergency situation will be TERMINATED.

8. RELEASE POTENTIAL Since the potential of releasing activity depends upon plant parameters and equipment, the establishment of a Recovery phase "

should not occur as long as uncontrolled releases are, or will occur. As long as offsite doses or dose projections remain above the PAG's due to plant conditions the Recovery phase should rot be established. The potential for uncontrolled releases should be negligible and plant' conditions stabilized before a Recovery may be established. t C. INITIATING CONDITIONS  ;

The following conditions are to 'be guidelines for determination of the oossibility for establisning a Recovery. The purpose of a Recovery is to terminate the emergency, provide the necessary manpower to handle the long term activities, and to return the plant to an acceptacle cordition. ,

, Establishment of a Recovery Phase should consider but not be limited to the following: t

1. Is the health and safety of the public adequately established?

2. Have plant parameters and equiptrent status been stabilized,  ;

anc controlled?

• 5-10

April, 1984 Revision 4 TABLE 5.0-6 (CONT) '

3. Have any uncontrolled gaseous releases to the environment been terminated?

4. Has the environment been monitored?

5. Have CECO workers been protected?

6. Has any security threat been neutralized, and/or is plant security under the direction of CECO personnel?

^

7. Have effluent monitors returned to acceptable levels?

8. Have any uncontrolled liquid releases been terminated?

9. Have core coverage and containment integrity been restored?

10. Are plant safety systems operable? *

11. Has the fuel pool been damaged, or spent fuel damage been contained and controlled?

12. Has excessive primary and/or secondary containment leakage e

been secured end controlled?

13. Is containment activity reduced to levels below that requiring protective actions?

14. Are plant conditions, parameters, systems, or equipment restored and/or replaced such that PAG's are ro longer i applicable?

l, s 15. Has the fire been extinguished?

16. Is the earthquake over?

17. Have adverse environmental conditions at the plant site been terminated? '

. i

18. Have flood waters subsided below EAL's?

19. Conditions as described in Tables 5.0-1, -2, -3, -4, or -5 that have initiated the emergency condition have been '

contained, controlled, eliminated or stabilized such that the classification is no longer spplicable. l

20. Has any otner condition of equivalent magnituce to the ,

criteria used by the Station Director /CCC Director / Recovery Manager to classify an emergency been determined to no longer be applicable? ,

I 5-11

4 CSEP CLASSIFICATION _

BASIS EE RGE E Y ACTION LEVELa G OSS BETA /G4 NR TRITILM (PWI)

LNUSUAL EVENT Parallel logic to the NRC CAL for airborne release:

Y.S. limit sRelease < 10xT.S. limit lx10-7 sC(uC1/ml)<10-6 3x10-3 SC(oC1/ml)<3x10-2 ALERT Lower limit based on EPA's suggested 10 mren whole body 40$A(C1) <2000c 500 sA(C1) < 20,000 limit for drinking water alert * $

1evel b g l$per limit based on FDA's pre-ventive level of 500 mree whole k g

body m m m M p5-*

Release 210 x T.S. limit C(uC1/ml)210-6 C(ucl/ml)23x10-2 gm z -e ui SITE EERGEOf Lower limit based on FDA's C $'p

! preventive level g, 9 Upper level based on FDA's 2000 $A(Cl) <20,000 2x104 s A(Cl) <2x105 h emergency level of 5000 mrea whole body hb r

GENERAL EE RGE E Y In excess of FDA's emergency A(Cl) >2x104 A(C1) >2x105 level O EALs are measured or estimated to be in discharge water flow, b Unofficial EPA guidance.

• c Assumptions: ,

g

. Water dllution of 1010 liters (typical for any station). EE

. Weighted concentration limit of 0.2 (C1/1 for FDAs preventive level (assumes a mixture of 8 14 each I-131, Sr-90; 10E Sr-89; 444 each Cs-134, Cs-137). *j

. Dose from Cs-134 is twice that from Cs-137 per unit of activity consumed.

C = Concentration (microcuries/ milliliter) A = Activity in Curles

April,1984 Revision 4 5.1 Guidance For Downgradino Of Classification Downgrading of the emergency classification may occur if conditions in the. plant have substantially changed so as to_ alter the condition for the potential of releasing activity to the environment. If the offsite dose equivalent and/or dose equivalent projections have been reduced , to a value within . a lower emergency classification, the actual classification may be downgraded to a lower level.

The purpose of downgrading the classification is to identify accurately k

the: emergency, and to allow Federal, State. and local officials to provide the necessary manpower to handle the current emergency condition.

4 Downgrading of the emergency classification may occur when conditions

- exist such that a lower level of classification would be appropriate.

1 Once a downgra< ing has been evaluated and established by the Station Director / Recovery Nneger/ Corporate Command Center Director the appropriate authorization level must report this action in accordance with established reporting procedures.

Figure 5.1-1 depicts the upgrading, cowngrading, terminating concepts

- (see Section 5.2), and returning the plant to its normal _ operational condition.

'This figure' indicates that ag emergency classification may be reclassifield directly to any other emergency classificationi either upgrading to a more

severe, or downgrading to a less severe emergency classification. It is also i possible to change from g emergency classification to " Recovery" or from

" Recovery" back to any emergency classification. This figure also permits an event to change from any emergency classification directly to " Normal Operations" without going through a " Recovery" if conditions permit.

I i

A 5-13

April, 1984 5.2 Guidance For Termination Of Emergency edsion 4 The purpose of terminating an emergency is to provide an orderly turnover of plant control from the GSEP organizations to the normal Commonwealth Edison plant organization. Termination of the emergency is declared by the person in charge: Recovery Manager, Corporate Command Center Director, or Station Director. Termination may occur from any Emergency Classification or from Recovery.

Termination of the emergency should consider but not be limited to the following:

1. Has the potential for activity release been adequately controlled?

2. Have off-site dose equivalent and/or dose equivalent projections been reduced to acceptable levels for public exposure?

3. Have plant parameters returned to acceptable conditions for normal plant organizational control?

4. Have conditions that initiated the emergency been mitigated?

5. Have appropriate Feoeral, State and local authorities been notified?

4 I

i 5-14 y . , - - - - - , - ,

I

4 i FIGURE 5.l-1

! EMERGENCY CLASSIFICATION CHANGE FLOW CHART

! RECLASSIFICATION OF EMERGENCY RECLASSIFYING EMERGENCY TO REC 0VERY Upgrading l

Emer nc Recovery Downgrading 'i' i

c h

.o.

E i .e General .

) =

3 Emergency b $$

M Sit l h Emergency j'y

' E Recovery E!:

Phase 8e Alert y I

l Unusual

Event TERM TE N 0 R M A L -

p - 0 P E R A T I 0 N l REC i

i TIME -->

April, 1984 Revision 4 6.0 EMERGENCY MEASURES This section discusses guidelines for Commonwealth Edison's 6.1 Emergency Response Actions 6.2 Assessment Actions 6.3 Protective Actions for the offsite Public 6.4 Protective Actions for Onsite Personnel 6.5 Aid to Affected Onsite Personnel Included are graphic and textual descriptions of preplanned organizational structures for notification of responsible agencies that an emergency has been declared at a nuclear power station. This section identifies communication flow paths for the rapidly developing emergency when only station personnel are available for evaluations and notifications. These same communication flow paths are used with additional requirements for the slowly developing emergency when . additional Commonwealth Edison emergency response organizations are available for evaluations and notifications. This section identifies notification schemes for the five (5) emergency classes as listed in Section 5.0 as well as the actions for Recovery, and Downgrading of the Emergency classes.

Throughout each emergency situation, continuing accident assessment will occur; therefore, a generic description of equipment and systems available for

( ,these actions is provided within this section.

protective &ctions for the public are based upon actual, potential, or imminent release of radioactive materials. Guidance on recommended protective (

actions, notification schemes, and re-entry to evacuated areas is provided.

and For onsite personnel, guidance is provided regarding protective equipment personnel accounting depending upon their location. Also given is guidance for radiation exposure, decontamination and first aid, and medical transportation and treatment.

i-4 5

6-1

April, 1984 Revision 4 -

6.1 Commonwealth Emergency Response Actions During an emergency situation at one of its nuclear stations, '

Commonwealth Edison has the responsibility to implement appropriate -

emergency measures. These measures include:

o Notification of responsible authorities;

o. Activation of the GSEP organization; o Assessment of the emergency situation; reference Figures 6.3-1 & -2.

o Initiation of actions to correct or mitigdte an emergency at or near the source of the problem; o Recommendation of protective actions for the offsite public; reference Tables 6.3-1 and 6.3-2. l, o Initiation of protective measures for onsite personnel; and o Provision of aid to affected onsite personnel.

When Commonwealth Edison initially notifies State or local authorities of an emergency condition, the following information should be transmitted as a minimum:

1) Name and title of the reporting person;

2) Location and type of incident (i.e., the emergency classification);

• r

3) Date and time of incident;

4) Whether a release of radioactive material is taking place;

5) Potentially affected population and areas;

6) Whether protective measures may be necessary; and

7) Verification to confirm authenticity of call.

Figure 6.1-1 (A), (B), (C), & (D) shows the initial notification scheme for declared GSEP emergencies.

6-2 s

, , . ~ . . - - - - . _* - . , - , . , , _ _ , , _ , , , . - .- . . , _ . - - - , . -

April, 1984 -

Revision 4 Followup messages to State and local authorities shall contain the following information if it is known and appropriate:

1) Type of actual or projected release (airborne, waterborne, surface spill), and estimated duration / impact times;

2) Estimate of quantity of radioactive material released or being released and the points and height of release;

~

3) chemical and physical form of released material, including estimates of the relative quantities and concentration of noble gases, iodines, and particulates;

4) Meteorological conditions at appropriate levels (wind speed, direction (to and from), indicator of stability; form of precipitation, if any);

5) Actual or projected dose rates at site boundary; projected integrated dose at site boundary;

6) Projected dose rates and integrated dose equivalent at the l projected peak and at about 2, 5, and 10 miles, including sector (s) affected; *

(

7) Estimate of any surface radioactive contamination inplant, onsite, or offsite;

8) meergency response actions underway;

9) Recommended emergency actions, including protective measures;

10) Requested onsite support from offsite organizations; and

11) Prognosis for worsening or termination of event based on plant information.

llaj.gr comunonwealth emergency response actions for upgrading to each emergency class are identified in Table 6.1-1 through Table 6.1-5 as indicated below:

1) Table 6.1 Actions for Transportation Accident;

2) Table 6.1 Actions for Unusual Event; j 3) Table 6.1 Actions for Alert;

4) Table 6.1 Actions for Site anergency;

_ 5) Table 6.1 Actions for General Emergency.

l f

Commonwealth Edison company actions for downgrading an accident and

!' for entering the recovery phase are given in Tables 6.1-6 and -7.

Figure 6.1-2 gives the sectors and zone designators that are used at each i

nuclear station.

6-3 i

FIGURE 6.1-1 (A)

SIMPLIFIED

EMERGENCY NOTIFICATION SCHEDULE TRANSPORTATION ACCIDENT t

ND0/CCC INPO Voluntary

SPS0 Director Assistance Program INARS)

Station ESDA

, ANI i Director DNS i

(RED) i i

4 i

U.S. 00T EE l

5. ;1 i

i E'

a-OUT - Of- STATE State Emergency Service Agency

• y 1 -

() INDICATES TYPE OF PHONE SYSTEM APPLICABLE FOR NOTIFICATION - UNLESS OTHERWISE NOTED, A STANDARD Pil0NE SYSTEM IS APPROPRIATE

.I I

FIGURE 6.1-1 (B)

SIMPLIFIED EMERGENCY NOTIFICATION SCHEDULE ueIUSUAL EVENT mummma SPS0 n===== ND0/CCC Director Station ESDA Director (NARS) l (RED) =mumme DNS

NAWAS NRC l Notificolion - Wisconsin or Iowa State Authorities mammmma Wisconsin or Iows Local Agencies i Zies Only i

e

[ ALERT SPS0 ;ND0/CCC Director summma Recovery Monoger l;

I a a Station (NARS) l DNS Director i

llNPO l l ANI

" Local lilinois Agencies l

l~ ED) ESDA

NAWAS NRC i

a:- W,-,. . . S ... -t , - W , - ,a . . . L . ., - .s E8 W

BL

• • I

( ) Indicates type of phone system opplicable for notification - unless otherwise noted, a stonderd phone system is appropriole

FIGURE 6.1-1 (C)

SIMPLIFIED EMERGENCY NOTIFICATION SCHEDULE SITE EMERGENCY +----------------------- bl Before the of fsite GSEP Orgenizet'en is activeled) un'unes' SPSO l ND0/CCC Director summmmma Recovery Monoger I

f;',' ,'," _

DNS i l ED) ESDA Local lilinois Agencies l NAWAS NRC

• blification A"'h 'i'i """ I'** l'I A " **I

4

• I*"' " I'** S' *II" Zion Only StTE EMERGENCY 4 ------------------------>( Alter the offslie GSEP Orgonizelion in activeted)

NHC, Region III i M ,SPS0 (GSEP) l(RED) (NARS)

Station Recovery Manager Local lilinois Agencies

' ESDA Director l ED)

- DNS NAWAS NRC I

Notification n===mmma Wisconsin or Iowa State Authorities U'

! Zion Only I 1 g

",I 1 llNP0 l AN1' g;,,,,g , g g ,;  ;

)

o

( ) Indicates type of phone system opplicable for notification - unless otherwise noted, o stonderd phone system is oppropriate l

. FIGURE 6.1-1 (D)

SIMPLIFIED EMERGENCY NOTIFICATION SCHEDULE U--------------->(Before the offsite GSEP Orgemisetion is_,, acti4eledI GENERAL EMERGENCY 4---

f;I',9

SPS0 LND0/CCC Director Recovery Monoger l

! j ED) ESDA I

E NAWAS NRC INPO l ANI l '

Notification DNS Zion Only Local Illinois Agencies Wisconsin or Iowa State Authorities e

Wisconsin or Iows Local Agencies 4

--> ( Af ter the ofIsite GSEP Organirolion is activated)

GENERAL EMERGENCY 4------------------

NRC, Region III 5 l(RED) (NARS) (NARS) g,gg ,,g, g g,,

(GSEP)

Station 1 Director .p

<~

l (RED)

CCC Director

, DNS UTx g-NAWAS NRC g aw I Notification . Wisconsin or Iowa State Authorities a,. y I

Zion Only I [ '

INPO ANI Wisconsin or Icwo Local Agencies

( ) Indicates type of phone system opplicable for notification -unless otherwise noted, o 'stonderd phone system is oppropriate

April, 1984 Revision 4 FIGUR,E 6. l-2 -

SECTOR AND ZONE DESIGNATORS 326.25 R

^ B 33.75 h NNW NNE C 303.75' 56.25*

NW NE P D 281.25 78.750 N WEST I I EAST [ .

2mi 258.75' 101.250 WSW ESE M Smi F

236.25, sw SE SSW

{ SOUTH SSE G

213.75 KM 191.25' 168.75' H '46 25 4

6-8

April, 1984 Revision 4 TABLE 6.1-1 COMMONWEALTH ACTIONS FOR TRANSPORTATION ACCIDENT

1. STATION DIRECTOR *(Reference Figure 6.1-1A) l

a. Declare Transportation Accident Condition.*

b. Notify System Power Dispatcher.

c. Notify the NRC Operations Center.

d. Notify the following agencies:

o The United States Department of Transportation ,

o The State and local emergency agencies nearest to the scene of the accident o The Illinois Emergency Services and Disaster Agency (if the accident occurred within the State of Illinois) o The Illinois Department of Nuclear Safety (if the accident occurred within the State of Illinois) o The Iowa Office of Disaster Services (if the accident occurred within the State of Iowa)

e. Activate those parts of the GSEP Station Group needed to meet the needs of the emergency.

f. Dispatch personnel for evaluation, if deemed necessary.

2. SYSTEM POWER DISPATCHER

.a. Immediately notify the Nuclear Duty Officer. l

3. NUCLEAR DUTY OFFICER / CORPORATE COMMAND CENTER DIRECTOR l

a. Activate those pa'rts of the offsite GSEP organization needed to meet the needs of the emergency.

b. Ensure that the following agencies were promptly notified of the emergency by the carrier and provide an update as appropriate:

o The American Nuclear Insurers o The United States Department of Transportation '

o The State and local emergency agencies nearest to the scene of the accident o The Illinois Emergency Services and Disaster Agency -(if the accident occurred within the State of Illinois) o The Illinois Department of Nuclear Safety (if the accident occurred within the State of Illinois) o The Iowa Office of Disaster Services (if the accident occurred within the State of Iowa)

c. Notify INPO regarding the Voluntary Assistance Program l

-*Since a Transportation Accident condition is an offsite occurrence, the Corporate Command Center Director may be notified of the emergency prior to a Station Director being notified; in that case, the CCC Director would declare the Transportation Accident condition.

6-9

4 April, 1984 l Table 6.1-1 (Cont.) ,

Each notification should have included:

o Name of reporter o Name and address of the carrier represented by the reporter.

o Phone number where the reporter can be contacted o Date, time, and location of incident o The extent of injuries, if any o The classification, name, and quantity of hazardous materials i involved, if such information is available o The type of incident and the nature of hazardous material i involvement and whether a continuing danger to life or health exists at the scene.

d. If deemed necessary, dispatch environmental monitoring teams or seek the aid of other emergency response organizations to assist in the field.

e. If the Transportation Accident occurs outside the Commonwealth Edison Company service territory and additional radiological assistance is necessary, contact the appropriate utility which has signed into the INPO Voluntary Assistance Agreement. ,,

4. OVERALL GSEP RESPONSE

a. Assess situation and respond,

b. Activate the Corporate Command Center as appropriate.

c. Initiate recovery measures in cooperation with State and local emergency personnel as appropriate.

1 e

6-10

i April, 1984 Revision 4 TABLE 6.1-2 COMMONWEALTH ACTIONS FOR UNUSUAL EVENT

l. STATION DIRECTOR (Reference figure 6.1-lb)  ! i

a. Declare an Unusual Event condition.

b. Notify System Power Dispatcher

c. Notify for Zion Station only: Kenosha Co. Wrn. Center, Wisconsin DEG.

and Waukesha Office. l

d. Notify the NRC Operations Center.

e. Activate those parts of the GSEP Station Group needed to meet the needs of the emergency.

i

2. SYSTEM POWER DISPATCHER

a. Inmediately notify the Nuclear Duty Officer.

b. If the Nuclear Duty Officer is not contacted within 5 minutes, notify i the organizations in 3.a. then resume trying to notify the Nuclear Duty Officer.

c. Perform the NARS notifications. s

3. NUCLEAR DUTY OFFICER / CORPORATE COMMAND CENTER DIRECTOR l

a. Ensure that the following organizations have been notified of the emergency:

o Illinois ESDA and DNS; o Scott /Clinton Counties (for QC Station only) o Iowa Office of Disaster Services (for Quad Cities Station only) '

o Wisconsin Division of Emergency Government (for Zion Station only).

o Kenosha County (for Zion Station only) *

b. Activate those parts of the offsite GSEP organization needed to meet the needs of the emergency.

c. Close out with a verbal summary to NRC, State of Illinois, and ,

contiguous State authorities as appropriate, or escalate to a more severe class.

4. OVERALL GSEP RESPONSE

a. Assess situation and respond,

b. Augment on-shift resources,

c. Recommend protective actions to ESDA/DNS and contiguous State authorities consistent with Figure 6.3-1 and Tables 6.3-1, 6.3-2, and 6.3-3.

9 6-11

, _ _ _ - - - . = . -

t April, 1984 '

Revision 4 TABLE 6.1-3 j

COPMONWEALTH ACTIONS FOR ALERT i

1. STATION DIRECTOR (Reference figure 6.1-lb) l .

• a. Declare Alert condition.

• b. Notify the System Power Dispatcher.

c. Notify . for Zion Station only: Kenosha Co. Wrn. Center, Wisconsin  !

DEG, and Waukesha Office.

,*d. Notify the NRC Operations Center. ,

e. Activate those parts of the GSEP Station group needed to meet the e

needs of the emergency.

f. Activate the TSC and OSC.

l 2.

SYSTEM POWER DISPATCHER (If the CCC/ EOF has not been activated)

a. Notify the Nuclear Duty Officer. k

b. If the Nuclear Duty Officer is not contacted within 5 minutes, notify t the organizations in 3.b then resume trying to notify the Nuclear l Duty Officer.

c. perform the NARS notifications. I

3. NUCLEAR DUTY OFFICER /NDORATE CC"""*"D CENTER DiwTOR

a. Perform actions la, Ib and Id if in command of the situation,

b. Ensure - that the following organizations have been notified of the emergency:

o Illinois ESDA and DNS; o Scott /Clinton Counties (for Quad Cities. Station only) o Iowa Office of Disaster Services (for Quad Cities Station only);

o Wisconsin Division of Emergency Government (for Zion Station j

. only);

o Kenosha County (for Zion Station only) o Institute of Nuclear Power Operations; {

c. Activate those parts of the offsite GSEP organization needed to meet the needs of the emergency. Activate the EOF Recovery Group if deemed necessary.

d. Evaluate emergency conditions, personnel requirements, health and safety aspects of the public, Commonwealth Edison Company personnel, plant status, and environmental conditions prior to briefing the NRC, State of Illinois, and contiguous State authorities as appropriate to escalate to a more severe class.

e. Evaluate emergency conditions, personnel requirements, health and L

• safety aspects of the public, CECO personnel, plant status, and environmental conditions prior to briefing the NRC, State Authorities (ESDA & DNS) of the recommendation for downgrading to a less severe class of emergency or to entering a Recovery Mode.

f. Notify ANI (Reference GSEP Section 4.10)  ;

• Actions la, -lb and Id are the responsibility of the Corporate command Center

. Director if the Corporate Command Center is activated and the CCC Director has assumed command..

t 6-12 ,

I

. . . . . . _ . - , _ _ , _ , _ . _ . _ _ _ . - _ _ _ _ _ . _ _ _ . . . _ . . , _ . . _ _ _ , ~ . _ _ _ _ . _ . , _ _ . _ _ - . . .

-e

, April, 1984 Revision 4 TABLE 6.1-3 (CONT)

4. OVERALL GSEP RESPONSE

a. Assess situation and respond,

b. Augment on-shift resources,

c. Activate the Corporate command Center, the TSC, and the OSC.

d. l Provide periodic plant status updates and meteorological information to ESDA/DNS and contiguous State authorities. If any releases are occurring, provide dose equivalent estimates for actual releases,

e. Recommend protective actions to ESDA/DNS and contiguous State authorities consistent with Figure 6.3-1 and Tables 6.3-1, 6.3-2, and 6.3-3.

f. Provide periodic plant and offsite status updates to ANI.

$. m ,

e s

6-13

I

~

April, 1984 Revision 4 -

TABLE 6.1-4 COB 990NWEALTH ACTIONS FOR SITE EMERGENCY t

1. STATION DIRECTOR (Reference figure 6.1-Ic) l

• a. Declare Site Energency.

• b. Notify the System Power Dispatcher.

c. Notify for Zion Station only: Kenosha Co. Wrn. Center, Wisconsin .

DeG, and Waukesha office.

• d. Notify the NRC Operations Center.  !

e. Activate the Station Group.

f. Activate the TSC and OSC. [

g. Dispatch personnel for environs monitoring if required. l

h. Call-in additional personnel as necessary.  !

1. -Initiate assembly and accountability of site personnel within the i protected area.

t j. Consider evacuation of non-essential personnel within the Protected  !

Area; evacuate them if there are no serious impediments to doing so.

2.

SYSTEM POWER DISPATCHER (If the CCC/ EOF has not been activated) I t

. a. Notify the Nuclear Duty Officer of the Site Emergency.

3 b. If the Nuclear Duty officer is not contacted within 5 minutes notify the organizations in 3.b then resume trying to notify the Nuclear Duty Officer.

r

c. Perform the NARS notifications. '

3.  !

NUCLEAR DUTY OFFICER /CN#0 RATE CC'"_*_"D CENTER Diner 7m/ RECOVERY M"MER

4. Perform actions la, Ib and ld if in command of the situation.

b. Ensure that the following organizations have been notified of the emergency:

o Illinois ESDA and DNS;  !

o Iowa Office of Disaster Services (for Quad Cities Station only);

' l o Scott /Clinton Counties (for Quad Cities Station only) o l Wisconsin Division of Emergency Government (for Zion Station only);

o Kenosha County (for Zion Station only)  !

o )  ;

Institute of Nuclear Power Operations (INPO).

c. Activate the total offsite GSEP organization, including the EOF t

Recovery Group.

d. Brief the NRC, State of Illinois, and contiguous State agencies as appropriate, to escalate to a General Emergency.

e. Evaluate emergency conditions, personnel requirements, health and safety aspects of the public Comunonwealth Edison Company personnel, plant status, and environmental conditions prior to briefing the NRC,  ;

State Authorities (ESDA & DNS) of the recommendation for downgrading  !

to a less severe class of emergency or entering a Recovery Mode.

! f. Notify ANI (Reference GSEP Section 4.10). ' l

• Actions la, Ib and Id are the responsibility of the Corporate Command -

Center Director or Recovery Manager if in command.

i I

6-14 '

I f

April, 1984 Revision 4 TABLE 6.1-4 (CONT)

4. OVERALL GSEP RESPONSE

a. Assess situation and respond.

b.

Augment the Tsc, theresources through Osc, and the EOF. activation of the Corporate Command Center,!

c. Dispatch environmental monitoring teams if deemed necessary. (At first these teams are under the direction of the Station Group; as soon as possible, direction shculd be transferred to a designated Environs Director.)

d. Provide periodic plant status updates and meteorological information to ESDA/DNS and contiguous State authorities. If any releases are occurring, provide dose equivalent estimates for actual releases,

e. Recommend protective actions to ESDA/DNS and contiguous State authorities consistent with Figure 6.3-1 and Tables 6.3-1, 6.3-2, and 6.3-3.

f. Provide periodic plant and offsite status updates to ANI.

6-15

l April, 1984 Revision 4 TABLE 6.1-5 COMMONWEALTH ACTIONS FOR GENERAL EMERGENCY

1. STATION DIRECTOR (Reference figure 6.1-Id)

• a. Declare a General Emergency.

• b. Notify the System Power Dispatcher.

• c. Notify the Illinois ESDA, and DNS, Wisconsin DEG (for Zion Station only), Iowa ODS (for Quad Cities Station only), and appropriate local authority of the emergency situation.

• d. Notify the NRC Operations Center.

e. Activate the Station Group.

f. Activate the TSC and OSC.

g. Dispatch personnel for environs monitoring if required. g

h. Call-in additional personnel as necessary.

1. Provide plant status updates to the state and local authorities (until this function can be performed by the CCC Director or the Recovery Manager.)

j. Assemble and evacuate non-essential personnel within the Protected Areas if not already done.

2. SYSTEM POWER DISPATCHER (If the CCC/ EOF is not already activated)

a. Immediately notify the Nuclear Duty Officer of the General Emergency.

3..

NUCLEAR DUTY OPPICER/ CORPORATE COMMAND CENTER DIRECTOR / RECOVERY MANAGER

a. Perform actions la, Ib, Ic and Id if in consnand of the situation.

b. Ensure that the Institute of Nuclear Power Operations has been informed of the appropriate classification.

c. Activate the total offsite GSEP organization, including the Recovery Group.

d. Brief the NRC, State of Illinois, local authorities, and contiguous State agencies, as appropriate of recommendation for downgrading to a less severe class of emergency or entering a recovery mode.

e. Notify ANI (Reference GSEP Section 4.10).

4. OVMRALL GSEP RESPONSE a.. Assess situation and respond.,

b. Augment resources through activation of the Corporate Command Center, the TSC, the OSC, and the EOP. l

• Actions 14, Ib, Ic and Id are the responsibility of the Corporate Command Center Director or Recovery Manager if in command.

6-16

April, 1934 Revision 4 TABLE 6.1-5 (CONT)

c. Dispatch environmental monitoring teams if required. (At first these teams are under the direction of the Station Group; as soon as possible, direction should be transferred to a designated Environs Director.)

d. Provide periodic plant status updates and meteorological information to RSDA/DNS and contiguous State authorities. If any releases are occurring, provide dose equivalent estimates for actual releases. l

e. Recommend protective actions to ESDA/DNS and contiguous State authorities consistent with Figure 6.3-1 and Tables 6.3-1, 6.3-2, and I 6.3-3.

f. Provide periodic plant and offsite status updates to ANI. l 0

3 N

6-17

f April, 1984 Revision 4 TABLE 6.1-6 COP 9tONWEALTH ACTIONS PCR RECOVERY

1. STATION DIRECTOR / CORPORATE COMMAND CENTER DIRECTOR / RECOVERY MANAGER l

After reviewing the guidance in Table 5.0-7.

a. Evaluate the status of this new classification and the j requirements to support this classification.  :

b. Declare the Recovery phase to be in effect. '

c. Notify the following:

o The System Power Dispatcher o The Illinois ESDA and DNS o The Iowa Office of Disaster Services (for Quad Cities Station ,

only) o The Wisconsin Division of Emergency Government (for Zion  :

Station only) I o The Contiguous local authorities as required o The NRC

d. Evaluate parameters, environmental condition and other information to determine what long-term organization is required for the Recovery phase,

e. Schedule personnel, material, and equipment necessary to support the Recovery phase,

f. Provide mechanisms, if required, for periodic plant status and meteorological information to ESDA/DNS and contiguous state authorities.

g. Provide recommendations regarding long-term effect and re-entry into sheltered and/or evacuated areas.

h. Determine level of activation and/or manning of emergency response facilities if pre planned events are to occur that have a potential (possibility) of impacting upon the health and safety of the public, CECO personnel, plant equipment, and/or the environment.

1. Modify the Station Group (OSC and TSC), Recovery Group (EOP) and Corporate Group (CCC) as necessary to support the Recovery phase classification.

j. Notify INPO via the designated emergency call number. l

k. Notify ANI via their emergency notification number.

6-18

April, 1984 Revision 4 TABLE 6.1-7 COPMONWEALTH ACTIONS FOR DOWNGRADING OF EMERGENCY CLASSIFICATION

1. STATION DIRECTOR / CORPORATE COMMAND CENTER DIRECTOR / RECOVERY MANAGER After review of the guidance in section 5.1

a. Evaluate the status of this new classification and the requirements to support this classification, .

b. Downgrade to a lower emergency classification.

c. Notify the following:

o The System Power Dispatcher o The Illinois ESDA and DNS o The Iowa Office of Disaster Services (for Quad Cities Station only) o The Wisconsin Division of Emergency Government (for Zion Station only) o contiguous State Authorities

d. Modify the Station Group, Recovery Group, and Corporate Command Center as necessary to support the new classification.

e. INPO and ANI shall be notified via their respective emergency notification numbers.

2. OVERALL GSEP RESPONSE

a. Proceed as required by the new GSEP classification using guidance of Tables 6.1-2 to 6.1-7, as applicable.

6-19

i April, 1984 6.2 Assessment Actions Throughout each emergency situation, continuing accident assessment will occur. Based upon these assessments, decisions will be made to ,

implement specific emergency measures.

6.2.1 Evaluation of Plant Conditions Evaluation of plant conditions is accomplished through the monitoring of plant parameters both from indication in the Control s

Room and within the plant. Some of the more important plant parameters to be monitored in the Control Room are assembled into a single display location which is entitled the " Safety Parameter Display System" (SPDS)*. The SPDS monitors such parameters as: '

reactor coolant system pressure, reactor / pressurizer water level, containment pressure, suppression pool water level and temperature, reactor power, feedwater flow, safety system status, containment radiation level and effluent monitor readings.  ;

In additionSystem calculation to the SPDS there is the A-model of the Offsite Dose (ODCS) which uses plant parameters and materological conditions to automatically assess conditions and then produce recommendations to control Room personnel regarding Emergency Action Levels (EAL'S)*.

l This system will not be fully operable at all stations as described '

until the stations are equipped with new plant process computers, and ,

the sof tware programs are fully developed. Reference the CECO April 1983 response to NUREG 0737 Supplement #1 or latest submitted schedule for planned operational dates.

6-20 I

. , , - - - - - -----,--,,-,..,~,.,,-m. - - - ~ ~ - , , - - - - , - ,.e-,-- -.--

f t

i April, 1984 '

I Revision 4 '

6.2.2 Radiological Measurements t

Inplant radiological measurements should provide information that may help determine the nature, extent, and source of emergency ~

i conditions. Systems are installed to permit reactor coclant and i containment atmosphere sampling even under severe accident condi- '

tions.

Environmental teams are dispatched by Commonwealth Edison to perform a variety of _ functions during conditions that involve significant l releases of radioactive materials from the plant. In addition to beta /genusa field measurements, the change-out of T!,Ds and air  ;

j sampler cartridges can be performed. Other actions may include l

[

soil, water, and vegetation sampling, as well as plume location j verification. t

, 6.2.3 Dose Proiections for the Offsite Public I l ,

Dose assessment activities shall be conducted with an emphasis on determining the necessity for protective action. ,

Radiological and meteorological instrumentation readings shall be -

used to project dose rates at predetermined distances from the  ;

' station, and to determine the integrated dose equivalent received. t The primary method of estimating offsite doses is through the use of  :

y, .

an'offsite Dose calculation System described in Section 7.3.3. ,

o c

6.2.4 Core Damage Assessment a

To aid GSEP and Controt Room personnel in an assessment of core damage during an emergency condition, each site specific annex  ;

shall contain a plot of activity (C1) versus containment radiation i reading (R/hr) for each reactor unit at the site (if of different '

design). Four points shall be marked on this plot representing:

1) Core release of 25% iodines and 100% noble gases

(

Reference:

Reg. Guide 1.3);

2)- 100% release of gap activity (

Reference:

Reg. Guide 1.25);

3) 0.2% core release of iodines and noble gases (for BWRs) or 2.0% core release of iodines and noble' gases (for .

PWRs) (reference: Reg. Guide 4.2); and

4) 100% release of coolant activity; at t =

0 following an accident, assuming an immediate release of said activities into the containment.

6-21

t

> April, 1984 L Revision 4 6.3 Protective Actions for the Offsite Public 6.3.1 Commonwealth Recommendations for Protective Action t

I For incidents involving actual, potential, or imminent releases of radioactive material to the atmosphere, the current i 1

issue of the " Manual of Protective Action Guides and Protective

Actions the basisfor Nuclear for- Incidents" (EPA recommendations 520/1 "J5-001) for protective actionsshall for the beoffsite used as l I public.  ;

The EPA Guide provides Protective Action Guides (PAGs) for  !

whole body external gamma radiation and for inhalation of

} radioactive material.in an airborne plume.  ;

i are The most effective actions to be recommended to the public evacuation, sheltering, and access control. Evacuation-potentially provides the greatest margin of protection and should be '

4, the primary means of protective emergency action in the event of a gaetous fission product release. On the other hand, because sheltering may be implemented in less time than evacuation, it may be the protective action of choice if rapid evacuation is impeded fer any reason.

! Also, since sheltering is less disruptive than  !

evacuation, it may be the protective action of choice when the dose  !

reduction factor associated with shelter is adequate to reduce the

, projected dose to less than PAG 1evels. Access control is an effective action to avoid exposure of personnel who might otherwise' y enter high exposure areas unnecessarily. '

For incidents involving contamination of food, water, or milk, protective action recommendations will be consistent with the '

guidance of the U.S. Food and Drug Administration published in the Federal Register, " Accidental Radioactive Contamination of Human Food and Animal Feeds; Recommendation for State and Local Agencies" '

, Vol. 4*l, No. 205, October 22, 1982. The FDA guidance includes PAGs l for two levels: a Preventive and an Emergency PAG. The Preventive PAG is a 1.5 rem projected dose equivalent commitment to the thyroid l 3

or a 0.5 ren .whole body dose equivalent commitment. The Emergency i ,

PAG is 10 times the preventive PAG, or a 15 rem thyroid or a 5 rem j whole body dose equivalent commitment.

adopted by FEMA. Thisguidelinehasalsobeenl i 1 Protective action (such as placing dairy cows on uncontami- '

nated stored feed) should be taken whenever a contaminating event is projected to expose an individual at the preventive level' PAG. When the projected dose equivalent reaches the emergency level, food f stuffs should be withheld from commerce until a judgement is made on +

condemnatior, or other appropriate action. I Figure 6.3-1, and Tabies 6.3-1, 6.3-2, and 6.3-3 have been 1 i developed to aid control Room personnel during a rapidly developing {

} '

emergency situation requiring urgent action by offsite officials.  ;

These figures and tables provide a NARS recommendation based upon

(

J the nature of the emergency condition.

l j 6-22  !

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w

July, 1984 I Revision 4a Footnotes to Figure 6.3-1 l

(a) 2x104 R/hr corresponds to approximately 20% GAP release as described in Table B.2 of Appendix to NURBG/GR-2925, In plant considerations for Optimal Offsite Response to Reactor Accidents, November, 1982.

(b) Primary containment pressure was chosen as the parameter that would be indicative of imminent containment failure. Imminent is defined here as a 100% probability that the condition will occur in less than (6) six hours. Six hours was chosen because offsite dose calculations are based on a six hour projection. It is expected that within this time period dose projections based on calculations would be made.

(c) Incomplete Primary Containment Isolation would be another indication of a containment failure.

(d) The top of the active fuel was chosen as the point of concern.

Design studies show that the core can be protected with water level much below the top of the active fuel. However, once water level drops below the top of the active fuel the potential for further core damage is increased. As much time as possible is needed to move the offsite public.

(e) 1 x 105 R/hr corresponds to approximately 100% GAP release as described in the reference listed in Note (a).

(f) This recommendation is made under the most severe conditions. At this point the philosophy is to move the people who are closest to the plant first and to move those who live farther away next until all who live within the area at risk are evacuated.

1 l

6-24

July, 1984 Revision 4a INTENTIONALLY LEFT BLANK

)

6-25

. g .7.w.7 -i.;

r.. * ,c

][-

, t.:.4 Q -

.: 1._ .v

• ' ' -" 5 '

y.s : *:

oggy 1.,mg ,s,g.g li - *

- Protective Actions For actual.oe r e aant casseus seteam. Conditions -

y# -. Recommanded Prot, Actions Mhas Form.

Projected Domes (See)** (S-Shelter. E-twacuation. section P Accident. is 2amal Areas, r. Y ,f. 3.

<'*k *'

Clasellication taisia andr Thyroid P - Prepare foo Possible action. I.O.- info only)

, [:*[ . r Y 2 r T 2 r Y 2

1. Unusual svent (1) Duee Projection uprIL I.O. (1) 9.A is not fIai* wr C.R.L. is ( 200 R/hc (2) not, finlahed ens C.R.L. La )200 R/br Change accident class to alerts (2) -

. b. lou.

(3) 4 0.S Any Any 42.5 Anreere in 10 mile sone  !.0. (3) 9.A (4)$0.5 Any AnP y2.5 Anyuhere cianse accident cleae to (4) -

l elerts (sec. 2 (4))

l (S) $ 1 Any Any y5 Anydere change accident class to (S) -

site emergency (sec. 1 (6))

2. Aler t (1) Not Pintahet end- I.O. (1) 9.A C.a.L. la ( 200 m/hr

. . (2) Not P1mished and (P) F) F) (2) 9.3 C.a.L

• is 200-408 E/he (3) Not Pialahed and Change accident class to (3) -

m . C.E.L. 1s > 40E R/hr . site emergency 3 (sece 2 (2)L h.- '

V,' (4) <1 Amr Aer (5 Anyd ere- (Pr ' F) z P) (4) 9.3 (S) ,PL any Ant >f5 Anreare- Changer accident class to. (S) -

ette emergency; (sec. 2 (s))

3. site smesseen:y (1) Mot Plaished and -

. (P) Pk F) (1) 9.E C.r.L. In 4.400 a/he .

(2) Not Pinished and ($1 F) F) (2) 9.C&D C.R.L. is 400-2000 g/hr (3) Not Pialahed and -

(s1 P) P) (3) 9.Cao C.R.L. is > 2000. E/hr and conta1 ament integrity esists (4) Not Pintahed ame ' ciange accident clama to general (4) -

. . C.P.L. La >2004 R/hs: ame ocultainmenb ' emergencyg go.immediately to lategrity- La toet os locatis imminenc rig. 6.3-1.

. (5) (1 Anp Any ' ' - CSi Any m ore- ' (PF PT- 7) (S) 9.3-(a) )1 4 Any , ps < 3- ' Anyr; ' (s') s') P) (e) s.C.u.&P (7) )1 y1 < 1.6 )$ $ 5. (.S (I*) t*) S) (7) 9.C.M.J.60 h (4)35 Any Any 7 21 . Any Amy. ciange accident class to general emergency (sec. 4 (51)

(s) -

4. om. oral til ao to Pig, s.J-1 Immedt.tely before attempt Lag to -

amergency maae dose Projections tu -

(sters (2) through (6) should be used only in conjunction with Pig. 4.3-1)

=

(2))1 41 Any ') 5 <5 Any (E*) S) P) (2) 9.C.M&P (3)'J1 71 41 35 *p S (5 (E*) t* ) s) (3) 9.C.M.J.&G (4) 7 1 71 3' 1 P, 5 35 j.' S (t') t*) E*) (4) s.C.N.J.&n (5) y 5 y1 <1 y as 7. s < s (s*) (E*) I*) (s) s.C.1&n l

to) a 5 35 y1 t as 22s7s (E*) (t') (s') (s) s.C & new l code needed for 0-10 stles evacuation Peut Notes

The sympo! "i )* represents the entire radius of att sectors of the designated sonal area. were a ataq1e *)*

dersesente the three dounutad sectors only of the designated sonal area. Esamples (s) S) P). The folloutng t -- -

--lation is (s) - shelter 0-2 elle radius. 8) - shelter 2-S mile three dounuLnd sectors. P) - Prepare for possible action 5-10 stle three downwind sectors.

C.S.I.. - Containment radiation level (8/hr)

B - Range (Miles)

, $5 - ELte boundary Any

• Any dose irteepective of quantity Evacuation, when noted. is the recomended protective action only den usether conditions perett and an evacuation time analysis Le re-confirms it as the preferred choLCo. otherwtse shelterlag is the protective action to recommend. If evacuation led for sanal areas T and 3 and if Ionet areas Y and 3 are ln wisconsin or loue, then the r--- - ;ation for evacuation should estend only to the range at which the projected dose is ! Ree wt or S Ree thyrold. untchever is the greater range. Sheltering La the protective action from this range out to 5 miles if the

• range' La in zone Y and out to 10 elles if Lt La La tone 3.

Projected doses are made for actual or imminent release conditione and should be based on a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> def ault Perlod if the release termination tLee is unknown. (use a two (2) haut def ault yetlod for uLnds into lame or Wisconsin.) Projected

, dose rates are also based on the amet (Lkely release point and the esisting site meteorological conditions.

The sones E. Y, and 3 ares E

• site boundary out to 2 elles (not including 2 elle)

Y a 2 miles out to S alles (not including 5 elle) 3

• 5 elles out to 10 ellee (Lncluding 10 sales) 6-24 3i

April, 1984 Rev1Ston 4 TABLE G.3-2 CSEP GUIDELINES FOR PROTECTION AGAINST INGESTION OF CONTAMINATION FOR THE OFFSITE PUBLIC FOOD AND WATER CCNTAMINATION A. Dutived Resunnno tavels Preventive Action Levels *+

Total Intake via All pasture Grass Nuclide** Critical Organ Milk / Water *** Food and Water Pathways (Fresh Weight) 1-131 Thyroid 0.015 uci/l 0.09 uct 0.05 uct/kg Cs-134 Whole Body 0.15 uCL/1 4.0 uci 0.8 uCi/kg Cs-137 Whole Body 0.24 uCi/1 7 uci 1.3 uC1/kg Sr-90 Bone 0.009 uC1/1 0.2 uC1 0.18 uci/kg Sr-89 Bone 0.14 uC1/1 2.6 uci 3.0 uct/kg

• The preventive derived response action levels relate to a 1.5 rem projected dose equivalent commitment to the thyroid or to a 0.5 rem projected dose equivalent commitment to the whole body, bone, or any other organ. Emergency action levels are equal to ten (10) times the preventive levels and relate .to either a 15 rem projected dose equivalent ccannitment to the thyroid or a 5 rem projected dose equivalent commitment to the whole body, bone, or any other organ. **If other nuclides are present, use Regulatory Guide 1.109 to calculate the dose equivalent commitment to the critical organ (s). Infants are considered .

to be the critical segment of the population.

B. Recommended Protective Actions Preventive Level Exceeded Emergency Level Exceeded

. For pasture; remove lactating dairy cows . Isolate food containing from contaminated pasturage and radioactive contamination substitute uncontaminated stored feed, to prevent its introduction Also, substitute a source of uncontaminated into commerce and determine water. whether condemnation or

. For milk; withhold milk from market to another disposition is allow radio 4Clive decay. Consider diversion appropriate. Before taking of fluid milk for production of butter this action, consider:

or evaporated milk. - Availability of other

. For fruits and vegetables; wash, brush, or possible actions; scrub to remove contamination. Allow - Importance of particular radioactive decay through canning, foods in nutrition; and dehydration, or storage. - Time and effort required

. For grains; mill and polish. to take action.

i ***The preventive action levels apply to water as well as milk; the protective action for water would be to use a suitable source of uncontaminated water.

FPA Publicatlon:

• " Accidental Radioactive Contamination of Human Food and Animal Feeds; Recommendation for State and Local Agencies," Federal Register, Volume 47, Number 205, October 22, 1982.

6-27

Apr11. 1944 Revia.1on 4 TA8t.E G 3-3 St491ARY OF POSSIBLE OFFSITE PROTHCTIVE ACTIONS TO BE RB00f9 TENDED OR IfE*1.EMENTED DURING AN EMENGENCY

• ACCIDEiiT PHASE EXPOSURE PATIAfAy Irv_"_TLES OF ACTION TO BE W C_

- 33 1 EMEkGENCY l Inhalation of gases, PHASE l radiolodine, or l Evacuetton, sheIter, access control, respiratory l (0.5 to 30 l particulate l protection, prophylaxis (thyroid protection) l 1

hours *) l i

l Direct whole body exposure l Evacuation, shelter, access control l l Ingestion of milk l Take cows off pasture, prevent cows from drinking l l l l surface water, discard contaminated milk, or divertl

l l to stored products such as cheese l j 2 INTERMEDIATE l Ingestion of fruits and l Wash all produce, or impound produce, delay harvest l

PHASE l_ vegetables i l Ingestion of water l until approved, 5=_M titute uncontaminated produce l I

l Cut off contaminated supplies, substitute from l l 1 other sources, filter, domineralize l

! (30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> to l Whole body exposure and l Relocation, decontamination, access control I 30 days)* I inhalation l l

l l Ingestion of food and water l Decontamination, condemnation, or destruction of l l contaminated from the soll l food; deep plowing, condemnation, or alternate use [

i l either by resuspension or l of land l

) 3 14NG TERM l uptake through roots l PHASE l

! l l 1

i (over 30 days)*l Whole body exposure from l Relocation, access control, decontamination, fixing l l deposition material or l of contamination, deep plowing l

} l inhalation of resuspended l l j i material l l

1 j 1 Emergency phase - Time period of major release and subsequent plume exposure.

i 2 Intermediate phase - Time period of moderate continuous releases with plume exposure and j contamination of environment.

3 Long Term Phase - Recovery Period.

I j ** Typical" Post-accident time periods.

i i

1

Reference:

USEPA " Manual'of Protective Actions Guides and Protective Actions for Nuclear Incidents." 1975.

{ 6-28 i

1 1

i

)

1 i

Aprile 1984 Revision 4 6.3.2 Notification of the Public The capability exists for the prompt notification of the general public within the plume exposure pathway emergency planning zones for Commonwealth Edison Company operating units. This notification capability consists of two principal elements: (1) the Prompt. Notification Systems (PNS) and (2) the Emergency Broadcast System (EBS) radio stations. Information describing these two systems is contained in the public information brochure.

The Prompt Notification System (PNS) consists of fixed sirens and vehicles with public address (PA) systems. The Emergency Broadcast System (EBS) is a network of local radio stations prepared to transmit or relay emergency information and instructions from the civil authorities to the general public. The public information brochures instruct the public to go indoors and turn on their radios when they hear the PNS sirens operating; these brochures also identify which local radio stations the public should tune to for information related to the emergency. The public information brochures are distributed annually to all residents of the plume exposure pathway EP2s and are further discussed in Section 8.4.

Activation of the PNS sirens by the civil authorities will alert the public to turn on their radios to a local Ess radio

( station for detailed information on the emergency situation. At the same time the emergency service vehicles being deployed by local authorities will be broadcasting messages on their P.A. systems also advising the public to tune to the local EsS radio stations or to take specific protective actions. The activation of the PNS sirens.

deployment of emergency service vehicles and operation of the Emergency Broadcast . System is discussed in detail in the Illinois Plan- for Radiological Accidents. A more site-specific description of the various prompt public notification systems is presented in the station-specific annexes to the GSEP.

The PNS is operated by local governmental agencies and maintained by Commonwealth Edison. To assure the PNS is maintained in an operational readiness posture the local agencies have ' agreed to test the system (by sounding the sirens) monthly and to repor.t inoperable equipment to TSN-designated maintenance personnel. The goal of the maintenance program is to render the' inoperable .

equipment functional as soon as possiible but definitely within one month. In addition to this non-routine repair program the PNS will i

be routinely tested and serviced on a semi-annual basis, e

6-29 '

April, 1984 Revision 4 6.3.3 Implementation of Offsite Protective Measures State and local governments have the responsibility to coordinate actions taken to protect the public during emergency situations. Refer to State and local emergency response plans for protective action information for offsite areas. (Also refer to Sections 4.7, 4.8, and 4.9 of this plan).

Time estimates for evacuation of the plume exposure EPZ surrounding each Commonwealth nuclear station appear in each site specific annex.

These evacuation time estimates may be used by the Environmental / Emergency Coordinator as an aid in determining the recommended protective action for the offsite public (i.e., l sheltering or evacuation).

The Illinois Emergency Services and Disaster Agency (ESDA) and Department of Nuclear Safety (DNS) are responsible for evaluation of Commonwealth Edison company recommended protective actions and preparing a State recommendation to the Governor, or his appointed agent. Similar concepts apply in Iowa and Wisconsin.

Only when the State acts under the Governor's order does a recommended protective action become a directed protective action.

GSEP Figure 6.3-1 and Table 6.3-1 suggest a series of protective actions as a function of the conditions of radioactive release. This figure and table agrees with the Illinois Plan for Radiological Accidents and is consistent with Appandix 1 of NUREG-0654. Bad road conditions and other serious offsite conditions might alter the recommendations, as would information from the evacuation time estimates.

6-30 4

_ -- - - - _ _ . , _ , _ . _ - . . _ _ , - _ _ - - . __ ,,,- . , - - _ _ _ -- ...y . -7. - _ _ , .

April 1984 Revision 4 6.3.4 Guidance for Recommending Re-entry into Evacuated Areas If the plant conditions are stable and offsite radiological conditions are such that the public health and safety are not endangered then re-entry to evacuated areas may be recommended.

This recommendation shall be transmitted via the NARS reporting system to State authorities.

The recommendation shall be made by the highest acting authority within the c m wealth Edison GSEP organization.

If the shelter / evacuation recommendation was based upon an actual plant uncontrolled release, then this release must have terminated and the offsite dose equivalents reduced to an acceptable level. This acceptable level should be based upon actual field measurements prior to recommendation of a Re-entry Action .

The following conditions are guidelines for recommendation of the Re-entry Action. Recommendation of this action will be at the discretion of the Recovery Manager / Corporate Command Center Director / Station Director based upon input from the EOF /CCC/TSC staff and/or other appropriate organization knowledgeable of the conditions.

A recommendation of a Re-entry Action is for ' areas that were previously sheltered and/or evacuated. Some of the conditions to be considered prior to making a recommendation are:

6 6-31

April, 1984 Revision 4

1. Has the health and safety of the pub 110 been adequately considered?

l

2. Has the plant parameter, and/or equipment that caused the sheltering and/or evacuations been stabilized and adequately controlled?

3. Have any uncontrolled releases been terminated?

4. Has the environment been monitored? ,

5. Have effluent monitors returned to acceptable levels? ,

6. Have unacceptable environmental areas l been identified, a controlled and monitored? l 5

7. Have contaminated areas requiring shelter / evacuation been returned to acceptable levels?

8. Has Ceco provided necessary plant status to Federal, State '

and local officials such that they can evaluate the '

possibility of a Re-entry Action? s

9. Are there any conditions existing either in the plant and/or environment that would cause a recommendation of shelter i and/or evacuation?

l

10. Are there any conditions that would prevent the t

recommendation of a Re-entry Action?  !

I The highest level of acting GSap organization authority shall I make the recommendation of a Re-entry Action for the environment, to Federal, State and local authorities. It is the responsibility of these authorities to evaluate the Ceco recommendation and consider their own analysis of the emergency condition prior to advising the public o'n an acceptable course of action.

S 6-32

April, 1984 6.4 Revision 4 Protective Actions for Onsite Personnel During an emergency situation the Station Director has the responsibility to provide for protective actions for ALL onsite personnel.

Protective actions to be considered for these personnel may be in the form of " Protective Equipment and Supplies",

" Personnel Assembly", " Personnel Evacuation" or " Contamination Control".

6.4.1 Protective Cover Usa of Protective Equipment and Supplies for personnel During the course of an emergency, protective actions shall be considered to minimize the effects of radiological exposures or contamination problems associated with all onsite personnel. For those who must work within the restricted area of the affected site.

measures that shall be considered are:

1) Distribution of respirators;

2) Use of protective clothing; and

3) Use of thyroid blocking agents.

The criteria for issuance of respiratory protection and protective clothing are described in " Commonwealth Radiation Protection Standards" and/or site specific radiation / chemistry procedures.

The use of thyroid blocking agents may be recommended when a projected dose of 25 rem is exceeded for a worker's thyroid. This is the value recommended by " Potassium Iodide as a Thyroid Blocking Agent in a Radiation Emergency: Final Recommendations on Use" Federal Register, Vol. 47, No. 125, June 29, 1982. The Commonwealth Medical Director is responsible for maintaining a supply of thyroid blocking agents within the company and for establishing the specific policy for its use.

6.4.2. Personnel Assembly During an emergency situation the Station Director may initiate an assembly of all personnel within the security " Protected Area". The purpose of an assembly is to account for all personnel inside the security " Protected Area", and to assemble emergency personnel at prearranged locations.

A site assembly may be initiated whenever:

1) It is determined that dose equivalent or projected dose equivalent can be avoided by relocation of personnel to the site assembly area.

system (All nuclear stations have a given to signal personnel to assemble to previously designated areas.)

6-33 A. '

April, 1984 Revision 4

2) If it is determined by the Station Director that other dangers exist that present a threat to the health and safety of onsite personnel.

3) A Site Emergency or Gereral Emergency is declared, if not previously initiated.

If it is determined that the prearranged assembly area unfit for personnel, the Station Director may designate an alternative site assembly area and assemble personnel using appropriate communication systems that are available, j

i When an assembly of onsite personnel is determined necessary by I the Station Director then accountability of all personnel within the l protected minutes, area shall occur and shall be completed within thirty (30)I j

6.4.3 personnel Evacuation i j

If it is determined that projected doses can be avoided by a relocation of personnel, or other dangers exist that present a threat l to the health and safety of personnel inside the " protected Area" or '

inside the " Site Boundary" an evaeJation may be initiated at any time during the emergency.

6.4.3.1 Personnel inside the Protected Area After assembly / accounting of personnel within the protected Area has been completed, evacuation of non-essential personnel shall , s commence in accordance with Station procedures as directed by the Station Director or his designee, unless one of the following conditions exist:

a) severe weather conditions threaten safe transport; b) a significant radiological hazard would be encountered; c) there is a security threat occurring which would have an adverse il impact on the personnel while leaving the site; ,

d) a condition similar to these in magnitude which in the opinion i of the Station Director, CCC Director, or Recovery Manager wouldI adversely affect the site personnel.

Regardless of who is to be evacuated the offsite evacuation  ;

recommendations shall be considered prior ^ to personnel leaving the protected Area, 6-34 l

April, 1984 Revision 4 6.4.3.2 Personnel inside the " Site Boundary" Each station shall identify locations where people might be !

expected to be present outside the Protected Area but within the owner controlled area called the " Site Boundary". In addition, provisions shall be established for notification and subsequent '

evacuation of personnel within the " Site Boundary". Personnel within the Site Boundary will be judged by the appropriate GSEP Directors as essential or non-essential personnel. Evacuation of non-essential personnel will be performed at the Site or General Emergency levels, as conditions permit.

6.4.4 contamination control During an emergency, the Station Director is responsible for preventing or minimizing direct or subsequent ingestion exposure to radioactive materials deposited on the ground or other surfaces.

Commonwealth Radiation Protection Standards are to be considered by the Station Director as general methods to be used in contamination control.

P 6-35

April, 1984 ,

Revision 4  :

6.5 Aid to Affected onsite Personnel I i

6.5.1 Emeroency Personnel Exposure Being licensed by the Nuclear Regulatory Commission, all i comunonwealth nuclear stations maintain personriel exposure control i programs in accordance with 10 CFR 20. The Commonwealth Edison Radiation Protection Standards include guidance that should be used i a

i for limiting personnel exposures under emergency conditions. When- '

1 over possible, .the prior. approval of the Station Superintendent, the >

Commonwealth Medical Director, and/or the Station's Radiation Protection Supervisor should be secured before exposing individuals  ;

to dose equivalents beyond 10 CFR 20 limits. In addition to the f guidance of the Commonwealth Edison Radiation Protection Standards, emergency personnel exposures shall be limited to the  :

recommendations of the U.S. Environmental Protection Agency as ,

i follows:

l

1) anergency Workers - This applies to conditions where it I is desirable to enter an emergency area to protect i facilities, eliminate serious unplar'aed release of f effluents, or to control fires, a) Planned whole body dose equivalent shall not exceed i

,25 rems;  ;

Planned dose equivalent to the thyroid shall not b) '

exceed 125 rems. L

2) Life Saving Actions - This applies to ' search for and removal of injured persons or entry to the emergency area  !

to prevent conditions that would injure other people.

• a) Dose equivalent to the whole body shall not exceed 75 rems; b) No limit for the thyroid since total ~1oss of thyroid f function could be allowable. I "The eneroency limits outlined in this section shall be  !

voluntary and, if received, be limited to once in a lifetime."

b I

6-36 +

1 i

4

.u-, - < - - , . , _ _ - , - .-w,w- -_..we, - _ - , . , . . ..r

.-- . .= . . - .

i April, 1984 Revision 4

, 6.5.2 Decontamination and First Aid i 6.5.2.1 General i

l'  !

, There are no resident physicians, nurses, or [

industrial hygienists on the staff of Coinmonweal th's  ;

generating stations. However, the radiation protection  ;

personnel at each nuclear station are experienced in control of radioactive contamination and decontamination work. The radiation protection personnel and certain supervisors are also trained and qualified to administer first aid. These individuals are annually retrained in first aid by the station training staff. At least one of these individuals is  !

available on shift at all times.

l The functions of station personnel in handling onsite injured  ;

people are:

1) afford rescue; ,

2) administer first aid including such resuscitative measures as are deemed necessary;

3) begin decontamination procedures; and

4) arrange suitable transportation to a hospital when required.

6.5.2.2 Initial First Aid Primary attention shall be directed to the actual factors involved in the treatment of casualties, such as:

control of bleeding, resuscitation including heart and lung, .

protection of wounds from bacterial or radioactive contami- ,

nation and the immobilization of fractures.

6.5.2.3 Decontamination r

Nuclear Station radiation protection personnel shall provide an initial estimate of the magnitude of surface  !

contamination of the injured and preliminary estimates of total body dose to the injured. Directed by radiation protection personnel, the station should carry out primary rapid . and simple decontamination of the surface of the body when possible and advisable before transportation of - the injured to a designated hospital. '

. 6-37

. a

- ~ . - ~ , - , , - - - ~ . , . -- , - - - , - - . - - -- , ,,,,.,w -

nn., , . . ,,,,,n._ . , - +-r , e- - w,

April, 1984 Revision 4 6.5.3 Medical Transportation F

Arrangements are made by each nuclear generating station for prompt ambulance service for transporting persons with injuries involving radioactivity from the respective generating station to designated hospitals. Such service is available on a 24-hour per day basis and is confirmed in writing. Radiation monitoring '

services shall be provided by Commonwealth whenever it becomes necessary to use the ambulance service for the transportation of contaminated persons.-

Injured persons shall be transported to a hospital or other medical facility in a prudent and timely manner. Those persons contaminated with radioactive material shall be taken to the desig-nated hospital and be accompanied by a person qualified in radi-ation monitoring techniques.

6.5.4. Medical Treatment 6.5.4.1 Hospital Facilities Arrangements . confirmed in writing every two (2) ,

calendar yeara, are maintained by Commonwealth with a qualified hospital located in the vicinity of each nuclear generating station for receiving and treating of contaminated ,

or exposed persons. Such nearby hospital facilities shall be ,

utilized for decontamination and initial treatment of persons '

with injuries involving radioactivity and requiring immediate hospital care. Commonwealth shall provide medical consultants to aid in any special care necessary at these facilities.

Arrangements, confirmed in writing every two (2) l calendar years, are also maintained by the corporate office with a qualified major medical facility well equipped and staffed for dealing with persons having radiation injuries

• and whenever necessary, such persons will be transferred to this major hospital facility- for extended specialized treatment. Currently,- Northwestern Memorial Hospital in Chicago, Illinois se'rves as this hospital. Commonwealth will l

have available to the staff of this hospital its specialist who will provide the direction of the special care necessary for the treatment of persons having radiation injuries.

6.5.4.2 Radioloqical Medical Consultants Because of the specialized nature of the diagnosis and treatment of radiation injuries, commonwealth's corporate medical office maintains a roster of physicians especially I competent in this area of medicine and available for the r

6-38 i

April, 1984 Revision 4 care of persons with these special problems. Included in this roster are experts in the treatment of internal contamination, cutaneous radiation injury, total body irradiation and other potential problems related to exposure by ionizing radiation or radioactive. materials.

These specialists may be in direct charge of the care of these patients or serve as consultants to other physicians in charge of their care.

i sf r

I t

I l

i 6-39

t W

April, 1984 Revision 4 7.0 EMERGENCY FACILITIES AND EQUIPMENT 7.1 Emergency Control Centers 7.1.1 Station Control Room The nuclear station Control Room shall be the initial onsite center of emergency control. Control Room personnel must evaluate and effect control over the initial aspects of an emergency and initiate activities necessary for coping with the initial phases of an emergency until such time that support centers can be activated.

These activities shall include:

o Continuous evaluation of the magnitude and potential consequences of an incident; o Initial corrective actions; and o Notification of appropriate indivicuals as outlined in Section 6.0 of this plan.

Support centers provided are the Technical Support Center, Operational Support Center, Corporate Command Center, and Emergency Operations Facility.

7.1.2 Technical Support Center (TSC) l Each nuclear generating station has established a Technical Support Center (TSC) for use during emergency situations by plant management, technical, and engineering support personnel. When activated during an emergency, the TSC shall be manned by sufficient i personnel to:

o Support the Control Room command and control function; o Assess the plant status and potential offsite impact; and o Coordinate emergency response actions.

Staffing of the TSC shall be directeo by the Station Director. Reporting initially to the TSC for the Site and General Emergencies shall be all cirectors of the Station Group, i.e., the Station Director, Operations Director, Technical Director, Maintenance Director, Stores Director, Administrative Director, ,

Security Director, and Rao/ Chem Director. (The Shift Engineer when acting as initial Station Director shall not report to the TSC).

Other personnel may augment the TSC staff upon approval of the Station Director.

Each TSC provides reliable voice communications to the Control Room, the OSC, the EOF, the CCC, the NRC, and State and local operations centers. In addition, they provide facsimile transmissions capability to the ECF and the NRC Operations Center.

7-1

. 1 _ _ . __

~ --.

L April, 1984 ,

Revision 4  ;

Each TSC is in proximity to the Control Room and is sized for a l '

minimum of 25 persons and supporting equipment. Of the 25 persons, five shall be reserved for the NRC and one person shall be available for the l '

State of Illinois. At Quad Cities and Zion Stations, an additional slot  ;

per station will be held for a contiguous state representative. ,

Personnel in the TSC shall be' protected from radiological hazaros,  !

including direct radiation and airborne contaminants under accident r conoitions with similiar radiological habitability as Control Room personnel. To ensure adequate radiological protection, permanent radiation monitoring' systems have been installed in the TSC. These systems continuously indicate radiation dose rates and airborne radioactivity "

inside the TSC while in use. In addition, protective breathing apparatus l (full face air purifying respirators) and thyroid blocking agents are i available for use as requireo. l The TSC has access to a complete set of as-built drawings and other  ;

records, including general arrangement diagrams, P& ids, and the electrical l schematics. The TSC~ has the capability to record and display vital plant '

data, in real time *, to be used by knowledgeable individuals responsible e for engineering. and management support of reactor operations, and for implementation of emergency procedures..

7.1.3 Operational Support Center (OSC) I r . Each nuclear generating station har established an Operational '

Support Center (OSC). The OSC is the location to which operations support personnel should report during an emergency and from which they will be dispatched for' assignments or duties in support of emergency operations.

Personnel who may report to the 0SC include:  ;

o OSC Director- .

I .

o Operating personnel not assigned to the Control Room; ,

o Radweste personnel o Rad / Chem Technicians o Maintenance personnel The Operations Director shall designate an individual to become the OSC Director, if not already appointed by the Shift Engineer. This person will manage and supervise the activities of the OSC. . The OSC shall be activated whenever the TSC 'is activated , but need not remain activated at the Alert level if its use is judged unnecessary by the Station Director.

At' the Site and General Emergency levels the OSC or an alternate OSC shall be activated at all times.

A limited inventory of supplies will be kept in the OSC. This l Inventory will include respirators, protective clothing, portable lighting, and portable survey instruments.

Each OSC is equipped with a cedicated direct voice communication line to the Control Room and normal station telephone access to the TSC and the EOF so that personnel reporting to the OSC can be assigned to duties in support of emergency operations.

• This system will not be fully operable at all stations as described until the stations are equipped with new plant process computers, and the software programs are fully developed. Reference the CECO April 1983 I response to NUREG 0737 Supplement 1 or latest submitted schedule for planned operational dates.

7-2

i April, 1984 j Revision 4 7.1.4 Corporate Command Center (CCC)  !

The Corporate Command Center located in the Edison Building, Chicago, Illinois is the location from which the Corporate Command l  !

Center Director, will normally direct a staff in evaluating,- '

coordinating, and directing the overall company activities involved ,

in coping with an emergency. If the Recovery Group is activated at the EOF, then the CCC shall be the location for a support staff reporting to the EOF Recovery Group.

In addition to the above functions, the CCC Environmental I Director shall support TSC/ EOF envirormental activities.

7.1.5 Emeraency Operations Facility (EOF) r The FJergency Operations Facility (EOF) is the location near -

the. generating station that provides for the management. of overall emergency response, the coordination of radiological and i environmental assessments, the determination of recommended :public i protection actions, -the management of recovery operations, and the coordination of emergency response activities with Federal, State, and local agencies. The EOF and associated Recovery Group function under a Recovery Manager and are activated for all Site and General p.- Emergency situations. Activation -- for other emergency conditions is optional.

• There shall be three major groups of emergency control.

personnel functioning at each EOF. They are (1) Recovery personnel; (2) Environmental Control personnel; and (3) Emergency News personnel' Refer to Figure 7.1-1.

{

' Recovery personnel function under the direction of the- [ 'I Recovery Manager and serve as the command post for direction of all-recovery operations.

Environmental Control personnel are under the direction of the EnvironmentalNmergency Coordinator and function to evaluate.

emtsrgency situations that affect the public. ,

r

-Emergency- News personnel operate from- the Emergency News Center, which is unoer the direction of the Emergency News Center- -

Director' and functions' as the single-point contact to interface with i Federal, State, and local authorities ~ who are responsible for i

~ disseminating information to the public. A technical spokesperson-will be chosen by the Recovery Manager. This spokesperson will be

. knowledgeable about the affected station and its operation and :will-  ;

have the aut.hority and responsibility to discuss technical problems '

associateo with the emergency. The spokesperson shall be available to brief the press at the Joint Public Information Center.

1 7-3 ,

i

' April, 1984 ,

Revision 4 The four primary EOFs (Mazon EOF to serve Dresden, Braidwood and LaSalle County Stations, Dixon EOF for Syron Station, Morrison ,

EOF for Quad Cities Station, and Zion EOF for Zion Station) are  ;

constructed according to the design criteria such that ,

1) The location provides optimum functional and availability characteristics for carrying out overall stategu, ,

direction of ECo onsite and support operations,  ;

cetermination of public . protective actions to be  ;

recommended to offsite officials, and coordination with Federal, State and local organizations.

2) They are well engineered for the design life of the plant and are of sufficient size to accommodate about 50 people. The Zion Station EOF, because of its close 4 proximity to the station, is provided with additional radiological protection features. '

3) They are equipped with reliable voice communications facilities to the TSC, the OSC, the CCC, the Control '

Room, FEC, and State and local emergency operations centers. In addition, each EOF has facsimile '

transmission capability to any other EOF, to all TSC's, and the NRC Operations Center. ,

4). Equipment is provided to gather, store, and display data '

needed in the EOF to analyze and exchange information on plant conditions with the designated senior &Co manager in charge of the TSC.

• 5) The EOF- technical data system receives, stores, ,

processes, and displays information sufficient to perform assessments of the actual and potential onsite and j offsite environmental consequences of an emergency ;

condition, l

6) They have ready access to plant records, procedures, and l emergency plans needeo to exercise overall management of :

TCo emergency response resources. .

t The Zion BEOF is constructed according to the design criteria , -

in a portion of' the . Lake County Emergency Operations Center at a i distance of 15 miles from the Zion plant. The facility is eculpped with reliable communication and appropriate dose projection computer :

equipment,- which provide for continuity of decision making ,

capability. l

• This. system will not be fully operable at all stations as described until the stations are equipped with new process computers,' and the software programs are fully developed. Reference the GCo April 1983 response to NUREG 0737 Supplement #1 or latest submitted

-schedule for planned operational dates.

7-4

~

FIGURE 7. I-I $$[)io[T COMMONWEALTH EMERGENCY CONTROL CENTERS

, 8 COMMUNICATIONS FLOW  :

l (For a full response situation)

Plant Control , . Technical Support Room Center .

a 6 I Operational 1

Support Center  :

- - - - - - - _ - - - _ _ - - - - _ Onsite  ;

Nearsite  !

[ 1 '  !

Recovery ,

Environmental Personnel

Control

, , Personnel a 6 Emergency Operations Facility (E0F)

Emergency News Personnel I

r News Media l Public  !

Nearsite Remote from l Site

. Corporate Command .

L Center  :

Note: The EOF has three defined functional centers. Space limitations of individual EOFs may not allow separate physical rooms for each

" center" .

7-5

April, 1984 Revision 4 7.2 Communication Systems Commonwealth has extensive and reliable communication systems installed at its generatic.g stations, system power supply office, corporate headquarters, and Division load dispatching offices. These systems include the use of normal and dedicated telephone lines on land lines and microwave voice channels, mobile radio units, handi-talkies, and computer peripherals.

For the purposes of GSEP commmunications, the system is addressed in terms of functional areas as described in the following sections.

7.2.1 Nuclear Accident Reporting System (NARS)

The Nuclear Accicent Reporting System is a dedicated telephone voice communications system that has been installed for the purpose of notifying State and local authorities of declared nuclear emergencies. This system links together the station Control Rooms, the Corporate Command Center, Technical Support Centers, System Power Supply Office, Emergency Operations Facilities, and State and local authorities as appropriate. (See Figure 7.2-1). ,

Except for special circumstances involving the Recovery Manager and directors of certain state agencies (ESDA, DNS, ODS, DEG) all NARS messages (Figure 7.2-2) shall be reported in the format of the current NARS form. The format and content of the NARS form must be mutually agreed to by the Directors of ESDA and DNS and the Technical Services Nuclear Manager before its use. The NARS form is a State of Illinois form included in the GSEP to aid the reader in understanding the reporting concept. This form is not subject to onsite/offsite review.

The State of Illinois Emergency Services & Disaster Agency, in cooperation with Commonwealth Edison, is responsible for the development and execution of al'. steps necessary to ensure continuous operation of the NARS.

7.2.2 Correnunications for Command and Control Commonwealth has established four separate dedicated communication systems that ensure reliable and timely exchange of information necessary to provice effective ccomand and control over any emergency response. These systems include:

o A microwave voice channel between the Corporate Ccmmand Center and the Shift Engineer's Office, the TSC, and the EOF at each nuclear station. (Gray phone) o A telephone link that enables communication between the Corporate Command Center, the TSC, and the EOF. (Yellow phone) 7-6

[

April, 1984 Revision 4 o A telephone link that enables communication between the g

Control Room and the TSC. (Non-color coded) o A telephone link that enables communication between the Control Room and the OSC. (Non-color coded)

Refer to Figure 7.2-3 for a more descriptive representation of the above systems.

7.2.3 Environmental Assessment Communications Two separate communication systems have been installed to allow coordinated environmental monitoring and assessment during an emergency.

The first system consists of the necessary hardware to allow communication between the Corporate Command Center, the Control Room, the TSC, the EOF mobile units in Commonwealth vehicles, and I handi-talkies held by environmental monitoring teams in the field.

The radio system has scramble and non-scramble capability to prevent monitoring by non-company equipment.

The second system consists of a dedicateo telephone which allow continuous communication between the Corporate Command Center and the Illinois Department of Nuclear Safety REAC in Springfield.

Refer to Figure 7.2-4.

7.2.4 tRC Communications There exists a dedicated telephone, Emergency Notification System (ENS), between each nuclear station's Control Room and the NRC, with an extension of that line in the Technical Support Center and Emergency Operation Facility. There also exists a separate dedicated telephone, Health Physics Network (hPN), between the NRC and the Radiation Protection Office at each nuclear station (See Figure 7.2-5) . The actual configuraticn of these systems may vary l from station to station. Installation ana use of the NRC phones is unoer the direction of the NRC.

7.2.5 NAWAS The Wisconsin National Warning System (NAWAS) network is available at the locations shown on Figure 7.2-1. The NAWAS is used to provice the init!al notification of a reportable incident at the Zion Station to the State of Wisconsin and to Wisconsin Warning Center I located at the Wisconsin State Police Patrol District Headquarters in Maoison, which is responsible for off-hours contact of the Wisconsin Duty Officer. N4WAS is used for initial Contact only. Details of the initial report ana subsequent changes in ,

status shall oe proviced to Wisconsin officials by other communications.

7-7

e July ,1964 R;vis1Dn 4 A MUCLEAR ACCIDENT REPORT SYSTEP' (WARS)

Selection of a predetermined code rings selected phones. The NARS phones are color coded GREEN.

DIAL CODE NAPE LOCATION DIAL CODE E

NAME LOCATION

' Dept. Nuclear safety Springfield 25 LAsat.t.E

• Illinois ESDA Springfield *LaSalle Control Room Seneca I*SystempowerSupply Lombard ' Tech Support Center seneca

• LaSalle E.O.F. Seneca 22 DRESDEN LaSalle County Sheriff Ottawa

• Dresden Control Room Morris LaSalle Co. ESDA Ottawa

• Tech.5upport Center Morris Grundy County Sheriff Morris

• Dr esden E.O.F. Morris Grundy County ESDA Morris Grundy County Sheriff Morris

• Dept. Nuclear Safety Springfield Grundy County E.S.D.A. Morris

• System power Supply tombard Will County E.S.D.A. Joliet

• Corporate Command Ctr Chicago

• Dept. Nuclear Safety Springfield

• Illinois ESDA Springfield

' System power Supply Lombard

• Corporate Command Ctr. Chicago H l

• Illinois ESDA Springfield

• Dept. Nuclear safety Springfield Kendall Co. Sheriff Yorkville

• Iowa Disaster Serv. Des Moines

• Illinois ESDA Springfield 23 CUAD CITIES

• System power Supply tenbard l

• gued Cities Control Rs. Cordova

• Tech Support Center Cordova H '

• Quad Cities E.O.F. Cordova Whiteside Co. Sheriff Morrison Rock Island r = m ica Rock Island Whiteside Co. ESDA Morrison Rock Island Co. ESDA Rock Island Rock Island Cons. RockIsland

• Iowa Disenter Services Des Moines. IA Rock Island Co. ESDA Rock!sland

' Scott County Sheriff Davenport. IA

• Illinois ESDA Springfield

• Clinton County E.O.C. Clinton. IA Whiteside Co. Sheriff Morrison M Whiteside Co. E.S.D.A. Morrisen

• Dept. Nuclear Safety Springfield

• Dept. Nuclear Safety Springfield

• Wisconsin D.E.G. Madison.VI

• System power Supply 14mbard

• Illinois ESDA Sprinfield

' Corporate Command Ctt. Chicago

• System power Supply tombard l

• Illinois ESDA Sprinfield H  ;

24 ZION Dewitt Co. Sheriff Clinton.IL *

+*21on Control Room Zion Dewitt Co. ESDA Clinton.IL

• Tech Support Center Zion *SESDA IL. ESDA Springfield

• I1on EOF Elon Zion police Dept. Ilon E P - nity Coord. Ctr. Libertyville ' Byron Control Room Byron Lake County Sheriff Waukegan

• Tech Support Center Byron

+Kenosha Co. Wrn. Center Kenosha. WI 'Dixon EOF Dixon

+* Wisconsin D.E.G. Madison. VI

• Illinois ESDA Springfield

+Waukesha Center Waukesha. WI *Ill. DNS Springfield

• Dept. Nuclear Safety Sprinfield +* System power Supply tombard

+* System power Supply tombard ' Corporate Command Ctr Chicago

• Corporate Command Center Chicago Ogle County Sheriff /ESDA Oregon

• Illinois ESDA Springfield l j Winthrop Harbor police Winthrop Harbor I

• -DIAL CAPA8ILITY '

+-WAWAS I

! 7-8 I

I l

1 i

~

s . 1 MESSAGE RECEIVED STATE OF IL.LINOIS TIME DATE NUCLEAR ACCIDENT REPORTING SYSTEM FORM

1. STATUS 2. SITE-IPR A VOL. . 3. ACCIDENT CL ASSIFIC ATION EAL. 4. RELEASE STATUS 5. TYPE OF RELE ASE lAl ACTUAL lAl DRESDENil (El BYRON VI lAl TRANSPORTATION ACCIDENT lAl NONE lAl RAD 10 ACTIVE GAS 181 EXERCISE / 18l LASALLE lli (Fl CLINTON Vil (Bl UNUSUAL EVENT 181 POTENTIAL 1Bl RAD 10 ACTIVE ll0Ul0

' DRILL / 1C1 QUAD CITIESIV lGI BRAIDWOOD-Vill ICI ALERT ICI OCCURRING (Cl NO RELEASE TEST [Dl ZION V (D) SITE AREA EMERGENCY 10l TERMINATED 10) UNKNOWN lEl GENERAL EMERGENCY

8. INCIDENT OCCURRED 7. ACCIDENT CL AS$1FIED [Fl RECOVERY IGl TERMINATE CONDITION lH1 OTHER TIME DATE TIME DATE , y

U D E *!!

8. WlND DIRECTION DATA (Check ene. Reed acroul 9. RECOMMENDED PROTECTIVE ACTIONS: M 70 m

SECTORS O >--

WIND FROM DEGREES WIND TOWARD AFFECTED

• lAl NOT APPLICABLE (INITIAL NOTIFICATION FOR INFORMATION ONLY)

[Al N 349 11 S H J K 181 PREPARE FOR POSSIBLE ACTION INVOLVING THE PUBLIC.TO INCLUDE NOTIFICATION -

lBI NNE 12 33 SSW J K L (Cl NOTIFY PUBLIC TO TAKE THE FOLLOWING PROTECTIVE ACTIONS:

ICl NE 34 56 SW K L M IN IL LINOIS SHELTER EVACUATE IN WISCONSIN /10WA

-J l EE 5 8 WSW M 0 2 BilLE RADIUS 10l [Hl 0 2 MILE RADIUS

"'" " ' ' " "^

ll SE 14 NW 0R lHI SSE 147 168 NNW Q R A 2 5 MILES FOR THREE (3) (Fl lJl 2- (R) MILES fil S 169-191 N A A B DOWNWIND SECTORS IJl SSW 192-213 NNE A B C lKl SW 214-236 NE B C D lL] WSW 237 258 ENE C D E 510 MILES FOR THREEl(3) (Gl [Kl (R) TO 10 MILES 1 DOWNWIND SECTORE (R IS THE RANGE EQUAL IMl W 259 281 E D E F TO THE PAG DOSE.)

lNI WNW 282-303 ESE E F G 10l NW 304-326 SE F G H l lP) NNW 327 348 SSE G H J (Ll DISCONTINUE USE OF POTENTIALLY AFFECTED WATER IN

LOCATIONISI j [M] PUT MILK PRODUCING ANIMALS ON STORED FEED IN DOWNWINDSECTORS OUT TO MILES.

i 1 10. MESSAGE REPORTED BY: 12 MESSAGE RECEIVED BY:

NAME OF CALLEH YOUHNAME OHGANIZATSON TELEPt40NE NO.

13. MESSAGE VERIFIED BY;

- NAME TIME OHGANIZATION

11. NARS DIAL CODE USED BY SENDER j 14. UTILITY DUTY OFFICER NAME TELEPHONE C E. Co. 86 2626 ($16 83

. April, 1984 Revision 4 FIGURE 7.2-3 COMMUNICATIONS FOR COMMAND AND CONTROL OSC h h CONTROL ROOM 1

1

=== %

e ** p ***

s

%' ~% A I I SHIFT TSC  !

ENGINEER'S OFFICE *

@ @ U p

l I

A ,

EOF

@ h CORPORATE coaa^ao CENTER hiephone line between the OSC and Control Room.

' Color coding of this system is at the discretion of each nuclear station. '

, Telephone line between the Control Room and TSC.

Color coding of this system is at the discretion of each nuclear station.

Microwave voice channel between the Corporate Command Center and the EOF, Shif t Engineer's Office, and the TSC. Phone receivers are color-coded gray.

Telephone line between the EOF, Corporate Command Center, and TSC. Phone receivers are color-coded yellow.

Regular 3tation telephone line.

dedicated

---

regular P Phone receiver At the discretion of each nuclear station, the gray phone for the Shif t Engineer's Office may be placed in the Control Room.

7 - 10

April, 1984 Revision 4 i FIGURE 7.2-4 ENVIRONMENTAL ASSESSMENT COMMUNICATIONS i CONTROL RC RC TSC ROOM

• I EOF RC CORPORATE RC COMMAND CENTER r 09 GSEP b  ;

ENVIRONS HT l TEAMS ILLIN0tS DEPARTMENT OF NUCLEAR N081LE UNITS g SAFETY REAC '

i Microwave radio link between tne Corporate Command Center, TSC, Control Room, EOF, GSEP environs teams, and mobile units. '

b Teleonone line between the Corporate Comand Center and the Illinois Department of Maclear Safety. Phone receiver is color-cooed black.

N Raolo/ console unit HT Hanoi-talkie (153.590 MHz)

O Radio (133.590 mz) b Fhone receiver  ;

O At the discretion of each nuclear station, the radio console for tne Control Room may oe placed in the Shift Engineer's Office. .

7 - 31

ap.... . 64 Revision 4 I

FIGURE 7. 2-5 NRC COMMUNICATIONS 4

& NRC &

HPN ENS STATION <

RADI ATION c CONTROL '

PROTECTION O ROOM -

0FFICE 4 EOF $

4 l, 4 TSC $

ENS: EMERGENCY NOTIFICATION SYSTEM; PHONE RECENERS ARE COLOR-CODED RED HPN: HEALTH PHYSICS NETWORK; PHONE RECEIVER COLORS VARY FROM STATION TO STATION.

@ PHONE RECEIVER THE EXACT CONFIGURATION OF THE ABOVE SYSTEMS MAY VARY FROM ONE NUCLEAR STATION TO ANOTHER. INSTALLATION AND USE OF THE NRC PHONES ARE UNDER THE DIRECTION OF THE NRC .

I t

7 - 12 l

l

April, 1984 Revision 4 7.3 Assessment Facilities 7.3.1 Onsite Systems, Instrumentation, and Eculoment Each nuclear station is equipped with instrumentation for seismic monitoring, radiation monitorii6, fire protection, and e meteorological monitoring. The actual instrumentation varies somewhat from site to site and thus will not be described in this generic plan. Descriptions of the above equipment will appear in each site specific annex. Instrumentation useful to the detection or analysis of emergency conditions shall be maintained in accordance with station Technical Specifications, if applicable, or commitments made to the NRC.

With regard to Commonwealth Edison's meteorological monitoring program, there has been a quality assurance program since 1976. The program was adopted from 10 CFR 50, Appendix 8. However,

, since the meteorological facilities are not composed of structures, systems, and components that prevent or mitigate the consecuences of postulated accidents and are thus not " safety relateo", not all aspects of 10 CFR 50, Appendix B apply. Those aspects of ouality assurance germane to supplying good meteorological information for a nuclear pc*er station were adopted into the meteorological cuality assurance program.

7.3.2 Safety Parameter Display System (SPOS)*

The Safety Parameter Display System (SPDS) shall provide a l display of plant parameters from which the safety status of ~

operation may be assessed in the Control Room, TSC, and EOF for each l nuclear station. The primary function of the SPDS is to help operating personnel in the Control Room make culck assessments of plant safety status. Duplication of the SPOS displays in the TSC, and EOF will promote the exchange of information between these l facilities and the Control Ronm and assist management in the decision making process.

7.3.3 Offsite Dose Calculation System (00CS)*

The Offsite Case Calculation System (00CS) is a computer based method for estimating the environmental impact of unplanned airborne releases of raoicactive material from nuclear stations.

The objectives of the Commonwealth 00CS are:

)

o Provide, where possible, redundant independent pathways of data transmission and redundant data processing computers for use in an emergency situation.

This system will not be fully operable at all stations as described until the stations are eculpped with new plant process computers, and the software prograns are fully developed. Reference the CECO response to NUREG 0737 Supplement #1 or latest submitted schedule for planned operational dates.

7-13 v

?

April, .1984  !

Revision 4  !

o Provide quick and reasonably accurate estimates of radiation dose equivalent to persons living offsite, including preparation of procedures and training of users required to accomplish this assessment.

o Provide a method for the meteorological contractor to secure meteorological data for assessment of routine.

releases and to detect equipment failure ouickly. y Each nuclear station's meteorological tower is frecuently -

interrogated- each day by the meteorological contractor to secure information necessary for.. preparation of meteorological operating 4

reports and for detection of system failures. i Hourly, and more frequently during an accident, a corporate - i computer shall. poll each meteorological facility to prepare the l 4 corporate data file and .to check the system in order to maintain the  ;

00CS in a readiness condition. The corporate computers shall then store the data for an extended time period.  ;

At each nuclear station the plant computer. will produce Linitial transport and diffusion estimates within 15 minutes i i following classification of an incident. The ' plant computer will

• C .

produce . refined estimates of dose equivalent as a- terminal entry system to the corporate computer.

l During an -accident the plant computer system and a larger,

corporate computer system will provide the various users with timely information - required to make decisions. . Emergency actions will be performed in the following sequence

, First -

time' frame: - initial one-half hour or so post-accident - ,

the control room operator will rely on wind speed and '

direction and ' effluent release rate information' provided '

by the plant process computer and these data converted .

, into requisite Emergency Action Levels (EALs) by the Class  !

A c.omputer model.

i j- ' [

V ,

f 4

, i i

s e

7-14  ;

I

. . , - . _ . _ . - , _ . . _ _ . . ._- .,,-___,.,._,.m. ,._.m , , , _ . , , . . . . , . . , _ . . . , . _ . - , . _ . , . _ - - _ - - . . _ _ . . - , ,

April, 1984 Revision 4

• The Class A model will provide warning to the Control Room operator when the following EALS have been exceeded: for Site Emergency: 2-minute average noble gas release rate having projected offsite. dose rate of 500 trR/hr and 30-minute average noble. gas release rate having projected offsite . dose - rate of 50 mR/hr, using worst . case meteorology; and for. General Emergency: 2-minute E average noble gas release rate having projected offsite dose rate -

of 1000 mR/hr using'15-minute average actual meteorology, second - 1/2 hour to few hours - emergency. personnel should likely analyze the. off-site consequences using the track model and C-model, both of which reside in the corporate computer and plant computer system.

!- third -

few hours to duration of accident - the EOF environmental staff backed by a corporate environmental group will l perform refined t.stimates of. the offsite consecuences for the duration of the emergency period. r o mputer trocels available for. use include the A, B, C, and track models.

This corporate group has.. been formed to support all nuclear stations and will perform its work in Chicago in

'lleu of having to relocate to each Emergency Operations l 4' Facility (EOF). .A data link between the corporate facility and each EOF will be provided. I This system will not be fully operable at all stations as described until the stations are equipped with new plant process computers,

. - and the software programs are fully developed. Reference the CECO response to NUREG 0737 Supplement #1 or latest submitteo schedule for planned operational dates.

l

< i.

4

[

a f

7-15

o April, 1984 Revision 4 7.4 Protective Facilities and Eouicment Each nuclear station has chosen locations to serve as both onsite assembly areas and offsite evacuation assembly areas. The specific locations of these areas are shown in each site specific annex.

7.5 First Aid and Medical Facilities Each nuclear station maintains onsite first aid supplies and equip-ment necessary for the treatment of contaminated or injured persons. As described in Section 6.5.2 of this plan, no resident physicians, nurses, or industrial hygienists are on the staff of Commonwealth's generating stations, and as such, medical treatment given to injured persons is of a "first aid" nature. When more professional care is needed, injured per-sons are transported to a local clinic or hospital. Hospital facilities are discusseo in Section 6.5.4 of this plan, c

I 7-16

April, 1984 Revision 4 7.6 Damage Control Eculoment and Supplies The onsite storeroom of each nuclear station maintains a supply of parts and equipment for normal plant maintenance. These parts, supplies, and equipment are available for damage control use as necessary. When an emergency condition exists at or.e station, additional supplies can be obtaineo from other stations and from Division resources upon request.

4 7.7 Facilities and Equipment for Offsite Monitoring Comonwealth Edison has contracted with a company (currently Teledyne Isotopes) to conduct an extensive offsite environmental I monitoring prcgram to provide data on measurable levels of radiation and radioactive materials in the environs. The program includes: fixed continuous air samplers; routine sampling of river water; routine sampling of milk; routine sampling of fish; and a fixed TLD monitoring network. The TLD program consists of the following elements at each nuclear station:

o A nearsite ring of dosimeters covering the 16 meteorological sectors.

v o A 16 sector ring of dosimeters placed in a zone about 5 miles from the plant.

o TLDs placed at each of the normal fixed air sampler locations (typically about 8-15 air samplers per nuclear station).

Each nuclear station maintains a supply of emergency equipment and supplies which may be used for offsite monitoring. The actual equipment may vary somewhat form site to site and thus the specific listing of equipment appears in Station Emergency Plan Implementing Procecures.

Table 7.7-1 lists the types of equipment and supplies. Sufficient supplies of emergency equipment shall be maintained in order to meet the initial requirements of two environmental sampling teams that woulo be dispatched for declared emergencies that involve releases of radioactive material to the environment. During subsequent phases of an emergency, equipment would be available from other Commonwealth Edison nuclear stat,lons, vendors, and offsite response organizations.

S 7-17

April, 1984 Revision 4 TABLE 7.7-1 0FFSITE EMERGENCY MONITORING EQUIPMENT FOR EACH NUCLEAR STATION EQUIPMENT A. Instrument Kit

• l

1. High range cutie-pie ion chamber (at least up to 50 R/hr)

2. GM survey meter (Beta-gamma) capable of measuring less than 0.2 mR/hr

3. Sample counting equipment capable of measuring radio-iodine concentrations in air in the plume exposure EPZ as low as 1E-07 uC1/cc under field conditions l

4. Dosimetry:

o Film or TLD Badges 0 0-200 mR self-reading dosimeters o High range self-reading dosimeters greater than or equal to 50 R g o Dosimeter charger

5. Instrument check sources

6. Air Sampling Equipment:

o Portable air sampler operated either with battery or portable generator o Filters for air sampler o Silver Zeolite Cartridges o Tripod (or equivalent) for air sampler

8. Protective Clothing

• l l 1. Coveralls (various sizes)

2. Gloves

3. Head Coverings

4. Shoe Covers

5. Plastic Suits

6. Boots

7. Full face respirators with combination filter / charcoal

. cartridges .

Actual quantities of listed items are established by each nuclear station. .

7-18

O April, 1984 Revision 4 TABLE 7.7-1 (CONT)

EQUIPMENT C. Communications Eculpment* ^

l

1. Handi-talkies on frequency of'153.590 MHZ with scramble capability. Note: These radios are probably not to be stored with the rest of the equipment listed in this table. ,

D. Sample Collection Kit

• l

1. Plastic Bags (various sizes)

2. Plastic Bottles (various sizes)

3. Masking Tape and Labels

4. Marking Pencil or Pen E. Miscellaneous Supplies *

1. Spare Batteries 1

2. Radiation Signs, Radiation Rope or Ribbon

3. High Intensity Flashlights or Lanterns f 4. Smears Pads 3 5. Shovel

6. Flares

7. Pocketknife

8. Ladoer

9. Set of keys to Environs Stations

10. Screwdriver (Plain and Phillips)

11. Scissors

12. Teri Towels (or equivalent)

13. Stopwatch '

F. Data Reference Kit

• l

1. Environmental Emergency Procedures (EG Series Procedures)

2. Emergency Log Book (for recording team activities)

3. Packet containing site and area maps, note pad, pencils or pens

4. Forms for recording timekeeping and/or dosimeter readings

5. Instrument Manuals G. First Aid Kit' Actual cuantitles of listed items are established by each nuclear l station.

7-19

April, 1984 edslon 4 8.0 MAINTAINING EMERGENCY PREPAREONE55 8.1 Organizational Preparedness 8.1.1 Division Vice-President and General Manacer, Nuclear Stations The Division Vice-President and General Manager, Nuclear Stations has overall responsibility for radiological emergency response planning within Commonwealth Edison. This individual is also the primary designated Recovery Group Manager.

A staff assigned to the Division Vice-President and General Manager, Nuclear Stations, has the responsibility for development and updating of the GSEP and coordination of the GSEP with other response organizations. This staff is headed by the Supervisor of Emergency Planning.

All personnel designated as directors in the GSEP organi-zation shall be appointed by the Division Vice President and General Manager, Nuclear Stations and documented by inclusion in the GSEP telephone directory listing of positions and personnel.

8.1.2 Station Superintendent I The Station Superintendent (or a designated alternate) has the responsibility to contact agencies with which the Station desires agreements for support during an emergency. This contact shall include:

1) An annual written invitation for members of these organi-zations to visit the station, Ciscuss the emergency plan, and familiarize themselves with plant facilities; and I personnel. I

2) Annual written offer by the nuclear stations to provice radiological training or retraining to members of these organizations with respect to their role in the emergency plan (also see Section 8.2); and

3) Once every two years, a recuest shall be mace for written confirmation of the availability of assistance from each supporting organization not already a party to the Illinois Plan for Radiological Accicents or the equivalent plans in Iowa and Wisconsin. Letters of agreement will be referenced in the site specific annex and the actual letters will be maintainea on file at each station respectively. Letters of agreement shall, as a minimum, state that the cocperating crganization will l provide their normal services in support of an emergency at the affected station.

8-1

April, 1984 Revision 4 The Station Superintencent has the following additional responsibilities:

4) Ensure the operational readiness of station communication systems for use during an emergency, by verification during drills (see Section 8.3.2.1);

5) Ensure the operational readiness of emergency equipment and supplies, such as, the Environs Team equipment (See Table 7.7-1), the Environs Team Van (at Mazon/Dresden, Quad Cities, and Zion), the TSC (See- Section 7.1.2), the OSC (See Section 7.1.3), and the equipment needed to classify an accioent (See Sections 5.0, 7.3-1 and the EAL section of the GSEP Annex);

6) Ensure that Station EPIPs are prepared as describeo in section 9.2 and are reviewed every two years; ano

7) Support the . Supervisor of Emergency Planning in the maintenance of the EOF and . Zion Back-up ECF, such as, maintenance of the health physics equipment stored there, and certain plant-related documents..

p 8.1.3 Medical Director .

The Commonwealth Medical Director is responsible- for obtaining, in accordance with Section 6.5.4, agreements for _ - the services of physicians - or clinics, and medical consultants specifically skilled in the medical aspects of radiation . accidents and other medical consultants as might be necessary for the ' case of

. a_ person involved in a radiation incident.

The Medical Director is responsible for maintaining. a supply of thyroid blocking agents within the company and for estaclishing policy for its use.

Following is Commonwealth Medical Director's policy regarding administration of Potassium Iodide (KI) as a thyroid blocking agent. -

1. M - dose of 130 mg KI (1 tablet) should be administered prior _ to receiving a projected calculated dose equivalent' to the thyroid of 25 rem or greater, or

2. One tablet should be taken as soon as- possible upon an individual oeing subjected for 1 to an airborne concentration of I-131 of 1.25 x 10 pur UC1/cc or greater.

8 April, 1984 Revision 4 8.1.4 Supervisor of Emergency Planning The Supervisor of Emergency Planning is responsible for ensuring- the operational readiness of the following offsite emergency response facilities:

1) The EOFs at Mazon, Morrison, Zion and Dixon (see Section 7.1.5);

2) The Corporate Command Center (see Section 7.1.4);

3) The Zion Back-up EOF in Libertyville (see Section 7.1.5).

4) The Prompt Notification System (PNS) (See Section 6.3.2).

'i

\

e 8-3

April, 1984 Revision 4 8.2 Training ,

The proficidncy of emergency personnel (as defineo in Section 2.0) .

is ensured by the following means:

1) Assigning persons to emergency duties which are similar to those performed as a part of their regular work assignment;

2) The initial and annual retraining of emergency personnel on applicable generic and site specific portions of the GSEP and corresponding Emergency Plan Implementing Procedures; and

3) Participation in exercises and drills designed to shaIpen those skills in which they are expected to use during a radiological emergency.

The training program for emergency personnel s1, lows each member to

-meet the following objectives:

o Know the objectives of the GSEP; o Understand the graded emergency classification system;

, o Display an adequate knowledge of personal responsibilities and i duties as listed in the GSEP and EPIPs; o Know the persons with w. om they may iriterface while performing GSEP functions; and ,

o Oisplay a functionab knowledge of the documents (e.g.,

procedures) necessary to fulfill their role in the GSEP.

The Commonwealth Proouction Training Department ha's the responsi-bility of ensuring that Comacnwealt.h emergency personnel receive all necessary training and retraining. In order to carry out this responsi-bility, the Supervisor. of Emergency Planning will notify- the Production l Training Department whenever new personnel are assigned GSEP related

positions.. The Production Training Department shall ensure that appropriate initial training, and retraining sessions are scheduled and glyan. It shall also maintain records of all emergency personnel trained.

Station personnel not specifically assigned to GSEP positions shall be proviced with an annual review of the GSEP by the Station training

~

staff. ,

?

s 8-4

, April, 1984 i

Revision 4 C " Commonwealth shall make an annual written offer to train those non-Commonwealth organizations referenced in the GSEP which may provice specialized services during a radiological emergency (e.g., fire-fighting, medical services, transport of injured, etc.). This training shall acquaint the participants with the special problems potentially encountered during a radiological emergency, notification procedures, and their expected roles. Those organizations who.must enter the site shall also receive on-site training. They will also , be instructed as to the identity (by position and title) of -those persons in the onsite organization who will control their support activites.

' Commonwealth Edison shall offer programs (at least annually) to acquaint news media with the GSEP, information concerning radiation, and points of contact for release of public information in an emergency.

9 4

n >

6-5

April, 1984 Revision 4

.8.3 Exercises and Drills 8.3.1 Exercises

.The Division Vice-President ano General Manager, Nuclear Stations, 'shall ensure- that Federally prescribed exercises are conducteo at each nuclear _ station in order to test the adequacy of l timing and content of implementing procedures and methods; to test emergency equipment and communication networks; and to ensure that emergency personnel are familiar with their duties. An exercise shall involve participation by Federal, State and local personnel as prescribed by the regulations.

I A written scenario shall be prepared for each exercise. This scenario shall include: .

1) The basic objective of the exercise;

2) The dates, time period, places, and participating organizations;

3) The simulated events; i 4) The time schedule of real and simulated initiating events;

5) A narrative summary describing the conduct of the exercise to include such things as simulated casualties, rescue of personnel, . deployment of radiological moni-toring teams, and public information activities; and

6) Arrangements for qualified observers.

Once every six years, an exercise should be scheduled between the hours of 6:00pm and midnight, and another between midnight and 6:00am.

A critique shall be conducted as soon as practical after. each exercise. The critique shall' evaluate. the ability of the GSEP l organization to respond to a simulated emergency situation as called for in the GSEP.

8-6

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

April, 1984 Revision 4 8.3.2 Drills 8.3.2.1 Communications Drills The GSEP communications systems outlined in Section 7.2 of this plan shall be fully tested annually.

The capability of (NARS) to notify the Illinois Emergency Services and Disaster Agency, the Illinois Department of Nuclear Safety, the Iowa Office of Disaster Services (for Quad' Cities Station), the Wisconsin Division of Emergency Government (for Zion Station), and appropriate local agencies shall be demonstrated at least monthly. The capability (ENS &

.hPN) to notify the MC from the Control Room, TSC and EOF shall be demonstrated at least monthly.

The capability to notify the MC Region III, FEMA Region V and VII and American Nuclear Insurers (ANI) and federal emergency response organizations as listed in the GSEP Phone Directory shall be demonstrated from the Commonwealth corporate office at least quarterly. Other GSEP communication ano computer equipment shall be functionally tested each

, , calendar quarter.

8.3.2.2 Fire Drills Fire drills shall be conducted at each nuclear station in accordance with Station Technical Specifications and/or

~

Station procedures.

8.3.2.3 Environmental Monitoring Drills Plant environs and radiological monitoring drills shall be conducted annually. These drills should include collection and analysis of sample media such as water, grass, soil, and air.

8.3.2.4 Health Physics Drills Health Physics Orills- shall be concucted semi-annually. These drills shall incluoe response to, and analysis-of, simulated airborne and liculd samples within the plant. At least annually, these drills shall include a test of post-accident sampling systems.

8.3.2.5 Medical Emergency Drills A medical emergency drill, involving a simulated contaminated individual, which contains provisions for participation by local support services agencies (i.e.,

ambulance and support hospital) shall be conducted annually at each nuclear station. The offsite portions of the medical drill may be performed as part of the required exercise.

8-7 L

April, 1984 Revision 4 8.3.2.6 Assemoly and Accountability Orills An assembly and accountability drill shall be conducted annually. The drill shall include identifying the locations of all individuals within the protected area after an assembly is announced.

I 8.3.2.7 Offshift Auamentation Orill' Each station shall initiate an unannounced offshift notification drill at least every six months. These drills shall involve implementation of the individual station's ]

notification procedure and documentation of the times at which persons are notified. This drill shall serve to demonstrate the capability to augment the onshift staff in a short period after declaration of an emergency.

8-8

4 April, 1984 Revision 4

- 8.4 Public Education and Information Commonwealth Edison is committed to the distribution of

- informational brochures on an annual basis. These brochures shall be oistributeo to the public residing within the ten mile plume exposure EPZ and shall address how they shall be notified and what their actions should be in an emergency.

The public information brochure shall. include the following infor-mation: what to do if a take-shelter request is given, what to do if an evacuation request is given, educational information concerning radiation, a map of major evacuation routes, a list of communities likely to serve as host shelter areas, and instructions on how to obtain additional information, especially for the disabled or their caretakers ano those without transportation.

The public information brochure described above shall be mailed to all- residents in the plume exposure EPZ of each nuclear station and shall also be provided to appropriate locations where a transient population may obtain a copy.

I e

8-9

8.5 April,1984 Revision A Distribution, Review, and Updating of the GSEP and Correscon s To ensure that the GSEP and the corresponding Emergency Plan Implerrenting Procedures are kept current and that updated c Emergency Planning shall ensure the following: maint v sor of 1)

Each GSEP manual shall be assigned a serial number; 2)

/ n assignment record shall be maintained of all GSEP man 3)

GSEP individuals manuals requiringshall them, be distributed including directors onof aGSEP controlpos and all appropriate Federal, State, and local agencies; 4)

The GSEP shall be reviewed and updated as needed; be certified (recorded) as current on an annual thebasis; GSEP will 5)

Proposed revision to the GSEP shall be reviewed ved andby aopro

{ an each nuclear generating station's Onsite Review Committee CECO Offsite Review committee. Documentation regarding this ;

review ano approval shall be maintainea in the appropriate generating statioh and CECO corporate office files. i to this review ano approval the GSEP shall be: In addition a) b) Reviewed by the Supervisor of Emergency Planning Approvec by the Technical Services Manager, Nuclear Stations Division c)

Authorized for use by the Division Vice-President and General-Manager, Nuclear Stations Division 6)

All persons in possession of receive authorized changes. an authorized GSEP manual shall dated and markeo to show where changes have pages added and old pages destroyed; new been m

{

7) Emergency Plan Implementing Procedures shall te developed consistent years. with the GSEP (see Section 9.2) and reviewed eve (Station conducted for Station Superintendents EPIPs); shsil ensure that this review is 8)

Names and phone numbers of the GSEP organization and sup personnel shall be reviewed and updated at least quarterly;

9) ,

Whenever exercises ano/or orills indicate deficiencies GSEP ortocorresponding in the necessary ensure corrective EPIPs, action. such documents shall be revis 10)

The public information brochures are distributed annually .

t 8-10

'{

April, 1984 Revision 4 An independent audit of the GSEP shall be conducted on an annual basis by the Commonwealth Quality Assurance Department. Actions shall be taken for evaluation and correction of all audit findings.

8.6 Emergency Eculpment and Supplies Various types of emergency equipment and supplies are maintained as required by this plan which specifies that items must be kept in the EOF, Zion Back-up - EOF, TSC and the OSC. The list of the emergency equipment and supplies are specific in the corporate EPIP's. This plan also identifies a typical list of equipment to be maintainec for offsite emergency monitoring Table 7.7-1 (storage location may vary). The operational readiness of these and other supplies is ensured by quarterly inventory and inspection required by each ' Station's procedures and their use during the required drills and exercises.

l 8-11

F-April 1984 Revision 4 9.0 APPENDIX 9.1 Required Content of Site Specific Annex The Generating Stations Emergency Plan (GSEP) consists of two parts, a generic plan and .a site specific annex for each nuclear station. The site specific annex shall be developed by the respective nuclear station and shall contain information and guidance which is unique (site spec-ific) to the station. The annex becomes part of the plan and is subject to the same review and audit requirements as the generic plan.

9.1.1 Annex Format and General Content The annex format shall conform to the format used in the generic plan. Information that is in the generic plan need not be restated in the annex; however, it may be desirable to do so in some cases in the interest of continuity and clarification. The annex shall adoress how (means, methods, resources) the requirements and responsibilities set forth in the generic plan are to be satisfied.

9.1.2 Annex Content (Specific)

References have been made throughout the generic plan that e additional information shall be in the site specific annex. Some areas require little aoditional information while other areas re-quire significant input. As a minimum, site specific annexes shall adoress the areas described in the following subsections.

9.1.2.1 Introduction Define the unit, station and surrounding area (include maps, drawings and/or diagrams) and address in a summary statement the annex's interface with the generic GSEP and' Station proceoures. Include a map or table that indicates the population oistribution around the nuclear station.

9.1.2.2 Definitions Provide definitions and/or abbreviations for terms used in the annex which are unique or have a meaning qr connotation that differs from normally accepted usage.

9.1.2.3 Summary of Emergency Plan Acoress in a summary statement the participating status "

of state and local authority with regard to increasing severity of emergency classifications.

9-1 -

r.

April 1984 Revision 4 9.1.2.4 01:;anizational Control of Emergencies o Specify organization and manning for both day and night crews (to include health physics organization).

o' Acdress the Station's commitment to augment the onsite emergency organization following declared GSEP emergencies, o Specify the agencies with which the Station has independent agreements for support during an emergency.

9.1.2.5 Classificatiori of Emercency Conditions Include a table of EALs for all emergency classes.

9.1.2.6 Emercency Meae.ures o Address provisions for the classification and declaration of an emergency from the control room. Specify the line of authority and responsibility for emergency classification and

(~

for contacting State and local authorities (of-ficials) who have the responsibility for taking protective actions in the interest of the public. Also specify who has authority and responsibility for recommending to state and local authority the protective actions to be taken, to include recommending evacuation.

o Describe the means (methods) of State and local governments in notifying the public of an emergency condition and of the protective accions to be taken during an emergency.

o Include a table and/or map indicating evacuation time estimates for members of the public.

o Include a map indicating the location of onsite l-assemoly areas.

o Include map indicating site evacdation routes l- and address site personnel relocation and ac-

countability and monitoring of site evacuees.

Also address roadway / traffic control measures of roads under the control of the station.

, o Incluce a plot of Containment Activity versus N. Radiation Level for the four points. described in Section 6.2.4 of the generic GSEP.

i 9-2

April 1984 Revision 4 9.1.2.7 Emergency Facilities and Eculpment o Include "as built diagrams" and cescriptions of the Station Control Room, Operational Support Center, the Technical Support' Center, ano the Emergency Operations Facility.

o Include a description of the Station seismic instrumentation, radiation monitoring equipment, fire protection equipment, and meteorological instrumentation, o Specify location of offsite fixed radiation environmental monitors including the rings of TLDs.

o Describe the capability and resources available to categorize accidents, including provisions for:

a) Detection of inadequate core cooling; b) Monitoring of high level radiation reading ir the containment; c) Post-accident sampling; and

. d) Monitoring of in-plant lodine.

o Specify the onsite dedicated communications to be established ano maintained during an emergency.

9.1.2.8 Maintaining Emergency Preparedness o Address the Station requirements to provide training of emergency personnel, o Describe the means (methods) of ensuring that local agencies, media, general public (including transient populations) are provided educational information concerning planning in their behalf.

4 9-3

April 1984 Revision 4 9.2 Required Content of Emergency Flan Imolementing Procedures ,

Emergency Plan Implementing Procedures (EPIPs) that are necessary for implementation of this plan shall be developed and updated as described in Section 8.5. The content and format of the EPIPs shall be in accordance with this plan (GSEP) and guidelines issued by the Division l Vice- President and General Manager, Nuclear Stations. I Each Station Superintendent is responsible for ensuring that the station's EPIPs are oey? loped which address the following subject areas:

1) Notification procedures using call lists to notify offsite authorities and to mobilize station personnel for all emergency conditions;

2) Emergency classification through the use of Emergency Action Levels;

3) Calculation procedures that provice a brief and relatively simple method of determining offsite dc:es from plant releases;

4) Radiological survey procedures for emergency surveys in the g plant ano for onsite areas;

5) Corrective actions aimed at correcting the emergency situation ,

at or near the source of the problem (e.g., firefighting);

6) Personnel monitoring and decontamination procedures for individuals leaving restricted areas or other areas known or suspected of being contaminated;

7) Evacuation procedures for " Protected Area" and Site Boundry. l

8) Methods of personnel accountability that ensure all indivicuals within the site are warned of imminent threats or hazardous conditions;

9) Methods and instructions' for receiving, transporting, and handling injured persons and providing onsite first aid and offsite mecical treatment; 8

9-4

April 1984 Revision 4

10) . Assignments of responsibility and access control for ensite emergency control centers;

11) Operation and use of onsite emergency communication systems;

12) Inventory and operational readiness of emergency equipment and supplies; and

13) GSEP organization and support agency phone numbers.

Information to be addressed in Station EPIPs may be fulfilled by other station procedures, but those procedures shall be referenced within the context of the EPIPs.

The Supervisor of Emergency Planning is responsible for ensuring that l general office EPIPs are developed which address the following subjt Ot areas:

1) Notification procedures using call lists to notify corporate management, offsite GSEP organization personnel, State authorities, and offsite emergency response organizations;

(' 2) Detailed procedures for determining projected and actual doses to members of the public following a release of radioactive material from a nuclear station;

3) Detaileo procedures for radiological surveys of the environs;

4) Operation and use of offsite emergency response facilities, computers and communications;

5) Assignments of responsibility and access control for offsite emergency control facilities; I

6) Methods of disseminating information to the media and the general public;

7) Procedures that acdress the exercise and drill program;

8) Procedures that address the recovery of a nuclear station to a pre-accident status, including reentry into previously evacuated areas, decontamination of the affected site, repair of critical plant equipment, and disposal of contaminated equipment and waste. It is not practical to plan detailed recovery actions for all conceivable situations in advance, but procedures that include at least initial ' planning considerations should be developed. Detailed procedures shall be develcped after an emergency situation occurs as necessary; and k 9) GSEP organization anc support agency phone numbers.

9-5

April 1984 Revision 4 9.3 Additional Emergency Response / Notification Recuirements The Generating Stations Emergency Plan is a plan written primarily to comply with the requirements of 10 CFR 50, P r 'raph 50.47 and Appenoix E. As such, GSEP addresses emergency con . . ;ns as definea in NUREG 0654. On the basis of other regulatory requirements, additional emergency conditions and required notifications have been defined. These regulations are listed below and define emergency conditions that may or may not warrant an emergency declaration under the GSEP in accoroance with Section 5.0 of this plan:

1) 10 CFR 50.70, " Inspections, Records, Reports, Notifications".

2) 10 UR 73, " Physical Protection of Plants and Materials".

3) 33 7R 153, " Control of Pollution by 011 and Hazardous Substances."

4) 10 CFR 20.403 and State of Illinois Rules and Regulations for Protection against Raciation, Section D.403, " Incident Notifi-cation Requirements."

( 5) 10 TR 50.72 Immediate Notification Requirements for Operating Nuclear Power Reactors.

Tne following sections summarize the actions required in accordance ~ with the above rules and regulations.

9.3.1 Notifications of NRC Coerations Center l An on-outy Station Management person shall notify the NRC Operations Center via the tRC's Emergency Notification System of:

1) The declaration of any of the EMERGENCY CLASSIFICATICNS as specified in the GSEP, or

2) Those NON-EMERGENCY events specified in 10 ER 50. 72 paragraph (b).

If the NRC's Emergency Notification System is inoperative the required notificalons shall be made via commercial telephone service, other dedicated telephone service, or any other method which shall ensure that a report is made as soon as practical to the NRC Operations Center. Refer to the GSEP telephone directory for the NRC Operations Center phone number.

The GSEP Emergency Classification shall be reported to the NRC Operations Center immediately after notification of the appropriate State or local agencies but not later than one (1) nour after the time of classification.

9-6

April 1984 Revision 4 Declaration of "NON-EMERGENCY" events in accordance with 10 CFR 50.72 paragraph (b), shall be reported via the Emergency Notification System to the tEC Operations Center in accordance with the "OtE-h0UR REPORT" or "FOUR-HOUR REPORT" criteria.

The Non-Emergency Event "ONE-HOUR REPORT" shall ' be made to the NRC Operations Center as soon as practical and ' in all cases within one hour of the occurrence of any of the items listec in 10 CFR 50.72 paragraph (b) (1), subparagraph 1, thru vi.

The Non-Emergency Event "FOUR-HOUR REPORT" shall be to the MC Operations Center as soon as practical and in all cases, within four (4) hours of the occurrance of any of the items listed in 10 CFR 50.72 paragraph (b) (2), subparagraph 1, thru vi.

Initial notification to the NRC Operations Center shall so state: the Emergency Class declared, or "One-Hour Report", or "Four-Hour Report" as well as necessary details to describe the event per 50.72 (b) (1) or (b) (2), as applicable.

Followup notifications shall be reported to the NRC Operations Center immediately, but not later than one (1) hour if:

1) there is any further degraation in the. level of safety of the plant or other worsening plant conditions occur such that a GSEP Emergency Classification is now applicable,

11) there is any change from one Emergency Class to another, or 111) there is a termination of the Emergency Class is declared.

Aoditional followup notifications shall also be reported to the NHC Operations Center immediately, but not later than one (1) hour to inform the NRC of:

iv) the results of evaluations or assessments of plant conditions, v) the effectiveness of response or protective measures taken, or vi) information related to plant behavior that is not understood.

If recuested by the NRC maintain an open, continuous communications channel with the PRC Cperations Center.

F-7 .

t April 1984 9.3.2 Revision 4 Nuclear Station Security Plan Each nuclear station shall have a Security Plan that complies with the requirements of 10 CFR 73.

The interface between the GSEP and the Nuclear Station Security Plan is basically one of parallel operation. The plans are compatible. The GSEP emergency response measures, once initiated, are executed in parallel with measures taken in accordance with the Station Security Plan.

The Nuclear Station Security Plan, Appendix C, Contingency Events, identifies situations which could be initiating conditions for CSEP response measures. Contingency events include bomb threats, attack threats, civil disturbances, protected area intrusions, loss of guard / post contact, vital area intrusions, bomb devices discovered, loss of guard force, hostages, extortion, fire /

explosions, internal disturbances, security communications failure, and obvious attempts of sabotage. The Station Security Plan pro-vides guidance for decisions ano actions to be taken for each secur-ity contingency event. As guidance, the Security Plan allows for differing responses depending upon the assessment of the actual

, situation within each contingency event classification.

e The asssessment of any security contingency event and the decision to initiate, or not to initiate the CSEP will be the responsibility of the Station Director or the Shift Engineer acting as the Station Director. I411 identified security contingency events have the potential of being assessed as initiating conditions for an emergency declaration under the GSEP.

9.3.3 Control of Pollution by 011 and Hazartous Substances 9.3.3.1 Reportable Discharces of 011 or Hazardous Substances A reportable discharge for the purp'ose of compliance with 33 CFR 153 is defined as the spilling, leaking, cumping, pouring, emitting, emptying, or dumping into or upon any public water body of:

o 011 in such quantities as to cause a film or sheen upon or discoloration of the water or upcn adjoining shore-lines; or o Hazardous substances designated in 40 CFR 116 in quantities equal to or exceeding in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period the harmful quantities establish in 40 CFR 118.

Also, PCB fluid leaks or discharges of greater than one-half gallon or ten pounds are considered as reportable incidents.

9-8 b

S April 1984 Revision 4 9.3.3.2 Reportina Procedure Upon learning of a reportable' discharge as described in Section 9.3.3.1 above, the Station Superintendent 'or an alternate shall immediately notify the Duty Officer, National Response Center, U.S. . Coast Guard, toll free telephone number 1-800-424-8802. If notification to the National Response Center is not possible or practical, notice shall be given to each of the following officials in order of priority:

1) Designated EPA / Coast Guard On-Scene Coordinator (OSC); and

2) Commanding Officer of any Coast Guard unit in the vicinity of the discharge; and i

3) Commander of the Coast Guard district in which the discharge occurs.

In addition, the Station Superintendent or an alternate shall notify:

1) The Director of Water Quality, Environmental

./ Affairs; and i

2) The Division Vice President and General Manager, Nuclear Stations Division.

9.3.3.3 Spill Prevention Control and Countermeasure Plans, l Each generating station shall have a Spill Prevention Control and Countermeasure (SPCC) Plan prepared in accordance with 40 CFR 112.7 in order to minimize the potential for oil cischarges. No SPCC Plan shall be effective unless it has been revieweo and certified by a Registered Professional Engineer. Each SPCC Plan shall be reviewed and evaluated at least once every three years in accorcance with 40 CFR 112.5.

Upon learning of an oil discharge into a navigable waterway at levels determined to be harmful to the puolic health or welfare, the United States Coast Guard must be immediately notifiec as set forth in Section 9.3.3.2.

The exact criteria for declaring oil discharges and the subsequent notification procedure shall be defined in the SPCC Plan and/or Station Emergency Plan Implementing Procedures.

9-9

April 1984 Revision 4 9.3.4 Incicent Notification Recuirements for the NRC Region III Office ano the Illinois Department of Nuclear Safety In accoroance with 10CFR20 -

Standards for Protection Against' Radiation Section 20.403 Notification of Incidents the following actions shall be taken by the appropriate CECO personnel.

An on-duty Station management person shall immediately notify the mC Region III Office and the Illinois Department of Nuclear Safety by telephone, telegraph, mailgram, or facsimile of any incident involving any source of radiation possessed by the Station and which may have caused or threatens to cause:

1) A dose equivalent to the whole body of any individual of 25 rems or more of radiation; a dose equivalent to the skin of the whole body of any individual of 150 rems or more of radiation; or a dose equivalent to the feet, ankles, hands, or forearms of any individual of 375 rems or more of radiation; or, l

l 2) The release of radioactive material in concentrations which if f

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 specifleo for such materials in Appendix 8 Table II l/. of 10CFR2Q; or, t

l 3) A loss of one working week or more of the operation of any facilities affected; or,

4) Damage to property in excess of $200,000.*

An on-duty Station management person shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify the MC Region III Office and the Illinois Department of Nuclear Safety by telephone and telegraph, mailgram, or facsimile of any incident involving any source of radiation possessed by the Station and which may have caused or threatens to cause:

1) A dose equivalent to the whole body of any individual of 5 rems or more of radiation; a dose equivalent to the skin of the whole body of any individual of 30 rems or more of radiation; or a dose equivalent to the feet, ankles, hands, or forearms of 75 rems or more of radiation; or,

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 Appendix 8, Table II of 10 CFR 20; or,

3) A loss of cne day or more of the operation of any facilities affected; or,

4) Damage to property in excess of $2,000.*

• For the State of Illinois, the property oamage reporting recuirements are

$100,000 and $1,000 for immediate and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification, respectively.

9-10 E

i April 1984 9.3.5 Revision 4 Reports of Theft or Loss of Radiation Sources and/or Licensed Materials In accordance with " Illinois Rules and Regulations for o rotection Against . Radiation" Section O.403 and 0.402 Amended sections 9.3.5.1 to 9.3.5.3 have been developed. 4-29-76 the following In addition this section also reqJires reporting to the appropriate NRC offices in accordance with 10 CFR 20 Section 20.402. These requirements are discussed in Sections 9.3.5.4 and 9.3.5.5.

9.3.5.1 Initial Notification Source. to the Illinois ONS of Loss of Radiation An on-duty Station management person shall immediately notify the Illinois Department of Nuclear Safety by telephone and telegraph, mailgram, or facsimile of the theft or loss of any inventoried source of ionizing radiation after such occurrence becomes known.

9.3.5.2 Initial in Notification unrestricted Area.to the Illinois DNS of Substantial Hazard An on-cuty Station management person shall immediately report to the Illinois Department of Nuclear Safety, after its occurrence becomes known to the licensee, any loss or theft of licensee material in such quantities and under such circumstances that it appears to the licensee that a substantial ' hazard may result to persons in unrestricted areas.

9.3.5.3 Notification of CECO Personnel.

An on-outy Station management person shall upon following notification to DNS and/or NRC as referenced in paragraph 9.3.5.1 and/or 9.3.5.2 above, "immediately" notify both the System Outy Power Officer (N00). Supply Office (SPS0) Dispatcher, and the Nuclear by the Station by calling The'the SPS0 tOO.will ensure the POO is contacted

' 9.3.5.4 Initial Notification to the NRC of Loss or Theft of Licensec Materiai An on-outy Statior, Management person shall report by telephone to the Director of the NRC Inspection and Enforcement office as listed in Appendix 0 of 10CFR20, immediately after its occurance becomes known to the licensee, any loss or theft of licensed material in such quantities and under such circurrdances that it appears to CECO personnel that a substantial hazard may result to persons in " Unrestricted Areas".

9.3.5.5 Followup Notification Material to the BRC of Loss or Theft of Licensed ECo personnel at the station where the loss or theft of ) '

Licensed Material had occurred will perform the following report within thirty (30) days to the appropriate PRC offices in

accordance with 10CFR20 Section 20.402.

9-11 ,

April 1984 Revision 4 9.4 Bibliography References and supporting plans consulted in writing the Commonwealth Generating Stations Emergency Plan are listed in this section. With exception of regulatory requirements, inclusion of material' on this list does not imply adherence to all criteria or guidance stated in each individual reference.

1) Cooe of Federal Regulations, Title 10, Chapter 1 Parts 20, 50, 73, and 100.

2) Code of Federal Regulations, Title 33, Chapter 1, Part 153.

3) Code of Federal Regulations, Title 40, Chapter 1, Parts 110, 112,116, and 118.

4) Code of Federal Regulations, Title 44, Chapter 1, Part 401.

5) Code of Federal Regulations, Title 49, Chapter 1, Parts 171 and 172.

6) Commonwealth Edison Quality Assurance Manual.

/

7) EPH " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," 1975.(and updated,1979).

I

8) NUREG 0396, " Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans in Support of Light Water Nuclear Power Plants," Dec. 1978.

9) MJREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

10) NUREG 0654, " Criteria for Preparation and Evaluation of oa dio-logical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Revision 1, November,1980.

11) NUREG 0696, " Functional Criteria for Emergency Response Facilities."'

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

9-12

• April 1984 Revision 4 L

13) " Illinois Rules and Regulations for Protection Against Radiation," l

} Section 0.403 and 0.402 Amenced 4/29/76.

- 14) Ef% 520/1-78-0018, " Protective Action Evaluation, Part 2, Evacuation and Sheltering as Protective Actions against Nuclear Accidents Involving Gaseous Heleases".

15) "Consonwealth - Edison description, latest Offsite approved copy. Oose Calculation System,"' system j

16) " Emergency Preparedness INPO Criteria," dated February 12, 1980. I

17) ANSI /ANS 3.7.2 - 1979, " Emergency Control Centers for Nuclear Power Plants."

- 18) ANSI /ANS 3.7.3 - 1979, " Radiological Emergency Prepareoness Exercises for Nuclear Po'wer Plants."

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

/ 20) Illinois Plan for Radiological Accidents (IPRA), l Latest approved copy.

21) The Iowa Emergency Plan, Latest approved copy. l

22) State of Wisconsin Peacetime Radiological Emergency. Response-Plan.

23) " Radiological Assistance Plan," Region 5, Department of Energy, l Latest approved copy

24) INPO Emergency Response Plan, Latest approved copy. l

25) NUREG 0737, " Clarification of TMI Action Plan Requirements,"

November, 1980.

26) " Evacuation Time Estimates for Areas Near Nuclear Power Plants -

Dresden, Quad Cities, Zion, LaSalle County Stations", 0.L. Peoples letter to 8.K. Grimes, cated March ' 11, 1980. Preliminary.

estimates for Byron and Braiowood Station were submitted by letter to D. G. Eisenhut,. MC, from L.O. DelGeorge, on August 29, 1980.

' A document " Evacuation Time Estimates Within the P10me Exposure Pathway Emergency Planning Zone for the Byron Nuclear Generating

' Station", dated December 1982, was submitted to the Byron ASLB in Oecember 1982.

27) " Voluntary Assistance Agreement By ano Among Electric Utilities i Involved in Transportation of Nuclear Materials," cated November i 1, 1980.

9-13 t

, April 1984 Revision 4

28) Comprehensive Environmental Response, Compensation and Liability Act of 1980.

29) NUREG 0728 " Report to Congress: NRC Incident Response Plan".

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

31) USNRC Regulatory Guide 1.101, " Emergency Planning and Preparedness for Nuclear Power Reactors", revision 2, October, 1981

32) American Nuclear Insurers Bulletin #5B (81).

33) " Potassium Iodide as a Thyroid Blocking Agent in a Radiation e Emergency: Final Recommendations on Use", Federal Register Vol. !

47, No. 125, June 29, 1982.

l

34) NUREG 0737 Supplement #1 or latest submitted scheduled of planned operational dates. i

35) CECO April 1983 response to NUREG 0737 Supplement #1 or latest submitted schedule of planned operational dates.

4. ~

36) William J. Dircks, Executive Director for Operations, NRC, to Dr. Donald F. Knuth, President KMC, Inc. dated October 26, 1981 9-14