SBK-L-22040, Radiological Emergency Plan (Ssrep), Revision 782

Radiological Emergency Plan (Ssrep), Revision 782

ML22110A172
Person / Time
Site:	Seabrook
Issue date:	04/20/2022
From:	Levander M NextEra Energy Seabrook
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
SBK-L-22040
Download: ML22110A172 (219)

Text

{{#Wiki_filter:NEXTera ENERGY ~ SEABROOK April 20, 2022 Docket No. 50-443 Docket No. 72-63 SBK-L-22040 United States Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001 Seabrook Station Radiological Emergency Plan (SSREP), Revision 78 In accordance with the requirements of 10 CFR 50, Appendix E; 10 CFR 50.4, and 10 CFR 72.44(£), enclosed is Revision 78 to the Seabrook Station Radiological Emergency Plan (SSREP). The revision does not reduce the effectiveness of the SSREP, and the SSREP continues to meet the standards of 10 CFR 50.47(b) and 10 CFR 50, Appendix E. The Resident Inspector copy is provided directly through the NextEra Energy Seabrook, LLC records management system. provides a summary of changes to the SSREP. Enclosure 2 provides a summary of the change analysis required by 10 CFR 50.54(q)(5), and Enclosure 3 provides a copy of the revised manual sections. Should you have any questions regarding the enclosed revisions, please contact me at (603) 773-7631. Sincerely, Matthew Levander Regulatory Affairs Manager NextEra Energy Seabrook, LLC PO Box 300, Seabrook, NH 03874

United States Nuclear Regulatory Commission SBK-L-22040 I Page 2 cc (with enclosures): J. Ambrosini, Region I, Division of Reactor Safety cc (without Enclosure 3): ATTN: Document Control Desk Director, Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards Nuclear Regulatory Commission Washington, DC 20555-0001 J. Poole, NRC Project Manager, Project Directorate I-2 cc (without enclosures): D. Lew, NRC Region I Administrator C. Newport, NRC Senior Resident Inspector

Enclosure 1 to SBK-L-22040 Summary of Changes Radiological Emergency Plan (SSREP), Revision 78

• Removed requirement for Environmental Analyst to respond to the EOF at an Alert.
• Removed PSNH Electrical System Control Center as a source of meteorological information.
• Removed requirement that the mobile communications with the offsite survey teams be push-to-talk. This change was previously presented and approved at ORG (ref. ORG Meeting 21-01AR2355399) however the change was not included in revision 77 due to an administrative error.
• Removed reference to the Health Physics (HP) Alternate Checkpoint radio console.
• Replaced SNC (Science and Nature Center) with JIC (Joint Information Center).
• Revised to read that the Response Manager is experienced as a senior manager vs. is a semor manager.
• Removed Licensing Coordinator Position. Reduced EOF Support Staff from 4 to 2.

Reduced Training Center Staff from 2 to 1.

• Reduced I&C Personnel from 2 to 1.
• Removed BOP Support Engineer, Electrical Support Engineer, NSSS Support Engineer, and Maintenance Coordinator.
• Revised Emergency News Manager's response location to the Joint Information Center or other appropriate location.
• Clarified that the New Hampshire and Massachusetts departments of Public Health call the Seabrook Station ERO per the Letter of Agreement in Appendix A.
• Changed title Technical Training Supervisor to Operations Training Supervisor.
• Changed title from Operations Support Manager to Assistant Operations Manager - Line
• Appendix A - Removed BOP Support Engineer, Electrical Support Engineer, Maintenance Coordinator, NSSS Support Engineer, and Licensing Coordinator.
• Appendix G-- Replaced Emergency Preparedness Drill and Exercise Manual (EPDE) with EP-AA-101-1000, Nuclear Division Drill and Exercise Procedure.

Enclosure 1, Page 1 of 1

Enclosure 2 to SBK-L-22040 Change Analysis Summary Radiological Emergency Plan (SSREP), Revision 78

• Section 6.1.4 - Removed requirement for Environmental Analyst to respond to the EOF at an Alert.
• Section 6.2.3.1 - Removed PSNH Electrical System Control Center as a source of meteorological information.
• Section 7.5.1 - Removed requirement that the mobile communications with the offsite survey teams be push-to-talk. This change was previously presented and approved at ORG (ref. ORG Meeting 21-01AR2355399) however the change was not included in revision 77 due to an administrative error.
• Section 7.5.2-Removed reference to the Health Physics (HP) Alternate Checkpoint radio console.
• Figure 8.2 -Replaced SNC (Science and Nature Center) with JIC (Joint Information Center).
• Section 8.2.2.2 - Revised to read that the Response Manager is experienced as a senior manager vs. 1s a semor manager.
• Figure 8.4-Removed Licensing Coordinator Position. Reduced EOF Support Staff from 4 to 2. Reduced Training Center Staff from 2 to 1.
• Figure 8.5 - Reduced l&C Personnel from 2 to 1.
• Figure 8.6-Removed BOP Support Engineer, Electrical Support Engineer, NSSS Support Engineer, and Maintenance Coordinator.
• Section 9.2.1 -Revised Emergency News Manager's response location to the Joint Information Center or other appropriate location.
• Section 11.1 - Clarified that the New Hampshire and Massachusetts departments of Public Health call the Seabrook Station ERO per the Letter of Agreement in Appendix A.
• Section 12.6 - Changed title Technical Training Supervisor to Operations Training Supervisor.
• Section 12.7 - Changed title from Operations Support Manager to Assistant Operations Manager - Line
• Appendix A-Removed BOP Support Engineer, Electrical Support Engineer, Maintenance Coordinator, NSSS Support Engineer, and Licensing Coordinator.
• Appendix G -- Replaced Emergency Preparedness Drill and Exercise Manual (EPDE) with EP-AA-101-1000, Nuclear Division Drill and Exercise Procedure.

Enclosure 2, Page 1 of 3

Removed requirement for Environmental Analyst to respond to the EOF at an Alert Removed requirement for Environmental Analyst to respond to the EOF at an Alert because there are no field team samples to analyze as field teams are deployed at a Site Area Emergency or General Emergency per section 9 .2.3. Removed PSNH Electrical System Control Center as a source of meteorological information Removed PSNH Electrical System Control Center as a source of meteorological information as this is no longer used. Removed requirement that the mobile communications with the offsite survey teams be push-to-talk Removed requirement that the mobile communications with the offsite survey teams be push-to-talk as there is no requirement for the mobile communications to specifically be push-to-talk. This change was previously presented and approved at ORG (ref. ORG Meeting 21-01 AR 2355399) however the change was not included in revision 77 due to an administrative error. Removed reference to the Health Physics (HP) Alternate Checkpoint radio console Removed reference to the Health Physics (HP) Alternate Checkpoint radio console as the Alternate HP Checkpoint is not a credited Emergency Response Facility. Replaced SNC (Science and Nature Center) with JIC (Joint Information Center) The Science and Nature Center was replaced by the Joint Information Center in SSREP Revision 77, however "SNC" remained in Figure 8.2. Revised to read that the Response Manager is experienced as a senior manager vs. is a senior manager Revised to read that the Response Manager is experienced as a senior manager vs. is a senior manager. The SSREP Appendix A was revised to allow the Response Manager to be a past or current Senior Manager (ref. SSREP Rev. 66, AR 01956417, CRC 2192, ORG 2014-14). This change corrects section 8.2.2.2 to allow the Response Manager to be experienced as a Senior Manager vs. currently a Senior Manager. Removed Licensing Coordinator Position. Reduced EOF Support Staff from 4 to 2. Reduced Training Center Staff from 2 to 1. Responsibilities have been transferred to other ERO members or are no longer needed. Reduced l&C Personnel from 2 to 1 Responsibilities have been transferred to other ERO members or are no longer needed. Removed BOP Support Engineer, Electrical Support Engineer, NSSS Support Engineer, and Maintenance Coordinator. Responsibilities have been transferred to other ERO members or are no longer needed. Revised Emergency News Manager's response location to the Joint Information Center or other appropriate location. Revised Emergency News Manager's Unusual Event response location from the site to the Joint Information Center or other appropriate location. Enclosure 2, Page 2 of 3

Clarified that the New Hampshire and Massachusetts departments of Public Health call the Seabrook Station ERO per the Letter of Agreement in Appendix A. Clarified that the New Hampshire and Massachusetts departments of Public Health call the Seabrook Station ERO per the Letter of Agreement in Appendix A. Changed title Technical Training Supervisor to Operations Training Supervisor. Changed title from Operations Support Manager to Assistant Operations Manager - Line Appendix A - Removed BOP Support Engineer, Electrical Support Engineer, Maintenance Coordinator, NSSS Support Engineer, and Licensing Coordinator. Responsibilities have been transferred to other ERO members or are no longer needed. Appendix G -- Replaced Emergency Preparedness Drill and Exercise Manual (EPDE) with EP-AA-101-1000, Nuclear Division Drill Enclosure 2, Page 3 of 3 to SBK-L-22040 RMD Controlled Copy _____________ SEABROOK STATION PROGRAM MANUAL Seabrook Station Radiological Emergency Plan SSREP Manual Owner: Rev. 78 D. Currier

SEABROOK STATION RADIOLOGICAL EMERGENCY PLAN (SSREP) TABLE OF CONTENTS CONTENT PAGE

1.0 INTRODUCTION

1-1.1 2.0 DEFINITIONS 1-2.1 3.0 RADIOLOGICAL EMERGENCY PLAN

SUMMARY

1-3.1 3.1 Introduction 1-3.1 3.2 Station Emergency Response 1-3.1 3.3 Local and State Government Responses 1-3.3 3.4 Federal Government Response 1-3.3 Figure 3.1 Notification Plan Figure 3.2 Relationship of the Seabrook Station ERO to Offsite Organizations 4.0 THE AREA 1-4.1 4.1 The Site 1-4.1 4.2 Area Characteristics, Land Use and Demography 1-4.1 4.2.1 Area Characteristics 1-4.1 4.2.2 Uses of Adjacent Lands and Waters 1-4.2 4.2.3 Population Distribution 1-4.2 4.3 Emergency Planning Zones 1-4.2 Table 4.1 Summary of Peak Population Estimates of Communities within 0 to 10 Miles of the Site Table 4.4 Communities Within the Seabrook Station Plume Exposure Pathway Emergency Planning Zone Figure 4.1 Site Boundaries Figure 4.2 Major Routes in 10 Mile Study Figure 4.3 Site Layout Figure 4.4 2010 Resident Population Distribution within a 0-10 Mile Radius of Seabrook Station Figure 4.6 Estimate Peak Transient Population (0-10 Miles) Figure 4.7 Seabrook Station "Plume Exposure" Emergency Planning Zone Figure 4.8 Seabrook Station "Ingestion Exposure" Emergency Planning Zone (County Designations) Page 1 SSREP Rev. 78

CONTENT PAGE 5.0 EMERGENCY CLASSIFICATION SYSTEM 1-5.1 5.1 Regulatory Context 1-5.1 5.2 Definitions Used in Developing EAL Methodology 1-5.2 5.3 Recognition Categories 1-5.3 5.4 Emergency Class Descriptions 1-5.5 5.5 Emergency Class Thresholds 1-5.7 5.6 Emergency Action Levels 1-5.8 5.7 Treatment of Multiple Events and Emergency Class Upgrading 1-5.9 5.8 Emergency Class Downgrading 1-5.10 5.9 Classifying Transient Events 1-5.10 5.10 Cold Shutdown/Refueling IC/EALs 1-5.11 5.11 ISFSI IC/EALs 1-5.11 Figure 5.6 Emergency Initiating Condition Matrix - Modes 1, 2, 3 and 4 Figure 5.7 Emergency Initiating Condition Matrix - Modes 5, 6 and Defueled Figure 5.8 Fission Product Barrier Degradation Matrix - Modes 1, 2, 3 and 4 6.0 EMERGENCY FACILITIES AND EQUIPMENT 1-6.1 6.1 Emergency Centers 1-6.1 6.1.1 Technical Support Center 1-6.1 6.1.2 Operational Support Center 1-6.1 6.1.3 Emergency Operations Facility 1-6.2 6.1.4 Support for Radiological Analysis of Environmental Samples 1-6.3 6.1.5 Joint Information Center 1-6.3 6.1.6 Federal Radiological Monitoring and Assessment Center 1-6.3 6.2 Assessment Capability 1-6.4 6.2.1 Process Monitors 1-6.4 6.2.2 Radiation Data Management System 1-6.4 6.2.3 Geophysical Phenomena Monitors 1-6.5 6.2.4 Fire Detection Systems 1-6.6 6.2.5 Facilities and Equipment for Offsite Monitoring 1-6.6 Figure 6.1 Location of Emergency Operation Centers Around the Seabrook Station Site Figure 6.2 Relative Location of Technical Support within the 75' Elevation Level of the Control Building Page 2 SSREP Rev. 78

CONTENT PAGE Figure 6.5 Operational Support Center Layout Figure 6.6 EOF Layout 7.0 COMMUNICATIONS 1-7.1 7.1 Nuclear Alert System 1-7.1 7.2 NRC Communications Channels 1-7.1 7.3 Telephone System 1-7.2 7.4 Commercial Pager Service 1-7.2 7.5 Station Radio System 1-7.2 7.5.1 Offsite Monitoring Team Radio Network 1-7.2 7.5.2 UHF Radio System 1-7.3 7.6 Station Paging System 1-7.4 7.7 Sound-Powered Telephone System 1-7.4 Figure 7.1 Emergency Notification Figure 7.2 Coordination Channels with States Figure 7.3 Offsite Monitoring Team Radio Communications Figure 7.4 Telephone Communication Systems Overview Figure 7.5 UHF Radio Communication Systems Overview 8.0 ORGANIZATION 1-8.1 8.1 Introduction 1-8.1 8.2 Emergency Response Organization 1-8.1 8.2.1 On-Shift Emergency Response Organization 1-8.1 8.2.2 Augmented Emergency Response Organization 1-8.2 8.3 Emergency Public Information Organization 1-8.3 8.4 Seabrook Station Corporate Support 1-8.3 8.5 Recovery Organization 1-8.4 8.6 Extensions of Seabrook Station Emergency Response Organization 1-8.4 8.6.1 Local Services 1-8.4 8.6.2 Federal Government Support 1-8.5 8.6.3 Private Organization Support 1-8.5 8.7 Coordination with State Government Authorities 1-8.5 Page 3 SSREP Rev. 78

CONTENT PAGE Figure 8.1 On-Shift Emergency Response Organization Figure 8.2 Augmented Emergency Response Organization for Unusual Event Figure 8.3 Augmented Emergency Response Organization for Alert, Site Area Emergency, and General Emergency Figure 8.4 Emergency Operations Facility Staff Figure 8.5 Operational Support Center Staff Figure 8.6 Technical Support Center (TSC) Staff Figure 8.7 Canceled Figure 8.9 Joint Information Center Staff Figure 8.12 On-Shift Emergency Response Organization Actions Figure 8.13 Summary of the Radiological Emergency Responsibilities and Functions of the Massachusetts State Authorities Figure 8.14 Summary of the Radiological Emergency Responsibilities and Functions of the New Hampshire State Authorities Figure 8.15 Comparison of NUREG-0654 Emergency Response Staffing Goals with the Seabrook Station Emergency Response Organization (ERO) Figure 8.16 Seabrook Station News Services Staff 9.0 EMERGENCY RESPONSE OUTLINE 1-9.1 9.1 Initiation 1-9.1 9.2 Activation of the Emergency Organization 1-9.1 9.2.1 Unusual Event Response 1-9.1 9.2.2 Alert Response 1-9.2 9.2.3 Site Area Emergency Response 1-9.4 9.2.4 General Emergency Response 1-9.5 9.3 Emergency De-escalation, Termination and Recovery 1-9.5 Figure 9.1 Method of Notification and Reporting Instructions for Onsite Personnel 10.0 EMERGENCY MEASURES 1-10.1 10.1 Radiological Accident Assessment Systems and Techniques 1-10.1 10.1.1 Estimation of Offsite Dose Rates 1-10.2 10.1.2 Evaluation of Field Environmental Samples 1-10.3 10.1.3 Evaluation of Post Accident Samples 1-10.4 10.1.4 Severe Accident Management Guidance 1-10.4 10.2 Protective Action Recommendation Criteria 1-10.4 10.3 Radiological Exposure Control 1-10.5 10.4 Protective Measures 1-10.6 10.4.1 Personnel Accountability 1-10.6 10.4.2 Station Access/Egress Control Methods 1-10.6 Page 4 SSREP Rev. 78

CONTENT PAGE 10.4.3 Protective Measures for Hostile Action Based Events 1-10.7 10.4.4 Decontamination Capability 1-10.8 10.4.5 Use of Onsite Protective Equipment and Supplies 1-10.8 10.4.6 Radiation Guideline Action Levels 1-10.8 10.5 Aid to Affected Personnel 1-10.9 10.5.1 Medical Treatment 1-10.9 10.5.2 Medical Transportation 1-10.9 Table 10.1 EPA Protective Action Guidelines 1-10.10 Table 10.2 Emergency Dose Limits 1-10.11 Table 10.3 Emergency Center Protection 1-10.12 Figure 10.1 Emergency Center Protection Figure 10.2 Seabrook Station Evacuation Routes 11.0 EMERGENCY NOTIFICATION AND PUBLIC INFORMATION 1-11.1 11.1 Emergency Notification 1-11.1 11.2 Public Notification 1-11.1 11.3 Public Information 1-11.1 12.0 MAINTAINING EMERGENCY PREPAREDNESS 1-12.1 12.1 Drills and Exercises 1-12.1 12.1.1 Radiological Emergency Plan Exercises 1-12.1 12.1.2 Emergency Plan Drills 1-12.1 12.1.3 Drill and Exercise Scenarios 1-12.3 12.1.4 Evaluation of Exercises 1-12.4 12.1.5 Credit for Response to an Actual Emergency 1-12.4 12.2 Emergency Plan Training 1-12.5 12.2.1 Emergency Response Organization (ERO) 1-12.5 12.2.2 Support Groups 1-12.6 12.2.3 Station Personnel with No ERO Assignment 1-12.6 12.2.4 Emergency Preparedness Department Personnel 1-12.6 12.2.5 Records 1-12.6 12.3 Review and Updating of Plan and Procedures 1-12.7 12.4 Maintenance and Inventory of Emergency Equipment and Supplies 1-12.7 12.5 Emergency Preparedness Manager 1-12.7 12.6 Technical Training Supervisor 1-12.8 12.7 Operations Support Manager 1-12.8 Page 5 SSREP Rev. 78

CONTENT PAGE 13.0

SUMMARY

OF CHANGES 1-13.1 APPENDICES Appendix A Emergency Response Organization Position Definitions A-1 Appendix B Canceled B-1 Appendix C Evacuation Time Estimates C-1 Appendix D Letters of Agreement with Emergency Response Organizations D-1 Appendix E Seabrook Station Public Alert and Notification System E-1 Appendix F Emergency Equipment F-1 Appendix G Seabrook Station Supporting Emergency Plans and Procedures Listing G-1 Appendix H NUREG-0654/Seabrook Station Radiological Emergency Plan Cross Reference H-1 Page 6 SSREP Rev. 78

LIST OF EFFECTIVE PAGES PAGE REV. PAGE REV. Cover 78 Figure 8.7 Canceled Figure 8.9 66 TOC 1 - 6 78 Figure 8.12 50 Figure 8.13 13 LOEP 1 - 2 78 Figure 8.14 52 1-1.1 and 1-1.2 56 Figure 8.15 Sheet 1 55 1-2.1 thru 1-2.4 74 Sheet 2 55 Sheet 3 55 1-3.1 thru 1-3.4 66 Sheet 4 55 Figure 3.1 64 Sheet 5 55 Figure 3.2 55 Sheet 6 55 Figure 8.16 33 1-4.1 thru 1-4.5 66 Figure 4.1 56 1-9.1 thru 1-9.7 68 Figure 4.2 20 Figure 9.1 68 Figure 4.3 58 Figure 4.4 66 1-10.1 thru 1-10.12 73 Figure 4.6 66 Figure 10.1 30 Figure 4.7 5 Figure 10.2 48 Figure 4.8 Undated 1-11.1 thru 1-11.3 67 1-5.1 thru 1-5.12 71 Figure 5.6 57 1-12.1 thru 1-12.8 74 Figure 5.7 57 1-13.1 thru 13.2 77 Figure 5.8 57 Appendix A 1-6.1 thru 1-6.7 73 Cover Page 67 Figure 6.1 57 Index 67 Figure 6.2 42 A-1 thru A-24 67 Figure 6.5 47 Figure 6.6 64 Appendix B cancellation sheet 42 1-7.1 thru 1-7.4 65 Appendix C Figure 7.1 64 Cover Page 49 Figure 7.2 64 C-1 thru C-5 49 Figure 7.3 64 Figure 7.4 64 Appendix D Figure 7.5 64 Cover Page 64 Table of Contents 64 1-8.1 thru 1-8.6 72 D-1 58 Figure 8.1 70 D-1a 58 Figure 8.2 61 D-1b 58 Figure 8.3 60 D-2 63 Figure 8.4 68 D-3 thru D-3b 47 Figure 8.5 60 D-4 61 Figure 8.6 60 D-5 thru D-5c 57 Page 1 SSREP Rev. 78

LIST OF EFFECTIVE PAGES PAGE REV. PAGE REV. D-6 61 D-7 59 D-8 thru D-8e 59 D-9 thru D-9b 60 D-10 64 Appendix E Cover Page 58 E-1 thru E-5 58 Appendix F 33 Appendix G G-1 thru G-7 56 Appendix H Cover Page 47 H-1 thru H-7 47 Page 2 SSREP Rev. 78

1.0 INTRODUCTION

The Seabrook Station Radiological Emergency Plan (SSREP) was developed in accordance with the requirements of paragraphs 50.47(b) and Appendix E to Title 10 of the Code of Federal Regulations Part 50, "Licensing of Production and Utilization Facilities." In addition, Paragraph 50.47 of 10 CFR 50 specifies that the Operating License award depends on a finding by the Nuclear Regulatory Commission as to the adequacy of both onsite and offsite emergency preparedness. To meet this requirement, the SSREP has been formulated to address planning elements which have been specified by the Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) in NUREG-0654/FEMA-REP-1, Rev. 1. Exceptions to this planning guidance are documented in the Emergency Preparedness Planning Basis Document. The purpose of this document is to provide a reference and guidance source which:

1. Outlines the Seabrook Station Emergency Response Organization (ERO), and specifies the interfaces between and among ERO activities, and State, local, Federal and private sector organizations;

2. Assures a standard emergency classification and action level scheme which activates emergency response functions dependent upon the severity of the accident;

3. Specifies the method of notification to the offsite emergency response organizations;

4. Summarizes ERO emergency response facilities and equipment;

5. Assures that provisions exist for communications among principal response organizations;

6. Defines the Station's capability for assessing and monitoring actual or potential offsite radiological consequences of an emergency condition; and

7. Assures that periodic training programs, exercises and drills will be conducted in order to maintain a high level of emergency preparedness at Seabrook Station.

In support of this document, emergency operating procedures will assist the Station operating staff in recognizing an emergency condition and will prescribe immediate response actions necessary to correct the condition. The emergency conditions that trigger the use of emergency operating procedures also trigger the use of an emergency classification procedure. The emergency classification procedure initiates activation of this plan in accordance with a prescribed set of emergency response procedures. The emergency implementing procedures will govern the actions undertaken by the ERO. The SSREP and associated procedures are part of the overall emergency planning and preparedness program related to Seabrook Station. New Hampshire and Massachusetts State agencies and local civil authorities within the plume emergency planning zone (i.e., approximately a 10-mile radius) have cooperated in establishing plans and procedures for the alerting and protection of the general public in the event of a radiological emergency at Seabrook Station. 1-1.1 SSREP Rev. 56

In addition, the support and capabilities of all appropriate Federal agencies would be made available to the Station, and State and local governments as specified in the National Response Framework, Nuclear/Radiological Incident Annex. Additional technical support and services can be acquired through emergency plan arrangements with industry organizations such as the Westinghouse Energy System Business Unit Emergency Response Team and the Institute of Nuclear Power Operations. 1-1.2 SSREP Rev. 56

2.0 DEFINITIONS Alert - Events are in process or have occurred which involve an actual or potential substantial degradation in the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. Alternative Operational Support Center - An area within the EOF where OSC personnel assemble for hostile action based events or other catastrophic events that prevent site access. Alternative Technical Support Center - An area within the EOF where TSC personnel assemble for hostile action based events or other catastrophic events that prevent site access. Assembly Area - The Assembly Area for backup response personnel and maintenance technicians is located in the Seabrook Station Conference Center at the rear of Warehouse #1. This facility would be activated only during the period from 0700 to 1630, Monday through Friday, except during planned outages when it would be opened on any shift. Activation is required at an Alert or higher emergency classification level. Assessment Actions - Actions which are taken to effectively define the emergency situation necessary for decisions on specific emergency measures. Automated Telephone Notification Service - A commercial, computer-based call-out service used to notify Primary, Subject-to- Call and Secondary Responders during back-shifts, weekends and holidays of an Alert or higher emergency classification. Backup Responders - Personnel who do not initially staff an emergency response facility but are available for subsequent staffing duties (e.g., second shift). During a daytime plan activation, these personnel report to the Assembly Area. Committed Dose Equivalent (CDE) - The dose equivalent to an organ from an intake of radioactive material during the 50 year period following the intake. Committed Effective Dose Equivalent (CEDE) - The sum of the products of the weighting factors applicable to each of the body organs that are irradiated and the CDE to these organs. Corrective Actions - Emergency measures taken to ameliorate or terminate an emergency situation. Deep Dose Equivalent (DDE) - The external dose equivalent to the whole body at a tissue depth of 1 cm. Dose - A general term referring to the quantity of absorbed energy in tissue. In the SSREP, dose is used for irradiation of the whole body, unless otherwise indicated. Dose Equivalent (DE) - The product of absorbed dose in tissue and the quality factor. Emergency Action Level (EAL) - A pre-determined, site-specific, observable threshold for an Initiating Condition that places the Station in a given emergency class. 1-2.1 SSREP Rev. 74

Emergency Classifications - One of a minimum set of names or titles, established by the Nuclear Regulatory Commission (NRC), for grouping off-normal nuclear power plant conditions according to (1) their relative radiological seriousness, and (2) the time-sensitive onsite and off-site radiological emergency preparedness actions necessary to respond to such conditions. The radiological emergency classes, in ascending order of seriousness, are as follows:

• Unusual Event
• Alert
• Site Area Emergency
• General Emergency Emergency Operating Centers (EOCs) - Areas designated by the State and local authorities as Emergency Plan facilities for their respective staffs.

Emergency Operating Procedures - The outline of specific corrective actions to be taken by Station operators in response to abnormal operating conditions. Emergency Operations Facility (EOF) - A center established beyond ten miles from the Seabrook Station site where Seabrook Station emergency management directs the actions of the emergency response organization, coordinates the evaluation of offsite radiological conditions with offsite authorities, arrives at protective action recommendations, and establishes a recovery organization. Emergency Planning Zones (EPZ) - The areas for which planning is recommended to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The two zones are the plume exposure pathway zone (about 10 miles in radius) and the ingestion exposure pathway zone (about 50 miles in radius). Emergency Response Organization (ERO) - The Seabrook Station personnel assigned and trained to implement this emergency plan. Emergency Response Procedures - Procedures that outline specific actions to be taken by the Seabrook Station ERO to activate and implement this emergency plan. These procedures are contained in the Station Emergency Response Manual (SSER). GEL Laboratories - A contracted service for emergency environmental sample analysis. General Emergency - Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. 1-2.2 SSREP Rev. 74

HOSTILE ACTION - An act toward a nuclear power plant or its personnel that includes the use of violent force to destroy equipment, take hostages, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included. HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the nuclear power plant. Non-terrorism-based EALs should be used to address such activities (e.g., violent acts between individuals in the owner controlled area). HOSTILE FORCE - One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction. Ingestion Exposure Pathway - The pathway in which individuals receive a radiation dose due to internal deposition of radioactive materials from ingestion of contaminated water, foods, or milk. Initiating Condition - One of a predetermined subset of nuclear power plant conditions where either the potential exists for a radiological emergency or such an emergency has occurred. Joint Information Center (JIC) - A facility where news media representatives can obtain emergency news information. NextEra Energy Seabrook, LLC- Managing agent of Seabrook Station. Non-essential Personnel - Onsite personnel who are not assigned to the Seabrook Station ERO. These personnel are evacuated from the site at an Alert or higher emergency classification. Operational Support Center - An emergency center established for the assembly and dispatch of available skilled emergency personnel (e.g., additional Station operations and support personnel) in support of onsite emergency operations. Plume Exposure Pathway - The pathway in which individuals receive a radiation dose due to (a) whole body external exposure due to gamma radiation from the plume and from deposited material, and (b) inhalation exposure from the passing radioactive plume. Primary Responders - The eight ERO positions that are staffed on a rotating duty basis. These positions are notified by pager, respond to any emergency, and include the Site Emergency Director, Operations Technician, Technical Services Coordinator, Health Physics Coordinator, Response Manager, EOF Coordinator, ERO Technical Liaison and Emergency News Manager. Primary Responders are also notified by the automated telephone notification service during back-shifts, weekends and holidays of an Alert or higher emergency classification level. Projected Dose - The amount of radiation dose estimated at the onset of the accident. It includes all the dose an individual would receive for the duration of the accident assuming no protective measures were undertaken. Protective Actions - Emergency measures to be taken by the public to mitigate the consequences of an accident by minimizing the radiological doses that may occur if such actions were not undertaken. Protective actions would be warranted provided the reduction in the individual dose is not offset by excessive risks to individual safety in implementing such actions. 1-2.3 SSREP Rev. 74

Protective Action Guides (PAG) - Pre-established radiological dose values to the public which warrant protective actions following an uncontrolled release of radioactive material. Recovery Actions - Actions taken once the emergency condition has been controlled in order to restore stable Station conditions. Remote Monitoring and Decontamination Area - This area is located onsite. It will be activated in the event that a radiological release occurs prior to the evacuation of site personnel, and that the prevailing wind conditions at the time make it possible for site evacuees to be contaminated. Secondary Responders - ERO positions that are not staffed on a rotating duty basis. These positions are activated at an Alert or higher emergency classification. Secondary responders are notified by pager and, during back-shifts, weekends and holidays, by the automated telephone notification service of an Alert or higher emergency classification level. Site - Seabrook Station property situated on a 900-acre tract of land on the western shore of Hampton Harbor in Rockingham County. Site Area Emergency -Events are in process or have occurred that involve actual or likely major failures in plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevent effective access to , equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed the EPA Protective Action Guideline exposure levels beyond the site boundary. Station Emergency Response Manual (SSER) - The manual containing all Emergency Response Procedures. Subject-to-Call Responders - ERO positions that are not staffed on a rotating basis. Subject-to-Call Responders are expected to report on an all-call basis to activate emergency facilities at an Alert or higher emergency classification level. Subject-to-Call Responders are notified by pager and, during back-shifts, weekends and holidays, by the automated telephone notification service of an Alert or higher emergency classification level. Technical Support Center (TSC) - An in-station emergency center established in close proximity to the Control Room that has the capability to acquire parameters for post-accident evaluation by technical and recovery assistance personnel. Onsite emergency response activities are directed from the TSC. Total Effective Dose Equivalent (TEDE) - The sum of the deep dose equivalent (DDE) for external exposures and the committed effective dose equivalent (CEDE) for internal exposures. Unusual Event -Events are in process or have occurred which indicate a potential degradation in the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. 1-2.4 SSREP Rev. 74

3.0 RADIOLOGICAL EMERGENCY PLAN

SUMMARY

3.1 Introduction The Seabrook Station Radiological Emergency Plan (SSREP) has been developed to ensure the safety of Station staff and the public in the event of degraded or failed Station safety systems. The SSREP identifies the emergency response organization, the planned actions of that organization, and the coordination of activities with local, state and federal agencies. The Station Emergency Response Manual contains emergency response procedures that implement the responsibilities and actions described in the SSREP. 3.2 Station Emergency Response Once a potential emergency condition has been identified, the Unit Supervisor notifies the Shift Manager. The Shift Manager categorizes the emergency condition into one of four emergency classifications by use of the emergency classification procedure. Once an emergency has been declared, the Shift Manager assumes the role of Short Term Emergency Director (STED). The STED is responsible for directing activation and notification of the emergency response organization (ERO). The extent of organization and facility activation varies with the severity and classification of the emergency. The STED will insure that an emergency classification announcement is made over the Station public address system and that Primary Responders are notified via a pager system. The STED will ensure that notifications to New Hampshire and Massachusetts state authorities are initiated within 15 minutes of the emergency declaration. Notification arrangements are shown in Figure 3.1. During an Unusual Event, the Primary Responders will be notified by pager. Pager notification will be either a text message or numeric code. Primary Responders are the Site Emergency Director, Operations Technician, Technical Services Coordinator, Health Physics Coordinator, Response Manager, EOF Coordinator, ERO Technical Liaison and Emergency News Manager. (Protected: Ref. NRC Inspection Report 50-443/98-03) Activation of any emergency response facility at this level is at the discretion of the STED or Site Emergency Director. Following an Alert or higher emergency declaration, Primary, Subject-to-Call and Secondary Responders will be notified by pager, and all emergency response facilities will be activated. Pager notification will be either a text message or numeric code. In certain cases, the pager notification will be forwarded to cellular telephones as authorized by Seabrook Station for station issued cell phones or individual ERO members for personal cell phones. ERO personnel who are onsite at the time of emergency declaration may also be notified by plant announcement, activation of the site siren, the LAN emergency messaging system or by word of mouth. If an Alert or higher emergency is declared during a backshift, weekend or holiday, Primary, Subject-to-Call and Secondary Responders will be notified by the automated telephone notification service in addition to the pager system. 1-3.1 SSREP Rev. 66

The Technical Support Center (TSC) will be staffed by personnel needed to provide operational and engineering support to control room personnel. The Operational Support Center (OSC) is the location from which support personnel such as maintenance, health physics, operations, chemistry, instrumentation and control, and radwaste operations are dispatched to implement actions directed by the TSC. Alternative TSC and OSC facilities are located within the EOF. TSC and OSC personnel report there for hostile action based events or other catastrophic events that prevent site access. The Emergency Operations Facility (EOF) serves as the location where offsite consequences of the accident are assessed. At the EOF, dose projections will be made, field monitoring teams will be dispatched, and protective action recommendations made to state authorities. This location also serves as the headquarters for the recovery organization. The Joint Information Center serves as the facility where joint utility, state and federal press briefings will be coordinated and held to assure timely and complete accident information is made available to the public via the news media. The following response arrangements apply only in the event that an Alert or higher emergency is declared during an outage, i.e., the Station is in Modes 5 or 6. The goal is to keep key outage personnel readily available to return inoperable systems to service if the availability of those systems would lessen or terminate the emergency conditions.

1. Due to their outage assignments, some Seabrook Station personnel may not be readily available to report for their respective Emergency Response Organization (ERO) assignments. Depending upon which is more effective, these individuals may be directed to respond to the emergency in either their ERO role or outage assignment role.

2. Provided he or she has the necessary ERO qualifications, the on-duty Outage Control Center (OCC) Manager will assume the position of Site Emergency Director.

3. All non-ERO personnel with outage assignments, including outage workers who are not Seabrook Station employees, will assemble in the Seabrook Station Conference Center.

4. The onshift Outage Coordinator will confer with the Technical Services Coordinator concerning the status of outage-related work and what jobs, if any, will be resumed. The Outage Coordinator will continue to interface primarily with the Technical Services Coordinator.

5. The onshift Outage Coordinator will dispatch an outage management representative to the Seabrook Station Conference Center. This individual will ensure that an accountability listing is generated for the assembled personnel. Personnel needed to resume outage-related work will be directed to proceed to the OSC (or the work scene) and all others to evacuate the site.

6. Following emergency termination or declaration of Recovery, the OCC Manager will coordinate with the Site Emergency Director (if not the OCC Manager) and the Response Manager to determine the ways to communicate return-to-work instructions to outage workers (e.g., press release, vendor site managers, etc.).

1-3.2 SSREP Rev. 66

In the event an emergency classification is declared based on a security event, actions will be taken per other station procedures maintained in compliance with NRC security orders. These actions may deviate from actions prescribed for radiological emergencies that are not related to security events in order to protect the health and safety of station personnel and the public. Deviations for security related events may affect the call-out of emergency response personnel, method of offsite notifications, timing and extent of emergency facility activation, directions provided to station personnel, conduct of personnel accountability, and responses of federal, state and local support organizations. As warranted by emergency conditions and by agreement with offsite authorities, a recovery organization will be established to conduct recovery operations. Reentry into offsite areas which had been subject to radiological effects will be coordinated between the recovery organization and offsite authorities. Public information releases regarding reentry will also be coordinated. 3.3 Local and State Government Responses The SSREP is designed to interface with the state emergency response plans and implementing procedures of Massachusetts and New Hampshire. Local governments, in coordination with the emergency management agencies of these states, have plans which, should the need arise, contain instructions to carry out specific protective measures, dependent upon various emergency conditions. Seabrook Station is responsible for determining and conveying specific accident information, dose assessment information and protective action recommendations to the State of New Hampshire and Commonwealth of Massachusetts. It is the responsibility the States to evaluate this information, and then determine and implement appropriate protective actions in accordance with their plans and procedures. The local governments will provide the resources needed to implement these actions. Should local resources be exhausted or additional resources needed to accomplish actions in a timely manner, state governments will provide any additional support needed. 3.4 Federal Government Response Once notified of an emergency, the NRC will evaluate the situation and determine the appropriate NRC response. Depending on the severity of the accident, the NRC will activate all or part of the federal emergency response organization in accordance with the National Response Framework, Nuclear/Radiological Incident Annex (NRF). The NRF makes available the resources and capabilities of numerous federal agencies. Principal participants will be the NRC, Department of Energy, Environmental Protection Agency and Department of Homeland Security. Should the federal agencies respond to the site vicinity, they will establish a Federal Radiological Monitoring and Assessment Center to monitor and assess the radiological consequences and a Federal Response Center to coordinate the federal support provided during the emergency. Expected Time of Arrival of the NRC Region I response would be approximately 6 hours. Expected federal resources are specified in NUREG-0728, NRC Incident Response Plan. NRC Region 1 will deploy resources in accordance with the response modes described in NUREG-0728. 1-3.3 SSREP Rev. 66

Space is designated for the NRC in the Emergency Operations Facility (EOF) in Portsmouth, NH. FTS-2001 communications links are installed for NRC use in the Technical Support Center and the EOF (see Section 7.2). Four airfields are within a one-hour drive of Seabrook Station and the EOF: Logan Airport, Boston, MA; Manchester-Boston Regional Airport, Manchester, NH; Portland Jetport, Portland, ME; and Pease International Tradeport, Portsmouth, NH. 1-3.4 SSREP Rev. 66

4.0 THE AREA 4.1 The Site Seabrook Station is situated on a 900 acre tract of land on the western shore of Hampton Harbor in Rockingham County, near the northern boundary of the Town of Seabrook, New Hampshire. The site is located approximately eight miles southeast of the Exeter, New Hampshire, five miles northeast of Amesbury, Massachusetts, and two miles west of the Hampton Harbor Inlet. The site is bordered on the east by an extensive saltwater marsh and is located on a point of land called "the Rocks," between two small tidal estuaries; the Brown's River and the Hunt's Island Creek. The City of Portsmouth is located approximately eleven miles north of the site while the Boston, Massachusetts metropolitan area is located approximately forty miles south-southwest of the site. Seabrook Station consists of a four-loop pressurized water reactor. The Station exclusion area can generally be described as a circle of 3000 foot radius, as shown in Figure 4.1, Site Boundaries. All the area within the site boundary is controlled by NextEra Energy Seabrook, LLC. 4.2 Area Characteristics, Land Use and Demography 4.2.1 Area Characteristics Figure 4.2, Major Routes in 10 Mile Study, shows the major transportation arteries within 10 miles of the site. The location and orientation of principal structures within the site are shown on Figure 4.3, Station Layout. The control of traffic in case of an emergency on those portions of the Brown's River and Hunt's Island Creek that fall within the site boundary comes under the authority of the State of New Hampshire. A seasonal, overnight and daily transient population during the summer period is associated with the beaches and other recreational facilities in the vicinity of the Seabrook Station. The coastal beaches within 10 miles of Seabrook Station extend from Plum Island beach in Newbury, Massachusetts to Wallis Sands Beach in Rye, New Hampshire. Table 4.1, Summary of Peak Population Estimates of Communities within 0 to 10 Miles of the Site, summarizes peak transient population estimates within 0 to 10 miles of the site. Information on the location of major medical related facilities, including hospitals and nursing homes, has been compiled for the area within 10 miles of Seabrook Station. Supporting documents to the Massachusetts and New Hampshire Radiological Emergency Response Plans contain listings and populations of medical-related facilities within the Seabrook Station EPZ. The Pow Wow River State Forest occupies approximately 48 acres in the town of South Hampton, NH, approximately seven miles west of the site. The Parker River National Wildlife Refuge is located in the town of Newbury, Massachusetts, approximately nine miles south of the site, and has a total area of 6,403 acres. 1-4.1 SSREP Rev. 66

4.2.2 Uses of Adjacent Lands and Waters The Seabrook Station site is bordered on the north, east and south by marsh land extending to estuaries, streams and Hampton Harbor. The land to the west is characterized as a mix of residential, commercial, industrial and agricultural. Approximately 1.5 percent of the Town of Seabrook is designated as industrial. Water uses in the area of the plant site are mainly recreational, including the beaches in Salisbury, Seabrook, Hampton, and North Hampton, and boat docks in Hampton Harbor. Boating activity on the Hampton and Black Water Rivers, within a 2-mile radius of Seabrook Station, is concentrated within their lower stretches, in the Hampton Harbor area. Boating activity in the Atlantic Ocean is largely concentrated within two or three miles of Hampton Harbor inlet. Provisions with the U.S. Coast Guard are made by State of New Hampshire authorities to alert and control boating traffic in this area in the event of a radiological emergency at Seabrook Station. 4.2.3 Population Distribution Data from numerous sources were used in developing distributions and projections of permanent resident and transient populations within 10 miles of the Seabrook Station site. This area includes portions of New Hampshire and Massachusetts. The resident population distribution is shown in Figure 4.4, Resident Population Distribution within a 0 - 10 Mile Radius of Seabrook Station. During the summer period, a transient population is associated with the beaches and other recreational facilities in the vicinity of Seabrook Station. Figure 4.6 represents an estimate of the peak transient population during summer months within a 0-10 mile radius of Seabrook Station. 4.3 Emergency Planning Zones In accordance with the requirements specified in 10 CFR 50.33(g), emergency planning zones have been selected based upon the knowledge of the potential consequences, timing and release characteristics of a spectrum of accidents, including core melt scenarios, regardless of their extremely low probability of occurrence. As a result, an emergency planning zone concept was developed, both for the short-term plume exposure and for the longer-term ingestion exposure pathways. Emergency Planning Zones (EPZs) are defined as the areas for which planning is needed to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The choice of the size of the Emergency Planning Zones represents a judgement on the extent of detailed planning which should be performed to assure an adequate response. Dependent upon the severity of the accident, protective actions will generally be limited to only portions of the designated EPZs, but should the need arise, actions can be undertaken for the entire zone. In accordance with the recommended planning bases, two EPZs have been defined. The plume exposure pathway EPZ, shown in Figure 4.7, is an area designated by the jurisdictional boundaries of those communities which are within a radial distance of about 10 miles from the Station site. Table 4.4 lists communities in each state that are within the plume exposure pathway EPZ. The size of the zone is based primarily on the following considerations: 1-4.2 SSREP Rev. 66

1. that the projected doses estimated for most accidents would not exceed plume exposure protective action guide (PAG) levels outside the zone;

2. that detailed planning within this area would provide a substantial base for expansion of response efforts in the unlikely event that this proved necessary; and

3. that planning within this area recognizes all the jurisdictional restraints imposed by the zone designation.

The ingestion exposure pathway EPZ, shown in Figure 4.8, is an area extending radially outward from the Station site to a distance of about 50 miles. The size of the zone is based primarily on the consideration that the downwind range within which significant contamination could occur would generally be limited to this distance because of wind shifts and travel periods. In addition, projected doses from contamination outside this zone would not exceed ingestion exposure pathway Protective Action Guide levels. Precautionary control measures relative to livestock feeds, milk products, garden produce and potable water supplies will be implemented in this area to the extent dictated by the release conditions. The State of New Hampshire will notify the State of Maine to coordinate ingestion exposure pathway emergency response actions. 1-4.3 SSREP Rev. 66

Table 4.1 Summary of Peak Population Estimates of Communities within 0 to 10 Miles of the Site Communities Summer Weekend Amesbury 19,464 Brentwood 5,634 East Kingston 2,351 Exeter 21,084 Greenland 4,480 Hampton 27,229 Hampton Falls 3,401 Kensington 2,156 Kingston 6,844 Merrimac 6,361 New Castle 1,794 Newbury 6,908 Newburyport 19,428 Newfields 2,114 Newton 4,742 North Hampton 6,294 Portsmouth 40,777 Rye 7,313 Salisbury 14,498 Seabrook 13,806 South Hampton 1,610 Stratham 8,780 West Newbury 4,235 NOTE Figures are derived from 2010 United States Census data. These figures are subject to update as part of the continuous planning process. 1-4.4 SSREP Rev. 66

Table 4.4 Communities within the Seabrook Station Plume Exposure Pathway Emergency Planning Zone Communities Involved Affected by Winds Blowing from Brentwood, NH ESE East Kingston, NH E-ESE Exeter, NH SE Greenland, NH S Hampton, NH SW-SSE Hampton Falls, NH ESE-SE Hampton Beach, NH W-WNW Kensington, NH ESE-E Kingston, NH ESE-E Newfields, NH SSE-SE New Castle, NH SSW Newton, NH E-ENE North Hampton, NH S-SSW Portsmouth, NH SSW Rye, NH SSW Seabrook, NH NNW-E South Hampton, NH E-ENE Stratham, NH SSE-S Amesbury, MA ENE-NE Merrimac, MA ENE Newbury, MA NNE-NNW Newburyport, MA N-NNE Salisbury, MA ENE-NNW West Newbury, MA NNE-NE 1-4.5 SSREP Rev. 66

5.0 EMERGENCY CLASSIFICATION SYSTEM Seabrook Station uses NEI 99-01, Revision 6, as the basis for the emergency classification system. The information in this chapter is derived from generic basis discussion presented in NEI 99-01, Revision 6. 5.1 Regulatory Context Title 10, Code of Federal Regulations, Part 50 provides the regulations that govern emergency preparedness at nuclear power plants. Nuclear power reactor licensees are required to have NRC-approved "emergency response plans" for dealing with "radiological emergencies." The requirements call for both onsite and offsite emergency response plans, with the offsite plans being those approved by FEMA and used by the State and local authorities. This section deals with the utilities' approved onsite plans and procedures for response to radiological emergencies at nuclear power plants, and the links they provide to the offsite plans. Section 50.47 of Title 10 of the Code of Federal Regulations (10 CFR 50.47), entitled "Emergency Plans," states the requirement for such plans. Part (a)(1) of this regulation states that "no operating license will be issued unless a finding is made by NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency." The major portion of 10 CFR 50.47 lists "standards" that emergency response plans must meet. The standards constitute a detailed list of items to be addressed in the plans. Of particular importance to this project is the fourth standard, which addresses "emergency classification" and "action levels." These terms, however, are not defined in the regulation. 10 CFR 50.54, "Conditions of licenses," emphasizes that power reactor licensees must "follow, and maintain in effect, emergency plans which meet the standards in Part 50.47(b) and the requirements in Appendix E to this part." The remainder of this part deals primarily with required implementation dates. 10 CFR 50.54(q) allows licensees to make changes to emergency plans without prior Commission approval only if: (a) the changes do not decrease the effectiveness of the plans and (b) the plans, as changed, continue to meet 10 CFR 50.47(b) standards and 10 CFR 50 Appendix E requirements. The licensee must keep a record of any such changes. Proposed changes that decrease the effectiveness of the approved emergency plans may not be implemented without application to and approval by the Commission. 10 CFR 50.72 deals with "Immediate notification requirements for operating nuclear power reactors." The "immediate" notification section actually includes three types of reports: (1) immediately after notification of State or local agencies (for emergency classification events); (2) one-hour reports; and, (3) four-hour reports. Although 10 CFR 50.72 contains significant detail, it does not define either "Emergency Class" or "Emergency Action Level." But one-hour and four-hour reports are listed as "non-emergency events," namely, those which are "not reported as a declaration of an Emergency Class." Certain 10 CFR 50.72 events can also meet the Unusual event emergency classification if they are precursors of more serious events. These situations also warrant anticipatory notification of state and local officials. (See Section 3.7, "Emergency Class Descriptions".) 1-5.1 SSREP Rev. 71

By footnote, the reader is directed from 10 CFR 50.72 to 10 CFR 50 Appendix E, for information concerning "Emergency Classes." 10 CFR 50.73 describes the "Licensee event report system," which requires submittal of follow-up written reports within sixty days of required notification of NRC. 10 CFR 50 Appendix E, Section B, "Assessment Actions," mandates that emergency plans must contain "emergency action levels." EALs are to be described for: (1) determining the need for notification and participation of various agencies, and (2) determining when and what type of protective measures should be considered. Appendix E continues by stating that the EALs are to be based on: (1) in-plant conditions; (2) in-plant instrumentation; (3) onsite monitoring; and (4) offsite monitoring. 10 CFR 50 Appendix E, Section C, "Activation of Emergency Organization," also addresses "emergency classes" and "emergency action levels." This section states that EALs are to be based on: (1) onsite radiation monitoring information; (2) offsite radiation monitoring information; and, (3) readings from a number of plant sensors that indicate a potential emergency, such as containment pressure and the response of the Emergency Core Cooling System. This section also states that "emergency classes" shall include: (1) Unusual events (UNUSUAL EVENTs), (2) Alert, (3) Site Area Emergency, and (4) General Emergency. These regulations are supplemented by various regulatory guidance documents. A significant document that has dealt specifically with EALs is NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," October 1980. 5.2 Definitions Used in Developing EAL Methodology The following definitions apply to the Seabrook Station EAL methodology: EMERGENCY CLASS: One of a minimum set of names or titles, established by the Nuclear Regulatory Commission (NRC), for grouping off-normal nuclear power plant conditions according to (1) their relative radiological seriousness, and (2) the time-sensitive onsite and off-site radiological emergency preparedness actions necessary to respond to such conditions. The existing radiological emergency classes, in ascending order of seriousness, are called: Unusual event Alert Site Area Emergency General Emergency INITIATING CONDITION (IC): One of a predetermined subset of nuclear power plant conditions where either the potential exists for a radiological emergency, or such an emergency has occurred. 1-5.2 SSREP Rev. 71

Discussion: In NUREG-0654, the NRC introduced, but does not define, the term "initiating condition." Since the term is commonly used in nuclear power plant emergency planning, the definition above has been developed and combines both regulatory intent and the greatest degree of common usage among utilities. Defined in this manner, an IC is an emergency condition which sets it apart from the broad class of conditions that may or may not have the potential to escalate into a radiological emergency. It can be a continuous, measurable function that is outside technical specifications, such as elevated RCS temperature or falling reactor coolant level (a symptom). It also encompasses occurrences such as FIRE (an event) or reactor coolant pipe failure (an event or a barrier breach). EMERGENCY ACTION LEVEL (EAL): A pre-determined, site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be: an instrument reading; an equipment status indicator; a measurable parameter (onsite or offsite); a discrete, observable event; results of analyses; entry into specific emergency operating procedures; or another phenomenon which, if it occurs, indicates entry into a particular emergency class. Discussion: The term "emergency action level" has been defined by example in the regulations, as noted in the above discussion concerning regulatory background. The term had not, however, been defined operationally in a manner to address all contingencies. There are times when an EAL will be a threshold point on a measurable continuous function, such as a primary system coolant leak that has exceeded technical specifications for a specific plant. 5.3 Recognition Categories ICs and EALs can be grouped in one of several schemes. This generic classification scheme incorporates symptom-based, event-based, and barrier-based ICs and EALs. The symptom-based category for ICs and EALs refers to those indicators that are measurable over some continuous spectrum, such as core temperature, coolant levels, containment pressure, etc. When one or more of these indicators begin to show off-normal readings, reactor operators are trained to identify the probable causes and potential consequences of these "symptoms" and take corrective action. The level of seriousness indicated by these symptoms depends on the degree to which they have exceeded technical specifications, the other symptoms or events that are occurring contemporaneously, and the capability of the licensed operators to gain control and bring the indicator back to safe levels. Event-based EALs and ICs refer to occurrences with potential safety significance, such as the failure of a high-pressure safety injection pump, a safety valve failure, or a loss of electric power to some part of the plant. The range of seriousness of these "events" is dependent on the location, number of contemporaneous events, remaining plant safety margin, etc. 1-5.3 SSREP Rev. 71

Barrier-based EALs and ICs refer to the level of challenge to principal barriers used to assure containment of radioactive materials contained within a nuclear power plant. For radioactive materials that are contained within the reactor core, these barriers are: fuel cladding, reactor coolant system pressure boundary, and containment. The level of challenge to these barriers encompasses the extent of damage (loss or potential loss) and the number of barriers concurrently under challenge. In reality, barrier-based EALs are a subset of symptom-based EALs that deal with symptoms indicating fission product barrier challenges. These barrier-based EALs are primarily derived from Emergency Operating Procedure (EOP) Critical Safety Function (CSF) Status Tree Monitoring (or their equivalent). Challenge to one or more barriers generally is initially identified through instrument readings and periodic sampling. Under present barrier-based EALs, deterioration of the reactor coolant system pressure boundary or the fuel clad barrier usually indicates an "Alert" condition, two barriers under challenge a Site Area Emergency, and loss of two barriers with the third barrier under challenge is a General Emergency. The fission product barrier matrix described in Category F is a hybrid approach that recognizes that some events may represent a challenge to more than one barrier, and that the containment barrier is weighted less than the reactor coolant system pressure boundary and the fuel clad barriers. Symptom-based ICs and EALs are most easily identified when the plant is in a normal startup, operating or hot shutdown mode of operation, with all of the barriers in place and the plant's instrumentation and emergency safeguards features fully operational as required by technical specifications. It is under these circumstances that the operations staff has the most direct information of the plant's systems, displayed in the main control room. As the plant moves through the decay heat removal process toward cold shutdown and refueling, barriers to fission products are reduced (i.e., reactor coolant system pressure boundary may be open) and fewer of the safety systems required for power operation are required to be fully operational. Under these plant operating modes, the identification of an IC in the plant's operating and safety systems becomes more event-based, as the instrumentation to detect symptoms of a developing problem may not be fully effective; and engineered safeguards systems, such as the Emergency Core Cooling System (ECCS), are partially disabled as permitted by the plant's Technical Specifications. Barrier-based ICs and EALs also are heavily dependent on the ability to monitor instruments that indicate the condition of plant operating and safety systems. Fuel cladding integrity and reactor coolant levels can be monitored through several indicators when the plant is in a normal operating mode, but this capability is much more limited when the plant is in a refueling mode, when many of these indicators are disconnected or off-scale. The need for this instrumentation is lessened, however, and alternate instrumentation is placed in service when the plant is shut down. It is important to note that in some operating modes there may not be definitive and unambiguous indicators of containment integrity available to control room personnel. For this reason, barrier-based EALs should not place undue reliance on assessments of containment integrity in all operating modes. Generally, Technical Specifications relax maintaining containment integrity requirements in modes 5 and 6 in order to provide flexibility in performance of specific tasks during shutdown conditions. Containment pressure and temperature indications may not increase if there is a pre-existing breach of containment integrity. At most plants, a large portion of the containment's exterior cannot be monitored for leakage by radiation monitors. 1-5.4 SSREP Rev. 71

Several categories of emergencies have no instrumentation to indicate a developing problem, or the event may be identified before any other indications are recognized. A reactor coolant pipe could break; FIRE alarms could sound; radioactive materials could be released; and any number of other events can occur that would place the plant in an emergency condition with little warning. For emergencies related to the reactor system and safety systems, the ICs shift to an event based scheme as the plant mode moves toward cold shutdown and refueling modes. For non-radiological events, such as FIRE, external floods, wind loads, etc., as described in NUREG-0654 Appendix 1, event-based ICs are the norm. In many cases, a combination of symptom-, event- and barrier-based ICs will be present as an emergency develops. In a loss of coolant accident (LOCA), for example: Coolant level is dropping; (symptom) There is a leak of some magnitude in the system (pipe break, safety valve stuck open) that exceeds plant capabilities to make up the loss; (barrier breach or event) Core (coolant) temperature is rising; (symptom) and At some level, fuel failure begins with indicators such as high coolant activity samples, etc. (barrier breach or symptom) 5.4 Emergency Class Descriptions There are three considerations related to emergency classes. These are: (1) The potential impact on radiological safety, either as now known or as can be reasonably projected; (2) How far the plant is beyond its predefined design, safety, and operating envelopes; and (3) Whether or not conditions that threaten health are expected to be confined to within the site boundary. The ICs deal explicitly with radiological safety impact by escalating from levels corresponding to releases within regulatory limits to releases beyond EPA Protective Action Guideline (PAG) plume exposure levels. In addition, the "Discussion" sections below include offsite dose consequence considerations which were not included in NUREG-0654 Appendix 1. UNUSUAL EVENT: Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. 1-5.5 SSREP Rev. 71

Discussion: Potential degradation of the level of safety of the plant is indicated primarily by exceeding plant technical specification Limiting Condition of Operation (LCO) allowable action statement time for achieving required mode change. Precursors of more serious events should also be included because precursors do represent a potential degradation in the level of safety of the plant. Minor releases of radioactive materials are included. In this emergency class, however, releases do not require monitoring or offsite response. ALERT: Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. Discussion: Rather than discussing the distinguishing features of "potential degradation" and "potential substantial degradation," a comparative approach would be to determine whether increased monitoring of plant functions is warranted at the Alert level as a result of safety system degradation. This addresses the operations staff's need for help, independent of whether an actual decrease in plant safety is determined. This increased monitoring can then be used to better determine the actual plant safety state, whether escalation to a higher emergency class is warranted, or whether de-escalation or termination of the emergency class declaration is warranted. Dose consequences from these events are small fractions of the EPA PAG plume exposure levels, i.e., about 10 mrem to 100 mrem TEDE. SITE AREA EMERGENCY: Events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary. Discussion: The discriminator (threshold) between Site Area Emergency and General Emergency is whether or not the EPA PAG plume exposure levels are expected to be exceeded outside the site boundary. This threshold, in addition to dynamic dose assessment considerations discussed in the EAL guidelines, clearly addresses NRC and offsite emergency response agency concerns as to timely declaration of a General Emergency. GENERAL EMERGENCY: Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. 1-5.6 SSREP Rev. 71

Discussion: The bottom line for the General Emergency is whether evacuation or sheltering of the general public is indicated based on EPA PAGs, and therefore should be interpreted to include radionuclide release regardless of cause. To better assure timely notification, EALs in this category must primarily be expressed in terms of plant function status, with secondary reliance on dose projection. In terms of fission product barriers, loss of two barriers with loss or potential loss of the third barrier constitutes a General Emergency. 5.5 Emergency Class Thresholds The most common bases for establishing these boundaries are the technical specifications and setpoints for each plant that have been developed in the design basis calculations and the Updated Final Safety Analysis Report (UFSAR). For those conditions that are easily measurable and instrumented, the boundary is likely to be the EAL (observable by plant staff, instrument reading, alarm setpoint, etc.) that indicates entry into a particular emergency class. For example, the main steam line radiation monitor may detect high radiation that triggers an alarm. That radiation level also may be the setpoint that closes the main steam isolation valves (MSIV) and initiates the reactor trip. This same radiation level threshold, depending on plant-specific parameters, also may be the appropriate EAL for a direct entry into an emergency class. In addition to the continuously measurable indicators, such as coolant temperature, coolant levels, leak rates, containment pressure, etc., the UFSAR provides indications of the consequences associated with design basis events. Examples would include steam pipe breaks, MSIV malfunctions, and other anticipated events that, upon occurrence, place the plant immediately into an emergency class. Another approach for defining these boundaries is the use of a plant-specific probabilistic safety assessment (PSA - also known as probabilistic risk assessment, PRA). A PSA has been completed for Seabrook Station. PSAs can be used as a good first approximation of the relevant ICs and risk associated with emergency conditions for existing plants. Generic insights from PSAs and related severe accident assessments which apply to EALs and emergency class determinations are:

1. Prolonged loss of all AC power events are extremely important. This would indicate that should this occur, and AC power is not restored within 15 minutes, entry into the emergency class at no lower than a Site Area Emergency, when the plant was initially at power, would be appropriate. This implies that precursors to loss of all AC power events should appropriately be included in the EAL structure.

2. For severe core damage events, uncertainties exist in phenomena important to accident progressions leading to containment failure. Because of these uncertainties, predicting containment integrity may be difficult in these conditions. This is why maintaining containment integrity alone following sequences leading to severe core damage may be an insufficient basis for not escalating to a General Emergency.

1-5.7 SSREP Rev. 71

3. EAL methodology must be sufficiently rigorous to cover risk-significant sequences such as containment bypass, large LOCA with early containment failure, station blackout greater than 4 hours (e.g., LOCA consequences of Station Blackout), and reactor coolant pump seal failure.

Another critical element of the analysis to arrive at these threshold (boundary) conditions is the time that the plant might stay in that condition before moving to a higher emergency class. In particular, station blackout coping analyses performed in response to 10 CFR 50.63 and Regulatory Guide 1.155, "Station Blackout," is used to determine whether a Site Area Emergency or a General Emergency is indicated. The time dimension is critical to the EAL since the purpose of the emergency class for state and local officials is to notify them of the level of mobilization that may be necessary to handle the emergency. This is particularly true when a "Site Area Emergency" or "General Emergency" is imminent. Regardless of whether or not containment integrity is challenged, it is possible for significant radioactive inventory within containment to result in EPA PAG plume exposure levels being exceeded even assuming containment is within technical specification allowable leakage rates. With or without containment challenge, however, a major release of radioactivity requiring offsite protection actions from core damage is not possible unless a major failure of fuel cladding allows radioactive material to be released from the core into the reactor coolant. NUREG-1228, "Source Estimations During Incident Response to Severe Nuclear Power Plant Accidents," indicates that such conditions do not exist when the amount of clad damage is less than 20%. 5.6 Emergency Action Levels With the emergency classes defined, the thresholds that must be met for each EAL to be placed under the emergency class can be determined. There are two basic approaches to determining these EALs. EALs and emergency class boundaries coincide for those continuously measurable, instrumented ICs, such as radioactivity, core temperature, coolant levels, etc. For these ICs, the EAL will be the threshold reading that most closely corresponds to the emergency class description using the best available information. For discrete (discontinuous) events, the approach will have to be somewhat different. Typically, in this category are internal and external hazards such as fire or earthquake. The purpose for including hazards in EALs is to assure that station personnel and offsite emergency response organizations are prepared to deal with consequential damage these hazards may cause. If, indeed, hazards have caused damage to safety functions or fission product barriers, this should be confirmed by symptoms or by observation of such failures. Therefore, it may be appropriate to enter an emergency for events approaching or exceeding design basis limits such as Operating Basis Earthquake, design basis wind loads, FIRE within VITAL AREAs, etc. This would give the operating staff additional support and improved ability to determine the extent of plant damage. If damage to barriers or challenges to Critical Safety Functions (CSFs) have occurred or are identified, then the additional support can be used to escalate or terminate the Emergency Class based on what has been found. Of course, security events must reflect potential for increasing security threat levels. 1-5.8 SSREP Rev. 71

Plant emergency operating procedures (EOPs) are designed to maintain and/or restore a set of CSFs which are listed in the order of priority for restoration efforts during accident conditions. The Seabrook Station CSF set includes: Subcriticality Core cooling Heat sink Pressure-temperature-stress (RCS integrity) Containment RCS inventory Emergency Coolant Recirculation Radiation/RDMS Display There are diverse and redundant plant systems to support each CSF. By monitoring the CSFs instead of the individual system component status, the impact of multiple events is inherently addressed, e.g., the number of operable components available to maintain the critical safety function. The EOPs contain detailed instructions regarding the monitoring of these functions and provides a scheme for classifying the significance of the challenge to the functions. In providing EALs based on these schemes, the emergency classification can flow from the EOP assessment rather than being based on a separate EAL assessment. This is desirable as it reduces ambiguity and reduces the time necessary to classify the event. As an example, consider that the Westinghouse Owner's Group (WOG) Emergency Response Guidelines (ERGs) classify challenges as YELLOW, ORANGE, and RED paths. If the core exit thermocouples exceed 1,100 degrees F or 725 degrees F with low reactor vessel water level, a RED path condition exists. The ERG considers a RED path as "... an extreme challenge to a plant function necessary for the protection of the public ..." This is almost identical to the present NRC NUREG-0654 description of a site area emergency "... actual or likely failures of plant functions needed for the protection of the public ..." It reasonably follows that if any CSF enters a RED path, a site area emergency exists. A general emergency could be considered to exist if core cooling CSF is in a RED path and the EOP function restoration procedures have not been successful in restoring core cooling. 5.7 Treatment of Multiple Events and Emergency Class Upgrading The emergency class declared is based on the highest EAL reached. For example, two Alerts remain in the Alert category. Or, an Alert and a Site Area Emergency is a Site Area Emergency. 1-5.9 SSREP Rev. 71

Although the majority of the EALs provide very specific thresholds, the STED/SED must remain alert to events or conditions that lead to the conclusion that exceeding the EAL threshold is imminent. If, in the judgment of the STED/SED, an imminent situation is at hand, the classification should be made as if the threshold has been exceeded. While this is particularly prudent at the higher emergency classes (as the early classification may provide for more effective implementation of protective measures), it is nonetheless applicable to all emergency classes. 5.8 Emergency Class Downgrading Another important aspect of usable EAL guidance is the consideration of what to do when the risk posed by an emergency is clearly decreasing. Seabrook Station uses a combination approach involving recovery from General Emergencies and some Site Area Emergencies and termination from Unusual Events, Alerts, and certain Site Area Emergencies causing no long-term plant damage. Downgrading to lower emergency classes adds notifications but may have merit under certain circumstances. 5.9 Classifying Transient Events For some events, the condition may be corrected before a declaration has been made. For example, an emergency classification is warranted when automatic and manual actions taken within the control room do not result in a required reactor trip. However, it is likely that actions taken outside of the control room will be successful, probably before the STED/SED classifies the event. The key consideration in this situation is to determine whether or not further plant damage occurred while the corrective actions were being taken. In some situations, this can be readily determined, in other situations, further analyses (e.g., coolant radiochemistry sampling, may be necessary). If the emergency-related indications completely clear before a declaration of an emergency classification level has been made, then no emergency classification is required. The Shift Manager shall notify the Emergency News Manager within one hour of the termination of the emergency-related indications that emergency-related indications briefly existed, but cleared prior to the declaration of an emergency classification. The Emergency News Manager will initiate state notifications per good neighbor notification procedures. The event shall be reported to the NRC in accordance with 10 CFR 50.72 and 50.73 per LI-AA-102-1001, Regulatory Reporting, and within 1 hour of the event. If emergency-related indications are received and later cleared, and after the fact it is determined that an emergency classification was warranted but not made, then no emergency classification is required. The Shift Manager shall notify the Emergency News Manager within one hour of discovery that an emergency classification was warranted but not declared and that emergency-related indications no longer exist. The Emergency News Manager will initiate state notifications per good neighbor notification procedures. The event shall be reported to the NRC in accordance with 10 CFR 50.72 and 50.73 per LI-AA-102-1001, Regulatory Reporting, and within 1 hour of the event. If emergency-related indications are received and reduce in severity, such that the emergency classification went from an earlier higher level to a current lower level, the current lower level emergency should be declared. 1-5.10 SSREP Rev. 71

Reporting requirements of 10 CFR 50.72 are applicable and the guidance of NUREG-1022, Rev. 1, Section 3 should be applied. 5.10 Cold Shutdown/Refueling IC/EALs Generic Letter 88-17, Loss of Decay Heat Removal, SECY-91-283, Evaluation of Shutdown and Low Power Risk Issues, SECY-93-190, Regulatory Approach to Shutdown and Low-power Operation, NUREG-1449, Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States, and NUMARC 91-06, Guidelines for Industry Actions to Assess Shutdown Management, all address nuclear power plant safety issues that are applicable to periods when the plant is shutdown. These evaluations identify a number of variables which significantly affect the probability and consequences of losing decay heat removal capability during shutdown periods. In addition, NUREG-1449 discusses that the need to respond appropriately, including emergency classification and notification, still exists during cold-shutdown and refueling conditions. Through use of NEI 99-01, Revision 6, the Seabrook Station emergency classification system addresses issues concerning shutdown effects on declaring emergencies discussed in SECY-93-190 and NUREG-1449. Given the variability of plant configurations (e.g., systems out-of-service for maintenance, containment open, reduced AC power redundancy, time since shutdown) during these periods, the consequences of any given initiating event can vary greatly. For example, a loss of decay heat removal capability that occurs at the end of an extended outage has less significance than a similar loss occurring during the first week after shutdown. Compounding these events is the likelihood that instrumentation necessary for assessment may also be inoperable. The cold shutdown and refueling EALs are based on performance capability to the extent possible with consideration given to RCS integrity, containment closure, and fuel clad integrity for the applicable modes. The initiating conditions and example emergency actions levels associated directly with Cold Shutdown or Refueling safety function are presented in Recognition Category C, Cold Shutdown/Refueling. 5.11 ISFSI IC/EALs An Independent spent fuel storage installation (ISFSI) is a complex that is designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage. The Final Rule governing Emergency Planning Licensing Requirements for Independent Spent Fuel Storage Facilities (Federal Register Volume 60, Number 120 June 22, 1995, Pages 32430-32442) indicated that a significant amount of the radioactive material contained within a cask must escape its packaging and enter the biosphere for there to be a significant environmental impact resulting from an accident involving the dry storage of spent nuclear fuel. Formal offsite planning is not required because the postulated worst-case accident involving an ISFSI has insignificant consequences to the public health and safety. 1-5.11 SSREP Rev. 71

Recognition Category E (Events Related to ISFSI) is applicable to licensees using their 10 CFR 50 emergency plan to fulfill the requirements of 10 CFR 72.32. The emergency classifications for Recognition Category E are those provided by NUREG 0654/FEMA Rep.1 in accordance with 10 CFR 50.47. The classification of an ISFSI event under provisions of a 10 CFR 50.47 emergency plan should be consistent with the definitions of the emergency classes as used by that plan. 1-5.12 SSREP Rev. 71

EMERGENCY INITIATING CONDITION MATRIX Modes 1, 2, 3, and 4 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Category R- Abnormal Rad Levels/Radiological Effluent RG1 Release of gaseous radioactivity RS1 Release of gaseous radioactivity RA1 Release of gaseous or liquid RU1 Release of gaseous or liquid resulting in offsite dose > 1,000 resulting in offsite dose > 100 mrem radioactivity resulting in offsite dose radioactivity > 2 times the ODCM mrem TEDE or 5,000 mrem thyroid TEDE or 500 mrem thyroid CDE > 10 mrem TEDE or 50 mrem thyroid limits for 60 minutes CDE Op. Modes: All CDE Op. Modes: All Op. Modes: All Op. Modes: All RG2 Spent fuel pool level cannot be RS2 Spent fuel pool level at 1.5 ft. (Level 3) RA2 Significant lowering of water level RU2 UNPLANNED loss of water level restored to at least 1.5 ft. (Level 3) Op. Modes: All above, or damage to, irradiated fuel. above irradiated fuel for 60 minutes or longer. Op. Modes: All Op. Modes: All Op. Modes: All RA3 Radiation levels that IMPEDE access to equipment necessary for normal plant operations, shutdown or cooldown. Op. Modes: All Category E - Events Related to ISFSI Malfunction EU1 Damage to a loaded cask CONFINEMENT BOUNDARY Op. Mode: All Category H - Hazards and Other Conditions Affecting Plant Safety HS1 HOSTILE ACTION within the HA1 HOSTILE ACTION within the HU1 Confirmed SECURITY CONDITION PROTECTED AREA. OWNER CONTROLLED AREA or or threat. Op. Modes: All airborne attack threat within 30 Op. Modes: All minutes Op. Modes: All HU2 Seismic event greater than OBE levels. Op. Modes: All HU3 Hazardous event. Op. Modes: All HU4 FIRE potentially degrading the level of safety of the plant. Op. Modes: All HA5 Gaseous release impeding access to equipment necessary for normal plant operations, shutdown or cooldown Op. Modes: All HS6 Inability to control a key safety function HA6 Control Room evacuation resulting in from outside the Control Room transfer of plant control to alternate Op. Modes: All locations Op. Modes: All HG7 Other conditions exist which in the HS7 Other conditions exist which in the HA7 Other conditions exist which in the HU7 Other conditions exist which in the judgment of the STED/SED warrant judgment of the STED/SED warrant judgment of the STED/SED warrant judgment of the STED/SED warrant declaration of a General Emergency declaration of a Site Area Emergency declaration of an Alert declaration of an Unusual Event Op. Modes: All Op. Modes: All Op. Modes: All Op. Modes: All Category M - System Malfunction MG1 Prolonged loss of all offsite and all MS1 Loss of all offsite and all onsite AC MA1 Loss of all but one AC power source MU1 Loss of all offsite AC power onsite AC power to emergency power to emergency buses for 15 to emergency buses for 15 minutes capability to emergency buses for buses minutes or longer or longer 15 minutes or longer AND Op. Modes: 1, 2, 3, 4 Op. Modes: 1, 2, 3, 4 Op. Modes: 1, 2, 3, 4 Restoration of at least one AC emergency bus in less than 4 hours is not likely. OR Core Cooling (C) CSF RED entry conditions met Op. Modes: 1, 2, 3, 4 MA2 UNPLANNED loss of Control Room MU2 UNPLANNED loss of Control Room indications for 15 minutes or longer indications for 15 minutes or longer with a significant transient in Op. Modes: 1, 2, 3, 4 progress. Op. Modes: 1, 2, 3, 4 MU3 Reactor coolant activity greater than Technical Specification allowable limits Op. Modes: 1, 2, 3, 4 MU4 RCS leakage for 15 minutes or longer Op. Modes: 1, 2, 3, 4 MS5 Inability to shutdown the reactor MA5 Automatic or manual trip fails to MU5 Automatic or manual trip fails to causing a challenge to core cooling or shutdown the reactor, and shutdown the reactor RCS heat removal subsequent manual actions taken at Op. Modes: 1 Op. Modes: 1 the Main Control Board are not successful in shutting down the reactor Op. Modes: 1 MU6 Loss of all onsite or offsite communications capabilities Op. Modes: 1, 2, 3, 4 MU7 Failure to isolate containment or loss of containment pressure control Op Modes: 1, 2, 3, 4 MG8 Loss of all AC and Vital DC power MS8 Loss of all Vital DC power for sources for 15 minutes or longer 15 minutes or longer Op. Modes: 1, 2, 3, 4 Op. Modes: 1, 2, 3, 4 MA9 Hazardous event affecting a SAFETY SYSTEM needed for the current Op. Modes: 1, 2, 3, 4 Modes 1, 2, 3 and 4 Figure 5.6 SSREP Rev. 57

EMERGENCY INITIATING CONDITION MATRIX Modes 5, 6, and Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Category R - Abnormal Rad Levels/Radiological Effluent RG1 Release of gaseous radioactivity RS1 Release of gaseous radioactivity RA1 Release of gaseous or liquid RU1 Release of gaseous or liquid resulting in offsite dose > 1,000 resulting in offsite dose > 100 mrem radioactivity resulting in offsite dose radioactivity > 2 times the ODCM mrem TEDE or 5,000 mrem thyroid TEDE or 500 mrem thyroid CDE > 10 mrem TEDE or 50 mrem thyroid limits for 60 minutes CDE Op. Modes: All CDE Op. Modes: All Op. Modes: All Op. Modes: All RG2 Spent fuel pool level cannot be RS2 Spent fuel pool level at 1.5 ft. (Level 3) RA2 Significant lowering of water level RU2 UNPLANNED loss of water level restored to at least 1.5 ft. (Level 3) Op. Modes: All above, or damage to, irradiated fuel. above irradiated fuel for 60 minutes or longer. Op. Modes: All Op. Modes: All Op. Modes: All RA3 Radiation levels that IMPEDE access to equipment necessary for normal plant operations, shutdown or cooldown. Op. Modes: All Category E - Events Related to ISFSI Malfunction EU1 Damage to a loaded cask CONFINEMENT BOUNDARY Op. Mode: All Category H - Hazards and Other Conditions Affecting Plant Safety HS1 HOSTILE ACTION within the HA1 HOSTILE ACTION within the HU1 Confirmed SECURITY CONDITION PROTECTED AREA OWNER CONTROLLED AREA or or threat Op. Modes: All airborne attack threat within 30 Op. Modes: All minutes Op. Modes: All HU2 Seismic event greater than OBE levels. Op. Modes: All HU3 Hazardous event. Op. Modes: All HU4 FIRE potentially degrading the level of safety of the plant. Op. Modes: All HA5 Gaseous release impeding access to equipment necessary for normal plant operations, shutdown or cooldown Op. Modes: All HS6 Inability to control a key safety function HA6 Control Room evacuation resulting in from outside the Control Room transfer of plant control to alternate Op. Modes: All locations Op. Modes: All HG7 Other conditions exist which in the HS7 Other conditions exist which in the HA7 Other conditions exist which in the HU7 Other conditions exist which in the judgment of the STED/SED warrant judgment of the STED/SED warrant judgment of the STED/SED warrant judgment of the STED/SED warrant declaration of a General Emergency declaration of a Site Area Emergency declaration of an Alert declaration of an Unusual Event Op. Modes: All Op. Modes: All Op. Modes: All Op. Modes: All Category C - Cold Shutdown/Refueling System Malfunction CG1 Loss of reactor vessel/RCS inventory CS1 Loss of reactor vessel/RCS inventory CA1 Loss of reactor vessel/RCS inventory CU1 UNPLANNED loss of reactor affecting fuel clad integrity with affecting core decay heat removal Op. Modes: 5, 6 vessel/RCS inventory for 15 containment challenged capability minutes or longer Op. Modes: 5, 6 Op. Modes: 5, 6 Op. Modes: 5, 6 CA2 Loss of all offsite and all onsite AC CU2 Loss of all but one AC power power to emergency buses for 15 source to emergency buses for 15 minutes or longer minutes or longer Op. Modes: 5, 6, Defueled Op. Modes: 5, 6, Defueled CA3 Inability to maintain the plant in cold CU3 UNPLANNED increase in RCS shutdown temperature. Op. Modes: 5, 6 OR Loss of ALL RCS temperature and reactor vessel/RCS level indication for 15 minutes or longer Op. Modes: 5, 6 CU4 Loss of Vital DC power for 15 minutes or longer Op. Modes: 5, 6 CU5 Loss of all onsite or offsite communications capabilities Op. Modes: 5, 6, Defueled CA6 Hazardous event affecting a SAFETY SYSTEM needed for the current operating mode Op. Modes: 5, 6 Modes 5, 6, and Defueled Figure 5.7 SSREP Rev. 57

FISSION PRODUCT BARRIER DEGRADATION MATRIX Modes 1, 2, 3, and 4 Fuel Clad Barrier Reactor Coolant System Barrier Containment Barrier Sub-Category Loss Potential Loss Loss Potential Loss Loss Potential Loss Core Cooling (C) ORANGE entry conditions RCS Integrity (P) RED entry conditions met Core Cooling (C) RED entry conditions met for met 15 minutes or longer Core Cooling (C) RED entry conditions met. with RCS press > 300 psig. OR

1. CSF Status OR OR (Note 1) Containment (Z) CSF - RED entry conditions Heat Sink (H) RED entry conditions met. Heat Sink (H) RED entry conditions met. met.

(Note 1) (Note 1) (Note 1) RCS activity > 300 uCi/gm Dose Equivalent I-131 (as determined per Procedure

2. RCS Activity CS0925.01, Reactor Coolant Post Accident Sampling)

Operation of a second charging pump in the An automatic or manual SI actuation is normal charging mode is required by EITHER required by EITHER of the following: of the following: Indications of RCS leakage outside of

3. RCS Leakage 1. UNISOLABLE RCS leakage

1. UNISOLABLE RCS leakage containment.

OR OR

2. SG tube RUPTURE

2. SG tube leakage.

A leaking or RUPTURED SG is FAULTED

4. S/G Rupture or Fault outside of containment.

Containment isolation is required Containment H2 concentration 6% AND EITHER of the following: OR

1. Containment integrity has been lost 1. Containment pressure > 18 psig

5. Containment Integrity based on STED/SED judgment. AND OR 2. Less than one full train of Containment

2. UNISOLABLE pathway from the Building Spray (CBS) is operating per containment to the environment exists. design for 15 minutes or longer

6. Containment Post-LOCA Radiation Monitors Post-LOCA Radiation Monitors Post-LOCA Radiation Monitors Radiation Monitor RM-6576A-1 or RM-6576B-1 95 R/hr RM-6576A-1 or RM-6576B-1 16 R/hr RM-6576A-1 or RM-6576B-1 1,305 R/hr Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED

7. STED/SED Judgment that indicates a Potential Loss of the Fuel Clad that indicates a Potential Loss of the RCS that indicates a Loss of the Containment that indicates a Potential Loss of the that indicates a Loss of the Fuel Clad Barrier. that indicates a Loss of the RCS Barrier.

Barrier. Barrier. Barrier. Containment Barrier. Barrier Status General Emergency Alert Site Area Emergency FG1 - Loss of ANY Two Barriers AND Loss FA1 - ANY Loss or Potential Loss FS1 - Loss or Potential Loss of ANY Two Barriers or Potential Loss of Third Barrier of EITHER Fuel Clad or RCS Barriers Fuel Clad Loss Enter Fuel Clad Potential Loss Enter RCS Loss Enter RCS Potential Loss Enter Containment Loss Enter Containment Potential Loss Enter Emergency Classification GE GE GE GE SAE SAE SAE SAE SAE SAE SAE SAE SAE SAE SAE SAE ALERT ALERT ALERT ALERT NOTE 1: Refer to ER 1.1, Section 1.1, Discussion concerning the proper use of CSFSTs as EALs Figure 5.8 SSREP Rev. 57

6.0 EMERGENCY FACILITIES AND EQUIPMENT Following the declaration of an emergency, the activation of the Emergency Response Organization (ERO) will be accomplished within a number of dedicated emergency facilities. Figure 4.3 indicates the relative locations of Station facilities within the site. Figure 6.1 represents the locations of offsite support organization emergency operations centers relative to the Seabrook Station site. Descriptions of Seabrook Station facilities follow in Section 6.1. A description of emergency equipment and inventories is found in the Emergency Preparedness Department Facility Inventory Manual (EPFI). 6.1 Emergency Centers 6.1.1 Technical Support Center A Technical Support Center (TSC) has been established in the Control Building to direct post-accident evaluation and assist in recovery actions. The TSC is habitable to the same degree as the Control Room for postulated accident conditions. The TSC has the capability to access and display Station parameters, including the Safety Parameter Display System (SPDS), independent from actions in the Control Room. The TSC is included in the Station emergency communications network. The TSC has access to the Seabrook Updated Final Safety Analysis Report (UFSAR), the Seabrook Station Radiological Emergency Plan (SSREP) and procedures, and a selected set of system prints, system flow diagrams, cable/wiring diagrams and equipment specifications. The TSC has the capability to assess radiological habitability conditions by monitoring for direct radiation and airborne particulates, and sampling for airborne radioiodines. Figure 8.6 defines the TSC organization. The TSC and TSC Document Control Center are depicted in Figure 6.2. An alternative facility for TSC responders has been identified in the EOF for hostile action based events or other catastrophic events that prevent site access in accordance with 10 CFR 50 Appendix E, Section IV, E, 8, d. Procedures for TSC responders are located in the alternative facility. 6.1.2 Operational Support Center The Operational Support Center (OSC), located on the first floor of the Administration and Service Building, provides a general assembly/dispatch area for assigned Station manpower needed to effect protective and corrective actions in support of the emergency situation. The OSC is included in the Station emergency communications network. Emergency equipment is provided at the Radiological Controlled Area (RCA) access point located within the OSC. Tools required by repair teams are provided at tool cribs maintained by the Maintenance Department in the RCA and other locations in the plant. Should conditions warrant evacuation of this center, the TSC will assume OSC functions; otherwise the OSC will remain active and staffed until terminated by the Site Emergency Director. Figure 8.5 defines the OSC organization. A layout of the OSC is provided in Figure 6.5. An alternative facility for OSC responders has been identified in the EOF for hostile action based events or other catastrophic events that prevent site access in accordance with 10 CFR 50 Appendix E, Section IV, E, 8, d. Procedures for OSC responders are located in the alternative facility. 1-6.1 SSREP Rev. 73

6.1.3 Emergency Operations Facility An Emergency Operations Facility (EOF) is located at the Pease International Tradeport in Portsmouth, New Hampshire. The EOF shown in Figure 6.6 serves as a base of operations for radiological assessment, overall emergency response organization management and recovery activities. The State of New Hampshire Incident Field Office is physically co-located with the EOF. This arrangement ensures close coordination with State emergency response staff. The EOF is included in the Station emergency communications network, as described in Section 7.0, which links all emergency response facilities, monitoring and assistance teams dispatched from the EOF, and offsite agencies. The EOF has the capability to access and display Station parameters, including the Safety Parameter Display System, independent of both the TSC and Control Room. Backup power to the EOF is available. Radiological assessment, monitoring and evaluation, and protective action recommendation formulation are directed from the EOF. The EOF organization shown in Figure 8.4 is responsible for continuous evaluation and coordination of all Seabrook Station activities related to an emergency having, or potentially having, adverse radiological consequences. Copies of selected building prints and general building layouts are available via the LAN and on disk and can be printed out at the EOF. Emergency planning documents applicable to Seabrook Station, including area maps, emergency response procedures, State and local emergency plans are available in the EOF. The Seabrook Station updated UFSAR is available via the LAN. A backup disk version is maintained at the EOF. The EOF has sufficient assembly space and is designed to accommodate responding representatives from government and industry. The EOF serves as the base of operations for Station material control, coordination of industry support, and establishment of a long-term organization to recover from the accident conditions and results. The EOF can serve as a centralized meeting location for key representatives from offsite authorities and Station management. The EOF can also act as a focal point for the coordination and acquisition of company resources and liaison with the Seabrook Station Joint Owners, American Nuclear Insurers and Institute of Nuclear Power Operations (INPO). Emergency equipment maintained at the EOF includes gear necessary to assess radiological habitability. This consists of monitoring for direct radiation, and sampling for airborne radioparticulates and radioiodines. The EOF provides information needed by Federal, State and local authorities for implementation of offsite emergency plans. 6.1.4 Support for Radiological Analysis of Environmental Samples The Environmental Analysts will be activated at a Site Area and General Emergency to provide radiological analysis of environmental samples in the EOF. The Environmental Analysts will respond to the EOF to utilize radio-analysis equipment maintained in the EOF to analyze silver zeolite cartridges and particulate filters used by field monitoring and environmental sampling teams to collect air samples in the field. 1-6.2 SSREP Rev. 73

More definitive analysis of environmental samples will be available from GEL Laboratories. GEL is capable of providing on a continuous basis a full spectrum of radio-analysis of environmental samples which includes identification of principal accident radio-nuclides and their evaluation against EPA dose guidelines for relocation and FDA derived intervention levels associated with consumption of contaminated foods. 6.1.5 Joint Information Center The Joint Information center (JIC) is co-located with the EOF in Portsmouth, New Hampshire. The center will be activated in order to provide a centralized location for holding joint utility, State, and Federal emergency news briefings. JIC support will also be supplied by NextEra Corporate Communications, based out of Florida. The Corporate JIC Manager and Emergency Communications Team (ECT) will work together with the JIC personnel located at the EOF. The Corporate JIC team will provide support remotely or travel to the JIC, dependent on the severity of the emergency. The Corporate JIC Manager and the Emergency News Manager will coordinate activities at the JIC. Emergency information will be obtained from the EOF and disseminated to the news media at the JIC. This center will accommodate the media by providing

1. a media relations telephone service for news media to call for information;

2. a media briefing room with a public address system and graphics;

3. accommodations for video and audio equipment and media vans; and

4. station background information.

It is expected that State and Federal public information personnel will operate from the JIC. New Hampshire Homeland Security & Emergency Management (NHHSEM) and Massachusetts Emergency Management Agency (MEMA) operate a rumor control telephone service for their respective states. Rumor trends will be reported to the NHHSEM and MEMA representatives in the Joint Information Center where they can be addressed in joint news briefings. 6.1.6 Federal Radiological Monitoring and Assessment Center The Federal Radiological Monitoring and Assessment Center (FRMAC) will be established by the US Department of Energy (DOE) at a suitable facility in proximity to the EOF in response to a request from either State or Federal authorities. The DOE and Environmental Protection Agency (EPA) are prepared to deploy specialized resources and establish a base of operations for offsite radiological monitoring and assessment activities. Environmental data obtained by an array of technical experts operating out of this center will be used by governmental officials in determining the hazard associated with the incident and the appropriate protective actions. DOE is responsible for the coordination of FRMAC emergency activities as described in the National Response Framework, Nuclear/Radiological Incident Annex. 1-6.3 SSREP Rev. 73

6.2 Assessment Capability The activation of this plan and the continual assessment of accident conditions require extensive monitoring and assessment capabilities. The essential monitoring systems needed to allow recognition of abnormal events by the Station operators was used in the accident classification methodology. This section briefly describes these monitoring systems as well as other assessment capabilities. 6.2.1 Process Monitors Station process monitoring capability includes many process monitor indications provided from various sensors located throughout Station systems. Parameters monitored include pressure, temperature, flow, level and equipment operating status. These monitoring systems are described in the Seabrook Station UFSAR. 6.2.2 Radiation Data Management System The Radiation Data Management System (RDMS) provides operators with the ability to assess Station radiological conditions during normal operations, as well as radiological emergency conditions. The RDMS is a microprocessor-based acquisition and display system. Field mounted detectors communicate individually to their own microprocessor which in turn communicates to two central processing units (CPU) on a redundant communication loop. The various parameters monitored include general area radiation, process radioactivity levels, airborne contamination levels, and effluent radioactivity levels. The quantity and diversity of the parameters monitored, along with the display capabilities of the RDMS, provide the operator with sufficient warning of accident conditions as well as continual accident assessments. However, the primary means of quantitatively evaluating system and plant radioactivity levels will be through a program of collecting physical samples and subjecting these physical samples to laboratory analysis to identify specific isotopes and their relation to the RDMS. A contingency capability has been established to measure accident dose rates in the reactor coolant system and to correlate the dose rates to reactor coolant activity. This capability provides the operators with fuel defect information that would be used to classify fuel damage events. This contingency capability includes the ability to collect an archive sample from either the reactor coolant system or the containment sump for laboratory analysis. Each of the RDMS monitors alarms in the Control Room and Operational Support Center for a variety of alarm conditions (e.g., alert level, high level, power failure, etc.). This system is described in the Seabrook Station UFSAR. 1-6.4 SSREP Rev. 73

6.2.3 Geophysical Phenomena Monitors

1. Meteorological Seabrook Station maintains a 210-foot-high meteorological tower located near the south edge of Brown's River, as shown in Figure 4.3. The parameters monitored include wind speed and direction at 43 feet and 209 feet above ground level, and vertical temperature difference (delta-T) between 43 feet and 150 feet and between 43 feet and 209 feet. The meteorological data from the tower are scanned and recorded as 15-minute averages by the Main Plant Computer System (MPCS). These averages are available for on-demand display on MPCS terminals located in the Control Room, TSC, and EOF. A data logger located in the instrument building near the base of the tower serves as backup recording mechanism. (Protected: Ref. NRC IR 85-32(19))

A freestanding 53' backup meteorological tower is located adjacent to the settling basin outlet structure. The meteorological data from the backup tower are scanned and recorded as 15-minute averages by an independent computer system. These averages for wind speed, wind direction and calculated equivalent delta temperature are available for on-demand display on MPCS terminals located in the Control Room, TSC and EOF. (Protected: Ref. NRC IR 85-32(20)) Additional sources of meteorological information include various National Weather Service (NWS) Offices. A dispersion model, Raddose-V, produces plume transport and diffusion estimates for the plume exposure pathway Emergency Planning Zone. The model produces plume dimensions, position, and relative concentrations at several downwind locations. Using effluent release information and a finite cloud external gamma dose model, estimates of near real-time dose rates will also be available. The model has the graphics capability of drawing plume position over a background map of the site. More information on these calculation techniques is given in Section 10.1.1 of this plan.

2. Seismic Seabrook Station has installed seismic monitoring equipment with alarms indicated in the Control Room. The equipment consists of Triaxial Time History Accelerographs capable of measuring and permanently recording the absolute acceleration versus time for both horizontal and vertical motion.

The Control Room alarms will indicate the following:

a. Seismic event in progress;

b. Seismic monitor trouble; and/or

c. Seismic monitor OBE exceedance.

1-6.5 SSREP Rev. 73

3. Hydrologic Seismic Category I structures that house safety-related equipment have been designed to withstand a depth of still water on the Station grade (+20.6 ft. MSL) of 0.6 feet. Access openings in exterior walls that are below the design flood level consist of a railroad door in Unit 1 Fuel Storage Building and man doors in other structures. Flood protection has been provided by means of water-tight doors or curbs around the door openings. In the case of the Fuel Storage Building, curbs have been constructed around vulnerable equipment. All below-grade structures are waterproofed on the exterior face, and sumps have been installed in all buildings. Because of the general design, it was not necessary to install hydrologic monitors, nor will it be necessary to bring the reactor to a cold shutdown for the most severe flood anticipated for the Station.

6.2.4 Fire Detection Systems Seabrook Station maintains an extensive fire detection network which utilizes a combination of smoke detectors, thermal detectors and rate-of-rise detectors as means of providing Station operators with complete fire status information. The fire protection system is comprised of the following basic systems:

1. A pumped water system providing a complete underground looped station fire main with hydrants, hose houses and hose carrier for yard and building exterior protection, and internal sprinklers, hose stations and deluge systems for specific building applications.

2. Portable halon extinguishers in the Control Room complex, and all battery rooms.

3. Portable C02 fire extinguishers for use in relay room and switchgear areas.

4. Portable C02 and dry chemical fire extinguishers located throughout the Station for immediate use on small fires.

5. Fire pump house ventilation system.

6. Fire pump house and fire tank heating system.

7. Standpipes with hose stations in the containment, control building, primary auxiliary building, fuel storage building, waste processing building and equipment vaults.

1-6.6 SSREP Rev. 73

6.2.5 Facilities and Equipment for Offsite Monitoring In addition to offsite monitoring equipment and maps at the EOF as described in Section 6.1.3, Seabrook Station conducts an offsite radiological environmental surveillance program. This program has been established for the site and surrounding area to monitor the environment under normal and accident conditions. Details of the requirements of this program are contained in the Station Offsite Dose Calculation Manual (ODCM). The EOF is equipped with a gamma spectroscopy system with High Purity Germanium detector and data processing computer. GEL Laboratories is available on a continuous 24 hour, seven days a week basis to provide a full spectrum of radio-analytical measurements on environmental sample media. If mobilized, additional offsite monitoring and analysis capability will be provided by Federal agencies in accordance with the National Response Framework, Nuclear/Radiological Incident Annex, as discussed in Section 6.1.6. This additional capability would be integrated with the efforts underway in a coordinated manner. 1-6.7 SSREP Rev. 73

7.0 COMMUNICATIONS Seabrook Station has established an emergency communications network for notifying and coordinating activities with offsite and onsite emergency response organizations. A summary of the communication network is presented below. 7.1 Nuclear Alert System The Nuclear Alert System (NAS), originating in the Control Room, and comprised of leased telephone lines, is used to notify the New Hampshire State Police (NHSP) Communications Center Dispatcher and Massachusetts Emergency Management Agency (see Figure 7.1) (MEMA) 24-hour Dispatcher of an emergency. The NHSP and MEMA dispatchers will notify the Director, New Hampshire Homeland Security

   & Emergency Management and Director, MEMA, respectively. The Directors will notify their respective Governors. In addition to the Control Room and offsite warning points, the NAS has been installed in the two states' Emergency Operations Centers (EOCs), the MA Region I EOC in Tewksbury, the NH Rockingham County warning point in Brentwood, and the Emergency Operations Facility (EOF). The system can serve as a back-up communication system for coordination between the locations as shown on Figure 7.2. Backup to this system is a radio system.

Provisions are made for backup power to the Nuclear Alert System. This system is manned on a 24-hour basis on both ends - the Station and the state offsite warning points. The system is tested monthly between the states and the Station. 7.2 NRC Communications Channels A designated FTS-2001 telephone is installed in the Control Room as the Emergency Notification System (ENS) line. This line is used to provide initial emergency notifications to the Nuclear Regulatory Commission Headquarters Operations Center in Rockville, MD. The line is staffed on an around-the-clock basis by both organizations. The ENS line is also available in the EOF and the Alternative TSC. Designated FTS-2001 telephones are installed in the Emergency Operations Facility and the Technical Support Center to support the Health Physics Network (HPN). These telephones will be used to provide radiological and protective action-related information to the NRC. Additional FTS-2001 and commercial line capabilities have been established in each response center for use by NRC response team members. The Emergency Response Data System (ERDS) is installed as a user-selected function on the Main Plant Computer System (MPCS). ERDS may be activated from selected MPCS terminals located in the Control Room and TSC. ERDS will be activated within 1 hour of the declaration of an Alert or higher emergency classification. ERDS is tested on a quarterly basis. 1-7.1 SSREP Rev. 65

7.3 Telephone System The Telephone System is used as a means of communications for notification and coordination with onsite and offsite organizations/teams. The telephone system is interconnected with the public address system and leased communications systems. If power is lost to the Station PBX, certain extensions located in the Control Room, TSC, OSC and Guard Island will be automatically connected to the public telephone exchange network directly. Power to the PBX is backed up by uninterruptible power supplies and the diesel generator. The telephone system can also access the UHF Trunked Radio System via a telephone interconnect. 7.4 Commercial Pager Service Seabrook Station utilizes a commercially available paging service to notify Primary Responders, Subject-to-Call Responders and other Secondary Responders. These digital display pagers are activated by telephone or by computer software. Pagers may be activated collectively by a group call number or individually. This pager system uses multiple transmitter sites within a twenty-five-mile radius of Seabrook Station. 7.5 Station Radio System Figure 7.3 provides a summary of the Offsite Monitoring Team Radio Communications Network described in Section 7.5.1. Figure 7.5 provides a summary of the existing Seabrook Station UHF station radio communications network described in Section 7.5.2. 7.5.1 Offsite Monitoring Team Radio Network The VHF radio system previously used as a primary means of two-way communications with the radiological survey teams has been retired. A UHF network, using radio frequencies supporting the Seabrook Public Alert Notification System (PANS), replaces it. This network consists of the following:

1. A tone remote, control base, and antenna assigned to the Emergency Operations Facility (EOF) which can transmit to radiological survey via five distinct channels.

2. Two mobile radios installed in dedicated radiological survey vehicles and a third portable mobile which can be installed in any vehicle.

3. Six portable radios available to support State radiological survey teams, as needed All components of the EOF controls are backed up by emergency power. All system repeaters are backed up by emergency power.

To support rapid deployment of onsite radiological survey teams within or near the site boundary, remote control consoles in the Control Room, Technical Support Center, and Operational Support Center can provide two-way communications with the teams via portables operating on the station UHF frequency discussed in Section 7.5.2. Dedicated portables are stored in both the Operational Support Center and a location outside the Protected Area. 1-7.2 SSREP Rev. 65

Seabrook Station also maintains commercially available mobile communications designed to provide two-way communications with State and utility radiological survey teams. 7.5.2 UHF Radio System A UHF trunked radio repeater system is used for onsite two-way communications by station Operations, Maintenance, Fire Fighters, Health Physics, and Security personnel. Trunking is the process where a trunking controller automatically selects the channel/repeater when a user keys a portable radio or base station. The trunking controller automatically selects the communication path rather than the user having to manually switch channels to find a clear channel. Should a trunked repeater fail, the trunking controller will allow the user to continue communication almost without knowledge of the repeater failure and without termination of the communication. Should the trunking controller fail, the system reverts to operation similar to a conventional repeater system where users are assigned a specific repeater. For a failure of all fixed radio equipment (trunking controller, repeaters, and RF mixing rack), communications can be maintained by manually switching the control stations and portables to the TALKAROUND (direct) mode. This mode has reduced coverage since the repeaters are not in service. Trunking greatly improves the reliability of the entire system and allows individual repeaters to handle traffic from any user group if other repeaters are in use or inoperable. The programmable features of the system allow the creation of various user talk groups and priority levels. A conventional radio repeater is provided as a telephone system interconnect. This allows the radio system to access the telephone system, or vice versa. This capability exists only for those portable radios that are programmed for this feature. Another conventional repeater is provided as a paging system interconnect to activate onsite pagers. The radio system equipment is powered from the nonsafety power system. Backup power for the trunking controller, repeaters, and RF mixing rack is provided by an emergency diesel generator and by a dedicated battery rated for two hours. Other fixed radio equipment such as control stations and control consoles are provided with backup power from an emergency diesel generator backed or uninterruptible power supply (UPS) backed sources, or a dedicated battery rated for two hours. Portable radios can operate independently of all other systems. They are backed up by their own batteries for continued operation in case of loss of all AC power. Remote control consoles are located at the main control room, the Technical Support Center (TSC), and the Health Physics/Operational Support Center (HP/OSC). For a description of the system features provided for Security, refer to the Security Plan. 7.6 Station Paging System A plant paging system is used for alerting in-plant personnel of emergencies. A central control panel is located in the Control Room. The paging system is accessed through dedicated paging system handsets which are located throughout the plant including the Control Room, Technical Support Center, Operational Support Center, and Security Guard House. 1-7.3 SSREP Rev. 65

The system consists of four channels, and is utilized as a page/talk system under normal operations. During emergency situations, the system can be used for (1) alerting Station personnel; (2) coordinating activities between onsite response teams and the Technical Support Center; (3) calling missing persons that may be in the Station; (4) coordinating activities between Control Room and Technical Support Center; and (5) communicating between Station centers. A multi-tone generator is associated with the paging system. This generator produces the various alarms designated to alert Station personnel of emergency situations. Alerting is ensured by the location of the page system speakers. In high background noise areas, beacon lights or similar devices supplement the speakers. The alerting signal is manually initiated from the Control Room by keying the appropriate alarm station. The evacuation alarm takes priority over all other transmissions. Power to the paging system is provided by uninterruptible power supplies, independent from the power supply for the telephone system. The paging system is used daily and the alerting alarm is tested weekly. 7.7 Sound-Powered Telephone System The Station has been equipped with a multiple loop sound-powered telephone system. Jack locations have been provided near many major pieces of equipment and on control panels, instrument racks, motor control centers, unit substations and switchgear. Switching panels are provided in the Control Room to enable the loops to be connected together. A supply of sound powered telephone handsets and cables are available in the Control Room emergency supply room. Since no external power is necessary for operation, the system is available during an emergency; however, its greatest application would occur during a recovery phase. 1-7.4 SSREP Rev. 65

8.0 ORGANIZATION 8.1 Introduction An Emergency Response Organization (ERO) has been established to respond to radiological emergencies at Seabrook Station. This organization includes Seabrook Station personnel, local services support, and private organization support. The structure of the emergency response organization will vary depending on the time of day, the severity of the incident, and the emergency classification. In the initial phases of an accident, an on-shift ERO (See Figure 8.1) consisting of personnel from the normal Station organization will be responsible for event classification and completion of emergency actions. In the following phases of emergency response, the Augmented ERO for either the Unusual Event (See Figure 8.2) or Alert, Site Area Emergency, and General Emergency (See Figure 8.3) will be activated with the capability of continuous, 24-hour-per-day operations for a protracted period. Figure 8.15 provides a comparison of the NUREG-0654 Table B-1 emergency response staffing requirements with the on-shift ERO. 8.2 Emergency Response Organization The ERO structure which would be activated to respond to an incident at Seabrook Station is provided in Figures 8.1 through 8.6 and Figure 8.9. Appendix A describes the positions listed on these figures along with activation level, response location and responsibilities. Appendix A also correlates the normal Station title and/or types of background and responsibilities of assigned personnel to the emergency title for each position. 8.2.1 On-Shift Emergency Response Organization The Shift Manager has the authority and responsibility to classify abnormal conditions in accordance with the emergency classification system. The classification and declaration of an emergency initiates the activation of the on-shift ERO (See Figure 8.1). Once an emergency is declared, the Shift Manager assumes the position of Short Term Emergency Director (STED). If available, the Unit Supervisor may assume the duties of the STED in the absence of the Shift Manager. The Work Control Supervisor is a senior licensed individual assigned to each shift and is available to assist the STED with emergency plan implementation. Such assistance will be at the discretion of and as directed by the STED. All information provided to offsite authorities by the Work Control Supervisor will first receive review and approval by the STED. Additional on-shift personnel assume emergency duties in the On-Shift Emergency Response Organization shown on Figure 8.1. Actions include assistance in initial emergency classification or reclassification, notification of State and NRC personnel, recommendation of offsite protective actions, and operational activities to achieve and maintain Station safety. The Seabrook Station On-Shift Staffing Analysis Report, developed in accordance with 10 CFR 50 Appendix E, Section IV, A, 9, shows that the on-shift ERO is not assigned responsibilities that would prevent the timely performance of its assigned functions as specified in the emergency plan. SSREP Figure 8.1 depicts on-shift ERO staffing. 1-8.1 SSREP Rev. 72

8.2.2 Augmented Emergency Response Organization Following classification of an emergency, the On-Shift ERO will evolve to an Augmented ERO. The composition of the Augmented ERO depends upon the emergency classification level.

1. Unusual Event Augmented Emergency Response Organization During an Unusual Event, a limited number of ERO members, shown in Figure 8.2, are notified to assist the on-shift staff with the emergency response. These individuals are referred to as Primary Responders. The STED will transfer overall management responsibility to the arriving Site Emergency Director. As part of this transfer, the Site Emergency Director will be fully briefed by the STED on the status of the Station, accident mitigation and corrective actions taken, offsite notifications and the status of the ERO.

Upon assuming command, the Site Emergency Director will notify appropriate ERO members of the transfer. Independent of the arrival of the Site Emergency Director, the Unusual Event Augmented ERO will carry out its responsibilities as outlined in the appropriate position descriptions of Appendix A. These actions are directed towards termination of emergency conditions, assessment of onsite radiological conditions, technical support, coordination of Station activities with offsite authorities (State and Federal), and provision of medical and other requested assistance. If the condition(s) that caused the Unusual Event completely clears prior to the Control Room notifying the Primary Responders, the STED may determine which, if any, of the Primary Responders need to report to the site. If not, these individuals will complete their assigned tasks on the following business day.

2. Alert, Site Area Emergency and General Emergency Augmented Emergency Response Organization Upon declaration of an Alert, Site Area Emergency, or General Emergency, there is a full augmentation of the On-Shift ERO. The fully augmented Alert, Site Area Emergency, General Emergency Augmented Emergency Response Organizations are shown on Figures 8.3 through 8.6 and Figure 8.9. The augmented emergency response organizations will carry out the responsibilities listed for the appropriate positions in Appendix A.

The Site Emergency Director will transfer command of the overall emergency response to the Response Manager. As part of this transfer, the Site Emergency Director will brief the Response Manager on Station status, accident mitigation, corrective actions taken, status of the ERO, and the protective action recommendations, if any, provided to offsite authorities. The Site Emergency Director will continue to direct all onsite response activities. 1-8.2 SSREP Rev. 72

The Response Manager position will be assumed by a member of Seabrook Station, experienced as a senior manager. This person has the authority, management ability and technical background to organize and manage response and recovery operations. The Response Manager is responsible for providing overall direction and guidance to the Site Emergency Director in the effort to return the Station to a safe condition. For Alert, Site Area Emergency, and General Emergency declarations, the Response Manager will report to the EOF and this position will remain in effect until emergency conditions and subsequent recovery activities have been terminated. The remaining Station ERO staff will report to locations identified in Appendix A and shown in Figures 8.3 through 8.6 and Figure 8.9. This may involve the relocation of some ERO staff from Unusual Event response locations to Alert, Site Area Emergency, and General Emergency response locations. 8.3 Emergency Public Information Organization The Emergency Public Information Organization is responsible for providing factual and timely information to the public regarding emergency conditions at Seabrook Station. Technical advisors in the Joint Information Center will provide information to the Emergency News Manager. JIC support will also be supplied by NextEra Corporate Communications, based out of Florida. The Corporate JIC Manager and Emergency Communications Team (ECT) will work together with the JIC personnel located at the EOF. The Corporate JIC team will provide support remotely or travel to the JIC, dependent on the severity of the emergency. The Corporate JIC Manager and the Emergency News Manager will direct the Joint Information Center organization shown in Figure 8.9, and are the primary spokespeople for the Seabrook Station ERO at the Joint Information Center. 8.4 Seabrook Station Corporate Support Seabrook Station Corporate Support is integrated into specific ERO positions. These positions respond as part of an Augmented ERO. Position descriptions are contained in Appendix A. Logistics support for emergency response personnel (e.g., transportation, communications, temporary quarters, food and water, sanitary facilities in the field, and special equipment and supplies procurement) will be arranged by the ERO staff at the Emergency Operations Facility. 8.5 Recovery Organization The emergency measures presented in this plan are actions designed to mitigate the consequences of the accident in a manner that will afford maximum protection to the public. The emergency response organization described in various sections of this plan provides the foundation for the recovery organization. The recovery organization provides the necessary capabilities to restore normal Station activity. 1-8.3 SSREP Rev. 72

The Response Manager will initiate planning for recovery at the EOF. Once the response phase of the emergency is terminated, a Recovery Manager will assume command of recovery efforts. Planning for the recovery mode of operations involves the development of general principles and goals, and an organizational capability that can be adapted to address the particular post-accident conditions. A recovery organization will be formed consisting of members of the normal station organization, the ERO and, if necessary, personnel from regional utilities, nuclear industry groups and consultants/vendors. The Response Manager is directly supported by the staff at the EOF. Expertise in the disciplines of Engineering, Operations and Quality Assurance will be available during the recovery phase. Additionally, the Seabrook Station Training Center staff will be available to evaluate and test proposed operating sequences and recovery actions using the Training Center simulator and technical resources. 8.6 Extensions of Seabrook Station Emergency Response Organization 8.6.1 Local Services Arrangements have been made for the extension of organizational capabilities for handling emergencies. These include the following:

1. Transportation of injured personnel using the Town of Seabrook Fire Department ambulance service;

2. Treatment of radioactively contaminated and injured personnel at Exeter Hospital and Wentworth-Douglass Hospital; and

3. Fire support services by the Town of Seabrook Fire Department and, if necessary, mutual aid.

Letters of agreement with participating local service organizations are maintained in Appendix D to this plan. The Seabrook Station Physical Security Plan includes a description of external organizations (LLEA) that would support response to a hostile action based event. Agreements with appropriate LLEA for this purpose are maintained by the Seabrook Station Security Department. LLEA provisions in the Physical Security Plan and supporting agreements meet the requirements of 10 CFR 50 Appendix E, IV, A, 7. 8.6.2 Federal Government Support Appropriate Federal agency resources would be made available in accordance with the National Response Framework, Nuclear/Radiological Incident Annex . This plan is activated through Station notification of the NRC. Available resources include offsite radiological assessment, under the leadership of the Department of Energy. This effort would involve manpower and equipment for extensive plume measurement, including aerial monitoring and tracking, and sampling and analysis of ingestion pathway media. The STED, Site Emergency Director and Response Manager have the authority to request Federal assistance. 1-8.4 SSREP Rev. 72

8.6.3 Private Organization Support Depending on the emergency conditions and the response needs, the Seabrook Station ERO can be augmented by personnel and equipment support arranged through the Institute of Nuclear Power Operations (INPO). The Response Manager and/or the Site Emergency Director will be responsible for the decision to request industry response through INPO. All industry organizations reporting to the Station will be required to report to Station emergency management who will specify the authorities, responsibilities and limits on the actions of these organizations. All response organizations will be required to adhere to all existing Station procedures while completing their activities. 8.7 Coordination with State Government Authorities Because of the location of Seabrook Station, the planning for and implementation of State response actions involve two states, New Hampshire and Massachusetts. The Seabrook Station Radiological Emergency Plan has been developed to provide for a coordinated response with the plans of offsite governmental agencies. Both New Hampshire and Massachusetts, as well as the localities within the plume EPZ, have prepared plans for a response to an emergency at Seabrook Station. In addition, the State of Maine, which lies within the ingestion EPZ, has the capability to carry out appropriate response actions. These plans describe their respective responsibilities, authorities, capabilities, and emergency functions. Section 7.0 of this plan describes the communications network that has been developed between Seabrook Station and these states as a means of promptly notifying appropriate authorities of Station emergency conditions. The Short Term Emergency Director notifies New Hampshire State Police and Massachusetts Emergency Management Agency using the dedicated Nuclear Alert System (NAS). This notification keys mobilization of various levels of emergency response dependent on the emergency classification. Dependent upon the emergency classification, both New Hampshire and Massachusetts would dispatch radiological health and emergency management representatives to the EOF for first-hand emergency information. The EOF Coordinator coordinates radiological accident information and its meaning with both State and Federal emergency response organizations. Government requests for non-radiological information and specifically those regarding emergency management issues will be addressed by the Response Manager. Based on accident assessment, protective measures will be recommended by Seabrook Station and implemented by each state according to actions prescribed by each state's Radiological Emergency Response Plan. The ERO Technical Liaison reviews plant technical information by telephone with offsite officials in the state emergency operations centers (EOCs). Seabrook Station technical representatives report to the New Hampshire and Massachusetts State EOCs to facilitate the review of plant information with state emergency response officials. The ERO Technical Liaison reviews plant information directly with New Hampshire and Massachusetts emergency response representatives at the Seabrook Station EOF. 1-8.5 SSREP Rev. 72

Figures 8.13 and 8.14 provide a summary of the radiological emergency responsibilities and functions assigned to various Massachusetts and New Hampshire state authorities. The Station maintains an updated copy of each state's Emergency Plan and associated implementing procedures. Information is coordinated with the Maine Emergency Management Agency by New Hampshire authorities for ingestion pathway considerations. Additional state support can be called upon from participating states in the New England Compact on Radiological Health Protection. 1-8.6 SSREP Rev. 72

9.0 EMERGENCY RESPONSE OUTLINE 9.1 Initiation Upon the recognition of abnormal Station conditions either through initiation of Emergency Operating Procedures (EOPs) or other sources of information, the condition will be classified in accordance with the method described in Section 5.0. Once an emergency is classified, the response actions are directed by Emergency Response (ER) procedures contained in the Emergency Response Manual (SSER). Procedures exist that direct the appropriate response for each of the four emergency classifications. 9.2 Activation of the Emergency Organization The Unit Supervisor is responsible for recognizing potential emergency conditions and notifying the Shift Manager. The Unit Supervisor will assume the duties and responsibilities of the Short Term Emergency Director (STED) until the Shift Manager responds to the Control Room. With an emergency declared in accordance with Procedure ER 1.1, Classification of Emergencies, the Shift Manager assumes the role of STED and ensures the activation of the Emergency Response Organization (ERO) according to Section 8.0. Upon declaration of an emergency, the STED will direct implementation of Procedure ER 1.2, Emergency Plan Activation. The STED will relinquish direction of the ERO upon the arrival and briefing of the Site Emergency Director. 9.2.1 Unusual Event Response Upon the declaration of an Unusual Event, the STED will direct the notification of Station personnel (via the Station public address system) and the Primary Responders (via a digital paging system). The Primary Responders are shown in Figure 8.2, "Augmented Emergency Response Organization (ERO)-Unusual Event" and are the supplementary personnel designated to assist the on-shift staff in an Unusual Event. Offsite emergency organizations are notified and assistance from offsite fire, medical and law enforcement organizations will be requested, as necessary. During an Unusual Event, the Site Emergency Director, Operations Technician, Health Physics Coordinator, Technical Services Coordinator and ERO Technical Liaison respond to the Control Room or Technical Support Center. The Site Emergency Director will relieve the STED of emergency response command and control duties. The Response Manager will obtain a briefing from the Site Emergency Director or Short Term Emergency Director prior to or after reporting to an appropriate onsite or offsite reporting location. The Response Manager will notify Seabrook Station executive management. The EOF Coordinator and the Emergency News Manager will obtain a briefing from the Response Manager. The Emergency News Manager reports to the Joint Information Center or an appropriate onsite or offsite location to coordinate public information needs. No Station emergency response facilities are automatically activated during an Unusual Event, although the Site Emergency Director may, at his discretion, activate any or all facilities. 1-9.1 SSREP Rev. 68

The response required as a result of this declaration varies according to the specific event, but a general summary of actions taken is described below:

1. On duty operating and selected Station personnel will assume the duties specified in Section 8.0;

2. The STED will ensure that New Hampshire State Police and Massachusetts Emergency Management Agency have been notified. In turn, the offsite warning points will notify the appropriate authorities designated in their plans;

3. The STED will ensure that the NRC has been notified and that a communication channel remains open until the condition has been terminated (unless permission is granted to establish a callback time);

4. The STED will direct the activities of the On-Shift Emergency Response Organization;

5. The STED will ensure activation of the digital paging system to initiate emergency notification;

6. The Primary Responders will respond as discussed above;

7. Should it be necessary, the Site Emergency Director would direct additional notifications by telephone to augment the existing ERO to the level required by the nature of the emergency condition;

8. If necessary, appropriate emergency medical, fire department or law enforcement agencies will be notified and requested to respond;

9. The Emergency News Manager will direct preparation of public information releases appropriate to the event; and

10. The Site Emergency Director will close out the event with a notification to offsite authorities or escalate to a more severe class.

9.2.2 Alert Response Upon the declaration of or escalation to an Alert, offsite emergency organizations are notified in accordance with Procedure ER 1.2, Emergency Plan Activation. The Station emergency response organization becomes fully activated and the following actions are taken in addition to those described in Section 9.2.1. An overview of reporting locations for site personnel is presented in Figure 9.1, Reporting Instructions for Onsite Personnel. An Augmented ERO, consisting of both Primary and Secondary Responders, is activated. This Augmented ERO is shown in Figure 8.3. Additional details regarding this organization are provided in Figures 8.4 through 8.6 and Figure 8.9. Primary Responders and Subject-to-Call Responders are personnel required to meet ERO staff augmentation goals or who should be present for activation of emergency response facilities. These responders are instructed to report to their assigned emergency facilities when their pagers are activated for an Alert or higher classification level. 1-9.2 SSREP Rev. 68

During normal work hours, Secondary Responders are notified by pager, the Station public address system, an onsite siren or security personnel. During backshifts, weekends, and holidays, Secondary Responders are notified via the automated emergency telephone notification service, a commercial computer-based callout system, which is activated by Security personnel. The Technical Support Center (TSC), Operational Support Center (OSC), Emergency Operations Facility (EOF), and the Joint Information Center (JIC) will be activated and staffed. Staffing assignments for the ERO are described in Appendix A. Seabrook Station has established the goal of activating the TSC, OSC and EOF no later than one (1) hour following the declaration of an Alert or higher emergency classification level. Primary Responder and Subject-to-Call Responder positions in each of the facilities are expected to be filled and ready to function within the one hour goal. The specific positions that are expected to be filled within the one hour goal are delineated in the operational procedures for each facility. Other Secondary Responders are expected to report to their assigned emergency facilities as soon as possible after they receive notification of an Alert or higher emergency declaration. Other Secondary Responder positions may be filled by qualified personnel who are called-in after facilities have been activated and beyond the one hour facility activation goal, but all ERO positions are expected to be filled as soon as possible following declaration of an Alert or higher emergency. Emergency plan implementing procedures provide guidance for accounting for the status of all ERO positions, for identifying any vacant positions and for calling-in qualified staff to fill vacancies. Alternative Technical Support Center and Operational Support Center are designated areas within the EOF where TSC and OSC personnel assemble for hostile action based events or other catastrophic events that prevent site access. The Assembly Area for backup emergency response organization personnel is located outside the Protected Area in the Seabrook Station Conference Center. For emergencies declared during normal working hours, this facility is activated at an Alert or Site Area Emergency or General Emergency, depending upon event meteorological and radiological conditions. The purpose for this facility is to (1) ensure that adequate manpower exists for the staffing of all emergency facilities, (2) develop a roster of available second shift personnel and (3) disseminate reporting information to second shift personnel (e.g., when and where to report). Maintenance technicians (mechanics, electricians, I&C technicians) will assemble at the Assembly Area if an Alert or higher emergency classification is declared during normal daytime working hours. Maintenance technicians working on swing or mid-shifts when an Alert or higher emergency classification is declared will report to the Operational Support Center. During outages when the station is in Mode 5 or 6, non-ERO assigned personnel working outage assignments on any shift will assemble at the Assembly Area. ERO and outage management will determine what outage personnel are needed to resume outage related work. Other personnel will be directed to leave the site. The following additional actions will be completed in the event of an Alert classification:

1. The Response Manager will report to the EOF and assume responsibility for providing overall emergency response organization direction to restore Station stability; 1-9.3 SSREP Rev. 68

2. The Massachusetts and New Hampshire state emergency response teams are alerted, and specific representatives will be dispatched to the Station EOF;

3. The EOF Coordinator will provide offsite authorities with periodic meteorological assessments and, if releases are occurring, projected dose estimates (NOTE: If radiological releases are occurring, monitoring teams will be dispatched to determine actual area dose rates);

4. Information will be coordinated, as necessary, with ANI and INPO; and

5. The Response Manager or designee will close out the event. The Site Emergency Director will either downgrade the classification or escalate it to a Site Area or General Emergency.

9.2.3 Site Area Emergency Response Upon the declaration of or escalation to a Site Area Emergency offsite emergency organizations are notified in accordance with procedure ER 1.2, Emergency Plan Activation, or if the EOF is activated, procedure ER 3.3, Emergency Operations Facility Operations. The Station emergency response organization takes the following actions in addition to those described in Sections 9.2.1 and 9.2.2.

1. Offsite monitoring teams will be dispatched from the EOF;

2. The Response Manager's staff will notify contracted service organizations, sponsor utilities and other industry resources which will be requested to render assistance, as appropriate;

3. State resources will be fully mobilized in accordance with planning arrangements set forth in Massachusetts and New Hampshire State Radiological Emergency Response Plans. Included in these planning arrangements is the activation of the Public Alert and Notification System (PANS);

4. Station conditions will be continually assessed and protective action recommendations to offsite authorities will be made on the basis of this assessment according to procedure ER 5.4, Protective Action Recommendations.

This could involve Station conditions related to the potential for radiological impact prior to the occurrence of actual releases; and

5. The Response Manager or designee will close out the event. The Site Emergency Director will either downgrade the classification or escalate it to a General Emergency.

9.2.4 General Emergency Response Upon the initial declaration of or escalation to a General Emergency, offsite emergency organizations are notified in accordance with procedure ER 1.2, Emergency Plan Activation, or, if the EOF is activated, procedure ER 3.3, Emergency Operations Facility Operations. The Station emergency response organization will promptly notify offsite authorities of the General Emergency status, informing them of accident conditions and coordinating a continuous flow of accident diagnosis and prognosis information. 1-9.4 SSREP Rev. 68

The Public Alert and Notification System (PANS) will be activated. Offsite authorities will fully activate emergency response resources and implement appropriate protective measures. These measures may be based on meteorological information, radiological dose projections or Station indications of the potential for significant releases of radioactive material. The Response Manager and the Seabrook Station ERO will evaluate Station accident parameters and indications, and will continually advise offsite authorities of the type of protective actions most appropriate to the observed situation. This would include advice on the question of shelter vs. evacuation. Additional responses taken in a General Emergency condition include activation of the NRC Incident Response Plan per NUREG-0748, Revision 4. 9.3 Emergency De-escalation, Termination and Recovery The emergency classification system defined in Section 5.0 of this plan provides the flexibility needed to both escalate or de-escalate the emergency level dependent upon the severity of the event. De-escalation criteria associated with making a transition between emergency classes will require a review of plant parameters and offsite radiological conditions in conjunction with the pre-established Emergency Action Levels (EALs). When the risk posed by the emergency is clearly decreasing or has ceased, de-escalation or closeout of the emergency is appropriate. A combination approach is used and summarized in the table below. Downgrading Closeout via Closeout via Allowed Termination Recovery Unusual Event N/A Yes No Alert Yes Yes No Site Area Emergency with no Yes Yes No long-term Station damage Site Area Emergency with Yes No Yes; may occur after long-term Station damage downgrading General Emergency Yes No Yes; may occur after downgrading After the emergency has been terminated, efforts will be focused on restoring the Station to a normal operating condition. If this is not possible, long-term decommissioning, dismantling, storage and disposal issues will be addressed. General planning guidance for recovery from emergency conditions, including reentry into affected areas of the Station, is contained in emergency response procedure ER 6.0. Termination of the emergency phase and initiation of the recovery phase will require satisfying the following criteria appropriate to the emergency condition:

1. Radiation levels of in-Station areas are stable or are decreasing with time; 1-9.5 SSREP Rev. 68

2. The reactor is shut down and criticality controls are in effect (only if reactor shutdown was required by the emergency condition);

3. The core is being adequately cooled;

4. Control has been established over containment pressure and temperature;

5. An adequate heat transfer path to an ultimate heat sink has been established;

6. Primary system pressure is under control;

7. Any fire, flooding, earthquake or similar initiating events are either under control or have ceased;

8. Releases of radioactive material to the environment are either under control or have ceased;

9. Specified corrective emergency actions have been completed and the Station is in the appropriate operating mode, and notifications are complete.

When transitioning to a recovery phase, the Response Manager and the Site Emergency Director shall perform the following actions:

1. Confer with key ERO managers to determine whether actual/potential conditions warrant entry into a recovery mode.

2. If recovery is appropriate, direct key ERO managers to confer with their respective staffs and determine whether any radiological and/or operational conditions exist which would preclude entry into a recovery mode.

3. Direct key ERO managers to develop a recovery organization and shift schedule. The organizational structure will take into account incident specifics and availability of outside support organizations.

4. Direct key recovery organization members to prepare written prioritized recovery work plans in accordance with the guidance in emergency response procedure ER 6.0.

5. Submit the recovery organization and action plans to the Site Vice President (Recovery Manager) for approval.

Prior to declaring recovery in effect, the Response Manager shall perform the following actions:

1. Review the proposed recovery organization, action plans, and the date and time for entry into the recovery mode with the following:

a. NRC personnel

b. Other federal representatives (e.g., DHS, DOE, EPA)

c. State emergency response officials.

2. Brief key ERO managers on the recovery organization, action plans, and date and time for entry into recovery mode.

1-9.6 SSREP Rev. 68

3. Direct the Emergency News Manager to issue a news release concerning entry into the recovery mode.

4. Provide recovery assistance to State authorities, as requested.

5. Direct the administrative, financial and legal support necessary for the recovery organization.

When the Site Emergency Director determines that recovery prerequisites have been met and the Response Manager declares recovery in effect, the Site Vice President becomes the Recovery Manager and assumes overall management of Seabrook Station recovery activities. The Response Manager will announce through ERO organizational and communication channels when recovery has been entered. During the recovery transition phase, the Recovery Manager will designate a Response Manager position holder as the EOF Recovery Coordinator who will remain in charge of recovery activities designated for the EOF and who will report to the Recovery Manager. Recovery activities performed at the EOF will be consistent with the principle of minimizing the offsite impact on station recovery operations. These activities may include media relations, financial and insurance related activities, and maintenance of long-term governmental and regulatory affairs. The Recovery Manager will determine when to phase out EOF support activities. This would normally be done upon completion of any required clean-up activities outside of the owner-controlled area. The Recovery Manager will designate a senior plant management position holder as the Onsite Recovery Coordinator who will be in charge of recovery activities directed at restoring the plant, to the extent possible, to pre-emergency conditions. The onsite recovery organization will originate in the TSC and will subsequently operate from a site facility designated by the Recovery Manager. The Recovery Manager will report to the Chief Nuclear Officer who will remain responsible for overall nuclear plant safety. The Chief Nuclear Officer will coordinate corporate support activities and resources with site recovery operations. 1-9.7 SSREP Rev. 68

1. NOTIFICATION METHODS LOCATION NOTIFICATION METHOD INSIDE THE PROTECTED AREA GAI-TRONICS ALARM AND PLANT ANNOUNCEMENT - ALARM MAKES A PULSATING SOUND OUTSIDE THE PROTECTED AREA SITE SIREN - THE SIREN MAKES AN ALTERNATING HI-LO SOUND WORKING ON A LAN CONNECTED PC POP-UP MESSAGE ON THE PC MONITOR SCREEN SELECTED SITE OFFICE BUILDINGS SECURITY CALL TO CERTAIN WORK AREAS - CALL RECIPIENT WILL NOTIFY CO-W0RKERS ANYWHERE ONSITE WORD-OF-MOUTH FROM ERO PERSONNEL NOTIFIED BY PAGER

2. EXPECTED RESPONSE TO NOTIFICATIONS NOTIFICATION METHOD EXPECTED RESPONSE GAI-TRONICS ALARM/ANNOUNCEMENT LISTEN TO ANNOUNCEMENT AND FOLLOW INSTRUCTIONS SITE SIREN NON-ERO PERSONNEL GO TO VEHICLES AND LEAVE THE SITE AS DIRECTED BY SECURITY POP-UP MESSAGE ON PC SCREEN FOLLOW INSTRUCTIONS PROVIDED IN POP-UP MESSAGE ON PC SCREEN SECURITY CALL TO OFFICE AREAS FOLLOW INSTRUCTIONS FROM PERSON WHO RECEIVED CALL FROM SECURITY WORD-OF-MOUTH FROM ERO MEMBER FOLLOW INSTRUCTIONS PROVIDED BY ERO MEMBER

3. REPORTING INSTRUCTIONS PERSONNEL/RESPONDER CLASS REPORTING INSTRUCTIONS ON-DUTY PRIMARY RESPONDERS* REPORT TO ASSIGNED EMERGENCY RESPONSE FACILITY**

OFF-DUTY PRIMARY RESPONDERS* REPORT TO ASSIGNED EMERGENCY RESPONSE FACILITY** SUBJECT-TO-CALL RESPONDERS REPORT TO ASSIGNED EMERGENCY RESPONSE FACILITY** REPORT TO ASSIGNED EMERGENCY RESPONSE FACILITY** SECONDARY RESPONDERS NORMAL WORKING HOURS: IF FACILITY POSITION HAS BEEN FILLED, GO TO THE ASSEMBLY AREA FOR ASSIGNMENT TO ADDITIONAL SHIFTS NON-ASSIGNED STATION PERSONNEL GO HOME OR GO TO REMOTE MONITORING AREA AS DIRECTED** SITE VISITORS LEAVE SITE OR GO TO REMOTE MONITORING AREA AS DIRECTED**

• NOT REQUIRED FOR RESPONSE MANAGER, EOF COORDINATOR AND EMERGENCY NEWS MANAGER AT UNUSUAL EVENT

  ** FOR SECURITY EVENTS, A GAI-TRONICS ANNOUNCEMENT AND ERO PAGER MESSAGE OR CODE MAY INDICATE DIFFERENT REPORTING INSTRUCTIONS.

METHOD OF NOTIFICATION AND SEABROOK STATION REPORTING INSTRUCTIONS FOR ONSITE RADIOLOGICAL EMERGENCY PERSONNEL PLAN SSREP REV. 68 Figure 9.1

10.0 EMERGENCY MEASURES 10.1 Radiological Accident Assessment Systems and Techniques The two monitored effluent pathways for accidental releases of radioactive material at Seabrook Station are the plant vent stack and the main steam lines (through the lifting of the safety relief valves or the throttling of the atmospheric steam dump valves). Each of these effluent pathways contains a monitor. The monitor responses can be correlated to the effluent radioactivity concentration. In addition to these monitored pathways, high-range containment area monitors are capable of measuring the exposure rate within the containment, which can be correlated to the radioactivity concentration within the structure. Each of the above systems may be considered as separate release pathways which can be assessed with its associated monitor. Containment leakage is also considered as a possible effluent pathway for dose assessment. The containment monitoring system consists of redundant ionization chambers and instrumentation channels with a range of 100 to 108 R/hr (gamma). The system is Class 1E qualified. A time-dependent conversion factor has been calculated which will enable conversion of the monitor's response (R/hr) to the total noble gas concentration (µCi/cc) in the containment building at a given time after shutdown assuming that the concentration within the containment is uniform. This conversion factor is calculated based on the assumption that a core equilibrium mixture of fission products exists at t=0. It should be noted, however, that the intent of this system is not to correlate this monitor response to core conditions or damage but to estimate the concentration in the containment building. The only relationship that can be readily made from this monitor to core conditions is a minimum core damage level since the amount of diluted or undiluted primary coolant leakage into the containment building may be a major unknown variable. If available, the minimum core damage level indicated by this monitor will be used as an indication of the type of fission product mixture being released through the effluent pathways. The Wide Range Gas Monitor (WRGM) is used to continuously monitor the gaseous activity released to the environment through the plant vent stack. Its monitoring range is large enough to encompass low level releases using a beta scintillation detector with a range of 4.0E-8 to 1.0E-1

    µCi/cc and two mid to high range solid-state beta/gamma detectors of 7.0E-5 to 1.0E+3 µCi/cc and 2.0E-2 to 1.0E+5 µCi/cc, respectively. The WRGM was designed and installed to minimize personnel exposure while obtaining particulate and iodine grab samples. The WRGM also calculates a release activity in µCi/sec in the range of 1.0E+2 to 1.0E+14 µCi/sec.

A backup monitor is available in the event of a WRGM failure. This monitor consists of an ionization chamber type detector, viewing a prescribed geometrical container in which the stack exit gas flows. The detector and associated remote universal digital rate meter are capable of monitoring dose rates from 0.1 mR/hr to 10,000 R/hr. The main steam line monitors consist of a G-M detector placed adjacent to each of the four (4) main steam lines (several inches) with remote readout modules. This monitor response (mR/hr) is used to estimate offsite doses. 1-10.1 SSREP Rev. 73

10.1.1 Estimation of Offsite Dose Rates Seabrook Station maintains a computerized dose projection system, utilized in the Control Room, TSC and EOF, which is capable of providing real time and forecast offsite dose estimates for actual meteorological and radiological accident conditions. The system is referred to as Raddose-V. Raddose-V uses a variable trajectory, puff advection model of dispersion to predict the position of the radioactive plume. A ground level plume is modeled. The model uses a finite cloud technique to estimate external exposure received from the plume, while the standard concentration /Q methodology is used to estimate doses received from inhalation of radioisotopes and external exposure over a four day period from material deposited on the ground. In addition, the model incorporates routines for computing deposition, as well as the current dose rate from radioactive material deposited on the ground, out to 50 miles. The Raddose-V calculation considers source term and plume decay, as well as the effects of wet and dry deposition of iodines and particulates. The model also includes predefined protective action recommendations to alert users of the program to any exceedances of the EPA-400 Protective Action Guides (PAGs). The EPA-400 PAGs used are 1 Rem TEDE and 5 Rem CDE-Thyroid. The six main tasks of the Raddose-V program are:

1. Determine the source term (release rates) of airborne radioactive material, based on current, plant-specific accident data.

2. Model the atmospheric transport and diffusion of the released material, based current, local meteorological conditions.

3. To calculate TEDE, estimate the sum of exposure from the plume, inhalation of radioisotopes, and four day exposure from material deposited on the ground.

4. Calculate committed dose equivalent (CDE) to the thyroid.

5. Estimate integrated deposition of radioactive material and corresponding dose rates from deposited material.

6. Provide dose and deposition results for both real-time and forecast periods.

Raddose-V performs all calculations in discrete 15-minute "advection time steps'. The model allows up to 200 advection steps (50 hours) to be modeled. The model requires relevant meteorological and radiological information for each time step. The program data input screens allow for direct entry of Main Plant Computer System (MPCS) meteorological and radiological parameters, or the user can enter this data manually. Raddose-V then calculates plume position, and dose and deposition information, for each step, according to the meteorological and radiological data entered. New real-time calculations are conducted every 15 minutes, based on the new position of the plume at the end of the 15 minute advection step. 1-10.2 SSREP Rev. 73

Once calculations are completed, users of the program are given the opportunity to print results following each 15 minute step. For each time step, Raddose-V calculates dose rates and integrated doses at 80 radial-grid positions within the Plume Exposure Pathway Emergency Planning Zone (EPZ). Results are also provided at 77 predetermined receptor locations. Maximum dose rates by distance, based on plume position at the end of each advection time step, are calculated for each reporting location. The model also has the ability to calculate dose rates at any user-defined receptor location by entering the position's distance and bearing from the plant. Further, the model calculates ground deposition at the 144 radial-grid receptors in the 50 mile Ingestion Pathway EPZ. These receptor locations include the same locations for which dose rates and doses are calculated in the Plume Exposure Pathway EPZ, plus receptors located at 20, 30, 40 and 50 miles at each of the sixteen (16) compass directions. TEDE and CDE-Thyroid doses are also given out to 50 miles. Raddose-V also provides the ability to project doses (using a standard 4-hour default release duration) for the present incident without affecting the calculation results of real-time doses. Forecast results are based on "avoided" dose consistent with EPA-400 philosophy. Output reports available for real-time dose assessment are also available for the forecast calculations. 10.1.2 Evaluation of Field Environmental Samples When Seabrook Station monitoring teams have determined the approximate plume centerline (i.e., maximum radiation level) in the field, they will take air samples at various intervals downwind from the station. These samples will be analyzed on a gross (beta, gamma) basis in the field and, if elevated levels are observed, returned to the EOF. At the EOF they will be referred to an appropriate laboratory facility to be analyzed to determine radionuclide concentrations. Particular attention will be directed to observed iodine concentrations. The air samples will be analyzed in a two-step process. The first step involves a field analysis of the sample which measures the gross radioactivity collected on the silver zeolite cartridge and filter paper samples using a Pancake G-M detector. Field monitoring instrumentation can detect and measure radioidine concentration in the air as low as 10-7 Ci/cc. If the sample analysis shows a relatively high amount of radioactivity, a second analysis will be performed at an appropriate laboratory facility. The sample will be delivered to a laboratory facility for gamma spectroscopic analysis with greater sensitivity. Procedure ER 5.2, Site Perimeter and Offsite Monitoring and Environmental Sampling, also describes air sampling methods. Projected thyroid committed dose equivalent (CDE) will be determined from measured I-131 concentrations by multiplying by an estimate of the duration of the exposure and a dose conversion factor. 1-10.3 SSREP Rev. 73

In addition to the measurement and evaluation of offsite direct dose rates and air samples for radioiodine, the offsite radiological impact assessment will include the identification of all principal radionuclides potentially released from the accident in all potentially significant exposure pathways. This will be accomplished through an offsite monitoring and sampling program in which environmental samples of media (water, air, soil, etc., as appropriate) will be collected and subjected to detailed radionuclide analysis. This analysis can be performed by the GEL Laboratories, Charleston, South Carolina. The radionuclide results of any such analysis would be interpreted in terms of radiation exposure to the public by the use of the comprehensive dose calculation programs available at the EOF. The results of environmental sample analyses will be evaluated in relation to US Environmental Protection Agency dose guidelines for relocation and to the US Food and Drug Administration (FDA) derived intervention levels for the radionuclides identified in FDA guidance for limiting consumption of radioactively contaminated foods. 10.1.3 Evaluation of Post Accident Samples When an emergency condition results in core damage, an in-station (e.g., containment) source term that could be subsequently released, or a release, station emergency response personnel will obtain and analyze various post accident samples. Potential sampling points include containment atmosphere, gas spaces in other plant areas, and the plant vent stack. Per the Seabrook Station Post Accident Assessment Program, archive samples of the reactor coolant system and containment sump can also be obtained and analyzed. Source-term components, including radioiodine, would be quantified and evaluated in terms of actual or potential impact. 10.1.4 Severe Accident Management Guidance Guidance for responding to severe accident conditions has been established and appropriate improvements have been implemented in accordance with Chapter 5 of NEI 91-04, Revision 1, Severe Accident Issue Closure Guidelines. Appropriate Severe Accident Management (SAM) references have been incorporated into applicable Seabrook Station emergency response (SSER) procedures. Severe accident management training requirements for TSC personnel are documented in the Emergency Preparedness Training Program Description. The Operations Training Department tracks SAM Implementor Training for Operations personnel. 10.2 Protective Action Recommendation Criteria Seabrook Station will issue protective action recommendations (PARs) based on the emergency class and several factors which vary with each emergency class. No protective actions will be recommended at the Unusual Event or Alert emergency classes. At a Site Area Emergency, PARs for beach areas may be issued based on the time of year and selected plant status indicators. At a General Emergency, PARs will be issued based on selected plant status indicators, dose projections and field monitoring results. 1-10.4 SSREP Rev. 73

Protective action recommendations have been developed using the guidance of NUREG-0654, Supplement 3, which provides an acceptable method to comply with 10CFR50, Appendix E, Section IV, paragraph 3 in the use of evacuation time estimates in the formulation of PARs for the plume exposure pathway emergency planning zone, and provides guidance for meeting planning standard 10CFR50.47(b)(10) in the development of a range of protective actions. The protective action recommendations have been coordinated with responsible State of New Hampshire and Commonwealth of Massachusetts authorities. For a General Emergency, other than a General Emergency based on a Hostile Action, Seabrook Station will at a minimum recommend (1) evacuation of towns within 2 miles of the Station, (2) evacuation of towns 5 miles downwind of the Station, (3) sheltering of the remaining towns within the EPZ, (4) evacuation of Hampton and Seabrook Beaches and (5) closure of Massachusetts beach areas. For a General Emergency based on a Hostile Action, the initial PAR will be to shelter for all EPZ towns. PARs may be expanded based on further assessments of plant and radiological conditions. For accidents that result in airborne radioactivity releases, projected dose and dose rate estimates at the site boundary and distances out to 10 miles will be issued to those offsite authorities responsible for protective action decision making. Based on offsite field monitoring results and dose projections, Seabrook Station will recommend protective actions in accordance with the criteria set forth in the EPA Protective Action Guidelines, Table 10.1. Seabrook Station will also perform ingestion pathway sampling and analysis, and assist offsite authorities in determining protective actions for the ingestion exposure pathway Emergency Planning Zone. 10.3 Radiological Exposure Control During a Station emergency, abnormally high levels of radiation and/or radioactivity may be encountered. These levels may range from slightly above those experienced during normal station operation to life-endangering levels of several hundred rem in a short period of time. Under all situations, whether it is immediate action to regain control of the emergency or for life-saving purposes, measures will be taken to minimize personnel doses from external and/or internal sources of radiation. Specific dose guidelines for entry or re-entry into areas in order to (1) remove injured persons, and (2) undertake corrective actions, are defined in Table 10.2 of the plan. The Site Emergency Director will authorize, with Health Physics Coordinator or Radiological Controls Coordinator concurrence, emergency dose guidelines consistent with these or more restrictive guidelines dependent upon emergency conditions. The Radiological Controls Coordinator will discuss the hazards involved in rescue procedures with the members of the response team prior to undertaking any health-threatening mission. Considerations to be made prior to allowing personnel to accept risks associated with rescue operations are defined in Table 10.2, Emergency Dose Limits. Dose to individuals providing other emergency functions will be consistent with the limits specified in Table 10.2 with every attempt being made to keep personnel dose as low as reasonably achievable (ALARA). 1-10.5 SSREP Rev. 73

The Health Physics Coordinator, or a designated alternate, is responsible for maintaining the emergency radiological protection programs developed for station staff and support personnel. A supply of self-reading dosimeters will be stored at the Health Physics Control Point for distribution and assignment to the Technical Support Center. An emergency tote of self-reading dosimeters is stored at the EOF to ensure immediate deployment of offsite monitoring teams with dosimetry and to support entry of offsite personnel to the site. Self-reading dosimetry readers and program software have been added to the EOF inventory to ensure dosimetry activation. Each emergency response organization member reporting to the site will be provided a Dosimeter of Legal Record (DLR) badge and a self-reading dosimeter. Dose records based upon the results of these dosimeters will be maintained at each center. This information will be cross-referenced with and replaced by DLR badge data when available. Should the station exhaust its supply of DLR badges, the station DLR vendor, Mirion Technologies (GDS) will supply DLR badges. Offsite authorities responding onsite will be provided dosimetry. 10.4 Protective Measures 10.4.1 Personnel Accountability The determination of station personnel accountability is facilitated by the use of a computer-assisted accountability system. The goal of this system is to generate an initial list of missing individuals within 30 minutes of the declaration of an Alert or higher emergency classification level. Upon declaration of an emergency and activation of station emergency alarms, station personnel assigned specific emergency responsibilities will proceed to their designated emergency center location. If an Alert or higher emergency classification level is declared, non-assigned personnel (e.g., station visitors, contractor and other station personnel) will return their dosimetry to the designated normal storage racks, if appropriate, and leave the protected area through the Guard Island. There, non-assigned personnel will receive instructions concerning station egress measures. Security will generate computer reports of personnel entering and evacuating through Guard Island. All emergency response personnel reporting to emergency centers will log in on card readers and accountability rosters associated with each center. Station security personnel will be responsible for reviewing computer results and reporting these results to the Security Shift Supervisor who, in turn, will make the final determination of station personnel accountability and report the results to the STED or Site Emergency Director. Search and rescue procedures will be implemented if any persons have been identified as missing. 10.4.2 Station Access/Egress Control Methods Under all Station emergency conditions, public address announcements, made by control room personnel, will provide emergency notification and instruction to those personnel within the Protected Area. Individuals in the balance of the owner-controlled area will be alerted by an onsite siren. Visitors or those in transit within the owner-controlled area will be advised by the most appropriate means. The complete warning and advisement process will be accomplished in a rapid manner to ensure personnel safety. 1-10.6 SSREP Rev. 73

When an Alert, Site Area Emergency or a General Emergency has been declared, all non-assigned station personnel will be directed to proceed to either the remote monitoring area for monitoring and decontamination or directly home (except during outages when the station is in Mode 5 or 6 - see Chapter 3, section 3.2). Unless directed otherwise, non-assigned personnel will use their personal vehicles to leave the site. In the event that station conditions may produce or have produced a release, traffic control measures will be established to direct unassigned personnel off site via the most appropriate exit (the North Access Road or the South Access Road). The Security Shift Supervisor will be informed by the Short Term Emergency Director or by the Site Emergency Director which access road to use for site evacuation traffic in order to minimize the potential for radiation exposure or contamination by radioactive material. If a radioactive release has occurred which might result in the contamination of Station evacuees, personnel trained in contamination monitoring techniques will proceed to the remote monitoring area to perform contamination monitoring of evacuated vehicles and personnel. All evacuating personnel will be instructed to report to the remote monitoring area to be surveyed for contamination levels. If contamination is detected, actions will be implemented that appropriately correspond to the type and degree of contamination and that are consistent with the priorities of the emergency actions and conditions underway. The Health Physics Coordinator will contact the Radiological Assistant at the EOF and report Remote Monitoring Area contamination survey results. Appropriate personnel and vehicle decontamination techniques will be used as necessary. Upon being released, station evacuees will be advised of area evacuation routes by security. Site evacuation routes are noted in Figure 10.2, Seabrook Station Evacuation Routes. Appendix C provides evacuation time estimates of the public within the plume exposure pathway EPZ and also summarizes the major evacuation routes which will be utilized if necessary. The Security Coordinator will make arrangements for station badging necessary to support incoming emergency response personnel. All incoming responders will be directed to report to the EOF where they will be briefed and provided with the necessary equipment. 10.4.3 Protective Measures for Hostile Action Based Events Operations Department Abnormal Operating Procedures (AOPs) contain specific instructions for onsite personnel within the Protected Area for hostile action based events. The AOPs are referenced in Appendix G, Section VII. The content of the instructions are specific to land based or airborne events. The protective measures prescribed by the AOPs conform to the requirements of 10 CFR 50 Appendix E, Section IV, 1. 1-10.7 SSREP Rev. 73

10.4.4 Decontamination Capability Station decontamination facilities are located in the Operational Support Center, specifically at the Radiologically Controlled Area HP Control Point. The RCA shower is available for personnel decontamination purposes. Soap, brushes, etc., are available to aid in decontamination efforts. Survey instrumentation for personnel monitoring is available here. If necessary, internal contamination can be assessed with the use of whole body count equipment (FASTSCAN) or its backup. All waste generated through the use of the decontamination facilities is collected and processed by the station liquid radwaste system. Decontamination capability exists at the EOF and at the remote monitoring area. At the remote monitoring area, initial decontamination methods will involve the use mild soap and water in conjunction with a soft brush. All radwaste generated as a result of this procedure will be disposed of by normal radwaste procedures. All personnel with detectable skin contamination will be detained for decontamination purposes; otherwise, they will be released. Radiation Protection Department procedures for personnel surveys and decontamination techniques prescribe progressive techniques for skin decontamination, including techniques applicable to removal of radioiodine contamination. The procedures and supplies for implementing them are maintained at the EOF and remote monitoring area. At both locations, personnel decontamination can be accomplished with the use of a shower station, with wash water collected into a tank and pumped to 55-gallon drums that shall be transferred for processing onsite. If required, vehicle decontamination will be accomplished via dry decontamination methods. 10.4.5 Use of Onsite Protective Equipment and Supplies The station supplies of personnel radiation protection equipment will be used as necessary to support the emergency response effort. Respiratory protection equipment, protective clothing, and potassium iodide will be assigned to the onsite emergency response organization members in accordance with Procedure ER 4.3, Radiation Protection During Emergency Conditions. Respiratory protection qualifications for personnel assigned to OSC positions, Offsite Monitoring Team positions, On-shift Electricians, On-shift Mechanics, and On-shift I&C Technicians will be tracked by Emergency Preparedness. Respiratory protection qualifications for Plant Engineering engineers who could be assigned to corrective action teams will be tracked by Plant Engineering. Radiological monitoring equipment will be stocked and available for use at established emergency centers. Seabrook Station documents containing detailed lists of dedicated equipment available to support radiological emergency response efforts are referenced in Appendix F. 10.4.6 Radiation Guideline Action Levels Radiation guideline action levels for emergency center habitability are shown on Tables 10.1 and 10.3. These tables describe the actions of station staff in response to a range of station radiological conditions. 1-10.8 SSREP Rev. 73

10.5 Aid to Affected Personnel 10.5.1 Medical Treatment Station medical facilities are provided in the first aid station located in proximity to the Radiologically Controlled Area HP Control Point. Seabrook Station also maintains a site medical office located in the Operations Support Building. The first aid station and medical office are equipped and supplied to implement the requirements of the Medical Program. (Protected: Ref. NRC IR 85-32[10]) Specific station personnel have been trained as Emergency Medical Technicians (EMTs). One Emergency Medical Technician, supplemented by at least one additional individual trained in first aid and cardio-pulmonary resuscitation, will be on site at any one time to provide 24-hour emergency response coverage. 10.5.2 Medical Transportation Arrangements have been made with Exeter Hospital to provide care for contaminated injured patients. In addition, Wentworth-Douglass Hospital located in Dover, NH, will provide care for these individuals on a backup basis. Both hospitals participate in medical emergency drills as a portion of emergency plan training. The Seabrook Fire Department ambulance will be used for medical transportation of injured and contaminated personnel. The ambulance is capable of radio communications with the hospital while en route with a patient. (Protected: Ref. NRC IR 85-32[12]) Ambulance personnel are provided with specific training by Seabrook Station staff on the radiation protection considerations associated with radiologically contaminated personnel. 1-10.9 SSREP Rev. 73

Table 10.1 EPA Protective Action Guidelines Applicable to Seabrook Station Protective Action Recommendation Procedures PAG PROTECTIVE ACTION COMMENTS 1 rem TEDEa Evacuation Evacuation of the general public should be initiated at 1 rem. 5 rem CDEb - thyroid Evacuation Evacuation of the general public should be initiated at 5 rem. Potential State Considerations PAG PROTECTIVE ACTION COMMENTS 5 rem TEDE Evacuation Special situations include severe weather, competing disasters, evacuation impediments or institutionalized persons not readily mobile. 25 rem CDE - thyroid Evacuation Special situations include severe weather, competing disasters, evacuation impediments or institutionalized persons not readily mobile. >25 rem CDE - thyroid Administer KI Offsite Emergency workers and institutionalized persons. a Total Effective Dose Equivalent - see Definitions b Committed Dose Equivalent - see Definitions 1-10.10 SSREP Rev. 73

Table 10.2 Emergency Dose Limits Dose Limita b (rem) Activity Condition 5 All activities 10 Protecting valuable property Lower dose not practicable 25 Lifesaving or protection of large Lower dose not practicable populations

    >25             Lifesaving or protection of large       Only on a voluntary basis to populations                             persons fully aware of the risks involved.

a TEDE to non-pregnant emergency workers. b Emergency dose limits for the lens of the eye and for any other organ (including skin and extremities) are three and ten times listed values, respectively. 1-10.11 SSREP Rev. 73

Table 10.3 Emergency Center Protection

1. Center habitability actions shall be as indicated on Figure 10.1.

2. The need to dispense potassium iodide (KI) tablets to emergency response personnel is based upon a projected or actual thyroid committed dose equivalent (CDE) 5 rem1. Administering KI after an uptake may limit thyroid CDE depending on time after exposure.

3. Protective clothing (lab coats, shoe covers, cotton gloves) will be required when indicated by RP survey results.

1 Based on most limiting FDA recommended threshold for pregnant and lactating women per "Guidance, Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies," U.S. Department of Health and Human Services, Food and Drug Administration, Center for Drug Evaluation and Research (CDER), November 2001. 1-10.12 SSREP Rev. 73

11.0 EMERGENCY NOTIFICATION AND PUBLIC INFORMATION 11.1 Emergency Notification Upon classification of accident conditions at the Station, the Short Term Emergency Director ensures that the New Hampshire State Police and Massachusetts Emergency Management Agency are notified. This notification is initiated within 15 minutes of emergency classification and is the initial link to the offsite governmental emergency network for the activation of offsite emergency response plans, including emergency public notification if the emergency condition warrants it. The format and contents of the initial message between the Station and the offsite warning point dispatchers are specified in notification procedures that are reviewed and agreed upon by state authorities. Having been notified through State channels, the Massachusetts Department of Public Health and the New Hampshire Division of Public Health Services will call Seabrook Station ERO and request the following information: Verification of the information provided during initial notifications A brief description of events and any prognosis When requested, additional follow-up information will be provided to State agencies. This information includes prevailing weather conditions (e.g., wind velocity, direction, atmospheric stability, precipitation, etc.), release magnitude, duration and impact, actual or projected dose rates at the Station boundary; projected dose rates at various distances from the Station (2, 5, and 10 miles), and emergency response actions underway. Follow-up reports will be provided to the state personnel when requested. 11.2 Public Notification Public alerting and notification within the Seabrook Station plume exposure pathway EPZ will be accomplished through the use of the equipment and systems described in Appendix E. 11.3 Public Information Any emergency will generate a continuous and intensive demand for up-to-date public information. This is best accomplished if each organization involved is aware of what the others are saying. Consequently, Seabrook Station has planned for the establishment of a Joint Information Center for the purpose of providing coordinated dissemination of information to the media. 1-11.1 SSREP Rev. 67

At an Unusual Event declaration, the Seabrook Station News Service staff will coordinate public information inquiries in accordance with Procedure ER 3.4, Seabrook Station News Services Operations. However, under an Alert, Site Area Emergency or General Emergency, the Joint Information Center, co-located with the EOF in Portsmouth, New Hampshire, will be activated. It will be staffed and operated by designated public information personnel from Seabrook Station in accordance with Procedure ER 3.5, Joint Information Center Operations. Personnel with nuclear expertise will be responsible for media contact and interfacing with public information representatives for the States of New Hampshire and Massachusetts, the NRC and other Federal agencies. JIC support will also be supplied by NextEra Corporate Communications, based out of Florida. The Corporate JIC Manager and Emergency Communications Team (ECT) will work together with the JIC personnel located at the EOF. The Corporate JIC team will provide support remotely or travel to the JIC, dependent on the severity of the emergency. The Corporate JIC Manager and the Emergency News Manager from Seabrook Station will manage the Joint Information Center and coordinate Joint Information Center activities with representatives from state and federal agencies at the Joint Information Center. The Emergency News Manager will be supported by technical advisors and other Joint Information Center support staff. The Joint Information Center Technical Advisor will obtain emergency information in the EOF and communicate this information to the Emergency News Manager and the Corporate JIC Manager. The Emergency News Manager and the Corporate JIC Manager will designate support staff to draft news statements, to staff record approved information on public and media information telephone lines, to monitor news media broadcasts, and to assist news media representatives present in the Joint Information Center briefing area. The Emergency News Manager and/or the Corporate JIC Manager will coordinate joint news conferences conducted by utility, state and federal personnel at the Joint Information Center. The Corporate JIC Manager and the Emergency News Manager are the primary spokespeople for the Seabrook Station ERO at the Joint Information Center. A senior company official, designated in accordance with Seabrook Station Communications policies, may support the Emergency News Manager and/or Corporate JIC Manager as a spokesperson for the company. State and federal public information personnel are provided work space and communications equipment in the Joint Information Center. Emergency information obtained from the Seabrook Station EOF and the State Emergency Operations Centers will be coordinated by utility and state personnel at the Joint Information Center. Public inquiries will be dealt with by rumor control personnel who staff designated toll-free telephone lines at the New Hampshire and the Massachusetts Emergency Operations Centers. Utility and state staff at the Joint Information Center will coordinate addressing rumor trends identified by state rumor control personnel and utility media monitoring personnel. Public information materials are available at the Joint Information Center. The materials include information on radiation, Seabrook Station operations, the Seabrook Station emergency planning zone, the emergency classification system, and other general emergency plan information. Communications staff provide public information materials to the general public upon request. Public information materials specific to emergency plans of New Hampshire and Massachusetts have been developed. The materials have been distributed to residents and made available to transients in New Hampshire and Massachusetts who are located within the plume exposure pathway Emergency Planning Zone (EPZ). Materials distributed include the following: 1-11.2 SSREP Rev. 67

Resident population: emergency information and special needs survey cards are distributed yearly to plume exposure pathway EPZ households. Beach/Transient population: signs posted at beaches, parks and state forest recreation areas Commercial establishments (restaurants, businesses, health care facilities, etc.) and schools: emergency information. Farmers, farm workers, food processors and food distributors: a brochure containing information on protection of the food chain. This brochure is made available to farmers and food processors within the ingestion exposure pathway EPZ. These materials contain facts about the emergency plans, information on potential protective actions (such as sheltering and evacuation), listings of EAS radio stations, emergency bus routes and evacuation routes, considerations for school children and persons with special needs, names and locations of reception centers and host facilities, contacts for additional information and educational material on radiation. In addition to the printed emergency plan public information materials, the states have developed broadcast messages consistent with Seabrook Station's emergency classification and protective action recommendation schemes. The messages are intended to be used as part of the Emergency Alert System to provide information to the public when needed. Communications personnel are in contact with local and regional media, respond to media inquiries, and annually coordinate a program to acquaint the news media with information concerning radiation, emergency public information procedures, general Station characteristics, the emergency classification system and other pertinent facts. 1-11.3 SSREP Rev. 67

12.0 MAINTAINING EMERGENCY PREPAREDNESS 12.1 Drills and Exercises Emergency exercises and drills shall be conducted to test and evaluate the adequacy of emergency facilities, equipment, procedures, communication channels, actions of emergency response personnel, and coordination between Seabrook Station and offsite agencies. A summary of exercises and drills, and associated elements are presented below. As used for emergency preparedness drills and exercises, "annual" means that the event shall be conducted once within a calendar year. For "semi-annual," the event shall be conducted once within the first 6 calendar months of a year and once again within the second 6 calendar months.

    "Biennial" means the event will be conducted within a two-year period.

12.1.1 Radiological Emergency Plan Exercises An exercise tests the execution of the overall Station emergency response and its integration with responding offsite organizations. In order to test and evaluate the Station emergency response, an exercise shall be conducted every two years. Consistent with the regulatory requirements for offsite exercise participation, Federal, State and local agencies shall be notified of intended exercises and their conduct shall be coordinated with offsite authorities as appropriate. 12.1.2 Emergency Plan Drills A drill is a supervised instruction period aimed at testing, developing and maintaining skills in a particular emergency response function. The frequency of drills is dependent upon the function to be tested.

1. Combined Functional Drills To ensure that adequate emergency response capabilities are maintained during the interval between biennial exercises, at least one annual drill will be conducted involving a combination of some of the principal functional areas of the onsite emergency response capabilities. The principal functional areas of emergency response include activities such as management and coordination of emergency response, accident assessment, protective action decision making, and plant system repair and corrective actions. Activation of all of the emergency response facilities will not be necessary during these drills. State and local governments within the plume exposure pathway EPZ may participate in these drills at their request.

2. Communication Drills To ensure that emergency communications equipment is operable, communication drills shall be conducted as outlined below. Included in the scope of these drills is the aspect of understanding message content. Paragraphs c, d, and g below may be performed as part of annual combined functional drills and the required biennial exercise.

a. Communication channels with State governments within the plume exposure pathway shall be tested monthly; 1-12.1 SSREP Rev. 74

b. The pager system for the notification of the Primary Responders of the Emergency Response Organization (ERO) shall be tested weekly;

c. Data transmission capability between Station emergency centers shall be tested annually;

d. EOF communications to State Emergency Operation Centers and to Station field assessment teams shall be conducted annually;

e. Communications between the Control Room and the NRC Headquarters Operations Center shall be tested weekly or as otherwise directed by the NRC;

f. Communications between the EOF, TSC and the NRC Headquarters Operations Center shall be tested monthly or as otherwise directed by the NRC; and

g. Notification of the Secondary Responders of the ERO via the automated telephone notification service shall be tested at least annually.

3. Fire Drills To evaluate the response and training of the Station fire brigade and coordination of same with offsite fire support, a number of fire drills are conducted annually.

The Town of Seabrook Fire Department shall be requested to participate in at least one drill annually. The drills shall be conducted in accordance with the Seabrook Station Fire Protection Manual (SSFP).

4. Medical Drills To evaluate the response and training of the Station medical response and offsite hospital personnel, a medical drill shall be conducted annually involving a simulated contaminated individual. Although the Station medical response may be tested more frequently, the offsite response portion of medical drills may be performed as part of the biennial exercise.

5. Radiological Monitoring Drills Plant environs and radiological monitoring drills (onsite and offsite) shall be conducted annually. These drills shall include collection and analysis of airborne sample media, communications, recordkeeping and, if feasible, interface with other offsite monitoring efforts. In addition, a drill will be conducted on the collection of other sample media (e.g., soil, water and vegetation). Radiological monitoring drills may be performed as part of a training activity, another drill or the biennial exercise.

1-12.2 SSREP Rev. 74

6. Health Physics Drills Health Physics drills shall be conducted semiannually which involve response to, and analysis of, simulated elevated airborne and liquid samples and direct radiation measurements. These drills may be performed as part of a training activity, another drill or the biennial exercise. Additionally, Chemistry personnel shall be drilled annually on obtaining and analyzing post-accident samples.

12.1.3 Drill and Exercise Scenarios The Emergency Preparedness Manager is responsible for coordinating preparation for and implementation of drills and exercises with the exception of fire and medical emergency drills. Operations Support staff are responsible for coordinating preparation for and implementation of fire and medical emergency drills. For exercises that include offsite participation, the scenario shall be submitted to FEMA for agency review in accordance with regulatory guidance. All exercise scenarios shall be submitted to the NRC prior to implementation. Within an eight-year period (beginning 1/1/2014), drill and exercise scenario content shall be varied to test all the major elements of the emergency preparedness program. These major elements correspond to the objectives presented in applicable fleet and site procedures. Within an eight-year period, one scenario shall include the states' response within the ingestion pathway EPZ. In general, the scenario shall simulate a sequence of emergency conditions that would call for the mobilization of the offsite authorities, require recommendations of offsite protective measures, and allow for evaluation of offsite plans and their integration with the Station response. The scenario shall include, as a minimum, the following:

1. Date, time period, locations and participating organizations;

2. Basic objectives and specific elements that are to be tested;

3. Guidelines and extent of play;

4. Controller instructions, and a list of controllers and evaluators;

5. A narrative summary of the exercise scenario and expected responses; and

6. Time schedule of real and simulated events.

Seabrook Station cannot commit other organizations to conduct an exercise during off-hour times. Outside organizations shall be encouraged to participate in exercises, but starting times and pre-notification for exercises have to be agreed upon by participating offsite organizations. Exercises will be conducted in different seasons of the year, to the extent practicable, depending on circumstances such as scheduled refueling outages and exercise schedules for other sites affecting the availability of NRC and FEMA evaluators. 1-12.3 SSREP Rev. 74

The exercise shall be structured with sufficient flexibility to allow free play for decision-making processes. The exercise scenario package shall describe a specific accident sequence, contain a set of input messages, and list anticipated response actions which parallel the accident sequence. The exercise controller organization shall receive instructions to recognize areas where ERO responses may deviate from anticipated responses. The exercise controller organization may (1) restrict player action if the response threatens the approved time sequence; (2) restrict player action if the response circumvents a required exercise objective; and (3) introduce "free play" items to the scenario sequence if player actions become stagnant. Exercise elements which may allow free play in the decision-making process include the following:

1. Exposure control actions;

2. Manpower augmentation actions;

3. Emergency classification actions, particularly the de-escalation process;

4. Recommendation of protective actions; and

5. Coordination and communication with offsite authorities.

12.1.4 Evaluation of Exercises To evaluate the performance of participating facility personnel and the adequacy of emergency facilities, equipment and procedures used during an exercise, the Exercise Manager shall arrange for qualified controllers and evaluators to evaluate and critique the exercise. A critique shall be conducted as soon as feasible following the conclusion of the exercise with player personnel as designated by the Exercise Manager. After the critique, the controllers and evaluators shall provide drill/exercise-related documentation and performance reports to the Drill/Exercise Manager. The Drill/Exercise Manager shall use this information to determine whether, and to what extent, drill/exercise objectives were demonstrated. The exercise documentation shall be submitted to the Emergency Preparedness Manager who shall assign responsibility and deadlines for corrective actions. Individuals assigned this responsibility shall be required to document actions taken to improve the Station's emergency preparedness. 12.1.5 Credit for Response to an Actual Emergency Demonstration of exercise or drill objectives scheduled for evaluation in accordance with Fleet EP Drill and Exercise procedures may be satisfied by the effective response and documentation of designated key ERO staff to an actual emergency. Credit will be given for this objective when the following provisions are met in response to an actual emergency.

1. The emergency required a prompt and timely response and mobilization of key ERO staff responsible for the implementation of RERP emergency functions; 1-12.4 SSREP Rev. 74

2. The emergency resulted in the establishment of communications links among responding organizations;

3. The following documentation, describing the level of response and involvement of key ERO staff to the emergency, is available:

Type of emergency; Period of response; Arrival times of responders; Communications logs; Emergency decisions made and implemented; Emergency plan resources used; and List of staff involved.

4. The event is evaluated in accordance with Emergency Preparedness Department procedures for Post Event Reviews and Evaluations to determine if the actions taken were appropriate or the response warrants implementation of future corrective measures.

12.2 Emergency Plan Training The following sections describe the various types of Emergency Plan Training. 12.2.1 Emergency Response Organization (ERO) Training for ERO personnel is conducted in accordance with the ERO Training Program Description. Changes to this document shall be reviewed to ensure that (1) they do not decrease the effectiveness of the SSREP, the SSER or Seabrook Station emergency response capabilities, and (2) when implemented, the emergency preparedness program will continue to meet the applicable standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E. (Protected: Ref. NRC Inspection Report 50-443/93-03) Major elements of the program are discussed below. Seabrook Station personnel with specific positions in the ERO shall receive training to initially qualify them for a response position. ERO assignments shall, as much as possible, parallel normal job knowledge, skills and abilities. Initial training shall consist of an overview course and other courses that are appropriate to the individual's response position. The required initial courses are specified in the ERO Training Program Description. Selected ERO members shall receive annual re-qualification training to maintain their level of emergency response knowledge. The required re-qualification training courses are also specified in the ERO Training Program Description. Re-qualification training courses are conducted throughout the year. The ERO Training Program Description contains a generic annual schedule which is used to ensure that re-qualification training occurs at about the same time period each year. Re-qualification courses may be scheduled up to three months away from the generic schedule to accommodate plant events such as outages. 1-12.5 SSREP Rev. 74

Annual re-qualification training courses shall be completed within 15 months. Training requirements are discussed in the ERO Training Program Description. Training other than that shown in the ERO Emergency Preparedness Training Program Description may be given to address specific needs. 12.2.2 Support Groups Personnel from support groups who report to Seabrook Station shall be offered training designed to aid them in performing their emergency response function, including the Town of Seabrook Fire Department. This training shall be offered annually. Support groups that do not report to Seabrook Station shall also be offered training designed to aid them in performing their emergency response function. These personnel include NH Homeland Security & Emergency Management, NH Department of Health and Human Services, Massachusetts Emergency Management Agency, Massachusetts Department of Public Health, Maine Emergency Management Agency, Wentworth-Douglass Hospital and Exeter Hospital. (Protected: Ref. NRC IR 86-18[03]) This training shall be offered annually. 12.2.3 Station Personnel with No ERO Assignment Station personnel with no ERO assignment shall be trained in their proper response to an emergency during Plant Access Training. This training shall be given on an annual basis. 12.2.4 Emergency Preparedness Department Personnel Emergency Preparedness Department personnel receive plant access training and training specific to their individual ERO assignments. In addition, the Emergency Preparedness Manager schedules personnel participation in specialized emergency planning training, participation in EP related conferences, and as technical specialists for EP audits at other sites. 12.2.5 Records Documentation of training conducted in support of emergency planning is maintained in accordance with appropriate nuclear training procedures. 12.3 Review and Updating of Plan and Procedures Independent reviews of the Seabrook Station emergency preparedness program shall be conducted every 12 months. The reviews shall include the emergency plan, its implementing procedures, training, equipment, readiness testing and State and local government planning interfaces. Management controls shall be implemented for evaluation and correction of review findings. The result of the review, along with recommendations for improvements, shall be documented and retained for a period of five years. 1-12.6 SSREP Rev. 74

Intent revisions to the SSREP and to SSER emergency plan implementing procedures ER 1.1, Classification of Emergencies; ER 1.2, Emergency Plan Activation; and ER 5.4, Protective Action Recommendations, shall be submitted to the On-Site Review Group (ORG) for review and approval before implementation. Intent revisions of other emergency plan implementing procedures contained in the SSER shall be reviewed by a station qualified reviewer per the Station Qualified Reviewer program and approved by the Emergency Preparedness Manager prior to implementation. On an annual basis, written agreements with outside support organizations and government agencies shall be evaluated to determine if such agreements are still valid. (Protected: Ref. FPL Common Letter L-2005-214) If not, then these agreements shall be renewed and updated; otherwise, the agreements shall be considered current. Telephone number listings associated with the Station emergency response facilities shall be reviewed quarterly and updated if necessary. Revisions shall be made in accordance with current regulations and guidelines on a continuing basis, as applicable. Revisions and changes to the plan and procedures shall be forwarded to all document control list recipients. (Protected: Ref. NRC IR 86-18[31]) 12.4 Maintenance and Inventory of Emergency Equipment and Supplies Emergency equipment and supplies are maintained as indicated in the Emergency Preparedness Facility Inventory Manual. Emergency portable survey instruments and dosimetry will be calibrated in accordance with applicable health physics programs and procedures. Along with requirements for calibration, the instruments shall be source-checked before each use. There are sufficient reserve instruments and equipment to replace those that are removed from emergency kits for calibration purposes. An inventory of the emergency storage locations shall be made, and discrepancies shall be noted and corrected. 12.5 Emergency Preparedness Manager The Emergency Preparedness Manager is the emergency planning coordinator with overall authority for radiological emergency response planning for Seabrook Station. The Emergency Preparedness Manager has the following responsibilities:

1. Maintain the Seabrook Station Radiological Emergency Plan (SSREP).

2. Maintain the Emergency Response Manual (SSER).

3. Ensure the conduct of drills and exercises.

4. Track identified drill and exercise deficiencies, and associated corrective action.

5. Maintain Emergency Response Organization staffing.

6. Maintain Emergency Response Organization pager assignments and publish schedules.

7. Maintain the Emergency Response Organization notification system data base.

8. Maintain the emergency response facilities as described in the Seabrook Station Radiological Emergency Plan and Emergency Response Manual.

9. Obtain and track the availability of facilities and equipment required to maintain the Seabrook Station emergency response in a continuous state of readiness.

1-12.7 SSREP Rev. 74

10. Ensure implementation of the communications and equipment test program.

12.6 Operations Training Supervisor Ensures the conduct and documentation of emergency preparedness training. 12.7 Assistant Operations Manager - Line

1. Maintains Operations Department fire response and medical emergency response procedures.

2. Ensures the conduct of fire and medical emergency response drills.

1-12.8 SSREP Rev. 74

13.0

SUMMARY

OF CHANGES Rev. 78: (PCR 2386017 June 2021) Section 6.1.4 - Removed requirement for Environmental Analyst to respond to the EOF at an Alert. Section 6.2.3.1 - Removed PSNH Electrical System Control Center as a source of meteorological information. Section 7.5.1 - Removed requirement that the mobile communications with the offsite survey teams be push-to-talk. This change was previously presented and approved at ORG (ref. ORG Meeting 21-01 AR 2355399) however the change was not included in revision 77 due to an administrative error. Section 7.5.2 - Removed reference to the Health Physics (HP) Alternate Checkpoint radio console. Figure 8.2 - Replaced SNC (Science and Nature Center) with JIC (Joint Information Center). Section 8.2.2.2 - Revised to read that the Response Manager is experienced as a senior manager vs. is a senior manager. Figure 8.4 - Removed Licensing Coordinator Position. Reduced EOF Support Staff from 4 to 2. Reduced Training Center Staff from 2 to 1. Figure 8.5 - Reduced I&C Personnel from 2 to 1. Figure 8.6 - Removed BOP Support Engineer, Electrical Support Engineer, NSSS Support Engineer, and Maintenance Coordinator. Section 9.2.1 - Revised Emergency News Managers response location to the Joint Information Center or other appropriate location. Section 11.1 - Clarified that the New Hampshire and Massachusetts departments of Public Health call the Seabrook Station ERO per the Letter of Agreement in Appendix A. Section 12.6 - Changed title Technical Training Supervisor to Operations Training Supervisor. Section 12.7 - Changed title from Operations Support Manager to Assistant Operations Manager - Line Appendix A - Removed BOP Support Engineer, Electrical Support Engineer, Maintenance Coordinator, NSSS Support Engineer, and Licensing Coordinator. Appendix G -- Replaced Emergency Preparedness Drill and Exercise Manual (EPDE) with EP-AA-101-1000, Nuclear Division Drill and Exercise Procedure. Rev. 77: (PCR 02355399 January 2021) Section 2 & Figure 9.1 - Removed reference to Red and White teams. 1-13.1 SSREP Rev. 77

Figure 6.1 - Corrected location of Emergency Operations Facility. Section 6.2.5 - Removed High Pressure Ion Chamber from the list of EOF equipment. Section 7.5.1 - Removed requirement that the mobile communications with the offsite survey teams be push-to-talk. Figure 8.16 - Revised the location of the Seabrook Station News Services from the Science and Nature Center to the Joint Information Center or as directed by the Emergency New Manager. Revised number of Technical Advisors to as needed. Section 9.2.1 - Revised to allow the Response Manager to obtain a briefing from either the Site Emergency Director or the Control Room. Section 11.3 - Replaced title of Science and Nature Center staff to Communications staff. Revised description of contact between the Seabrook Station Communications personnel with the media. Section 12.1.2.3 - Revised to request the Town of Seabrook Fire Department to participate in a drill annually. Section 12.3 - Editorial title change from SORC to ORG. Rev. 75: (PCR 02308922 and PCR 02330818 December 2019) Figure 8.9, Section 1-06.1.5, Section 1-08.3, Section 1-11.3 Revised for implementation of the Joint Information System. Reduction of JIC Technical Advisor position to 1 per shift. Reduction of JIC Support Staff to 3 per shift. Section 1-11.3 replaced the term calendar with brochure for emergency information distribution to the public. Rev. 74: (PCR 2291007 March 2019) 12.1.2.2.g replaced "RapidNotify emergency notification service" with "automated telephone notification service." Rev. 73: (PCR 02276102 September 2018) Revised sections 2 and 10 to support relocating remote monitoring area from Portsmouth to onsite. Rev. 72: (PCR 2217534 August 2017) Section 5 - Corrected footers on EAL charts. Corrected typographical error on Figure 5.7 (Category A to Category R) (AR 2217534). Section 12 - Replaced validation, exemption, and deferral are discussed in the ERO Training Program Description with training requirements are discussed in the ERO Training Program Description (AR 2194476). Appendix D - Updated Letter of Agreement with the State of New Hampshire and Commonwealth of Massachusetts. 1-13.2 SSREP Rev. 77

Rev. 71: (PCR 2191568 and PCR 2211605 July 2017) Section 5 - Editorial Change to correct footer in Figures 5.6, 5.7, and 5.8. Section 9 - Replaced Site Vice President title with Plant General Manager. Corrected typographical errors in Figure 9.1. Section 5 - Revised EAL description to match new NRC approved EAL scheme (AR 2101091). Editorial change to replace reference from NARC to LI-AA-102-1001 with regard to regulatory reporting. 1-13.3 SSREP Rev. 77

IMPLEMENT NRC UNIT SUPERVISOR INCIDENT RESPONSE NRC PLAN AS NECESSARY RECOGNIZE INCIDENT/ ~((;,, NOTIFY SHIFT MANAGER ~'\S V ((;,,~s IMPLEMENT STATE AND NH AND MA STATE p,\..E.~sYS\E.NI LOCAL EMERGENCY t-1\JCl-EJ'R WARNING POINTS RESPONSE PLANS SHIFT MANAGER PRIMARY RESPOND PER RESPONDERS PROCEDURE CLASSIFY EMERGENCY/ AUTHORIZE NOTIFICATIONS PRIMARY, SUBJECT TO CALL, AND' I ACTIVATE EMERGENCY SECONDARY ' FACILITIES RESPONDERS:

                                                             /

NOTIFICATION PLAN SEABROOK STATION RADIOLOGICAL EMERGENCY PLAN SS REP REV. 64 FIGURE 3.1

                                                                                                          ... MEMA Framingham Dispatcher is Directed to Activate Massachusetts Sirens
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and to Notify the Public Massachusetts Public Massachusetts EAS 4 Stations are Directed to Commence Broadcast of

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                                                                                                                                                                                                          ~-~.::)                                      /~:"> .,,/

D!SCHARGE TRANSITION STRUCTURE U. CONTROL BUILDING

12. DIESEL GENERATOR BUILDING

13. NON-ESSENTIAL SWITCHGEAR ROOM

  \"4. AHR SPRAY EQUIPMENT VAUL. T
                                                                                                                                                                                                .i
                                                                                                                                                                                                  /--'___<.,   ,_ *;
                                                                                                                                                                                                                                                  /(ENE
                                                                                                                                                                                                                                                  ]      ;-I

15. PRIMARY AUXILIARY 8U[L01NG

                                                                                                                                                                                                              '\t.~~::*'*,*---~~~)-~1

16. FUEL STORAGE BUILDING

17. CONDENSATE STORAGE TANK

18. EMERGENCY FEEOWATER PUMPHOUSE t9. STEAM & FEEOWATER PIPE CHASE tEAST>

20, STEAM & FEEO\JATER PIPE CHASE CWE:STI

21. PRE-ACTION VALVE BUILO[NG

22. PERSONNEL HATCH tlREA *.l"-..**:::::.L$,.J

23. TANI( FARM AREA 2"4. WASTE PROCESSING BU!LOING

25. SERVICE WATER COOi.ING TOWER

26. OEMINERALlZEO WATER STORAGE TtiNI<

w MARSH AREA

27. CONTROL BUILDING MAKEwUP AIR INTAKE

29. TRANSFORMER AREA 2q. SWITCHING STATION !SUBSTATION! E

30. FIRE PROTECTION TANl<S JI. FIRE PUMP HOUSE

32. FUEL OIL STORAGE TANI<

33. GUARD HOUSE 3"4. ABANDONED SEWAGE TREATMENT BU[LOING

35. MISCELLANEOUS NQNwQPERATIONAL BUILDINGS

36. METEORLOGICAL TOWER

37. RETAINING WALL

38. SEA\rl'ALL 3q, RIPRAP 41('1. SCIENCE & NATURE CENTER "41. FITNESS CENTER

42. PERMANENT SECURITY FENCE

43. STAGING STORAGE FACILITY

44. GENERAL OFFICE BUILDING ESE 45, CHLORINATION BUILDING

46. STEAM GENERATOR BLOWOOWN

47. OPS TRAINING CENTER

                                                                                                                                                                                                       ~-<~~::::>:::>.,
  '48. RADIATION CALIBRATION FACILITY cq. 3451CV TERMINATION AREA 5121. HYDROGEN STORAGE AREA
                                                                                                                                                                                                     ~*                                 ~--._J(.,

TOWN OF SEABROOK

51. OIL/WATER SEPo::iRATOR VAULT NO. I

52. OIL/'.IATER SEPARATOR VAULT NO. 2 DUMP/TRANSFER ST.:t.TION / c:<*<;..'i...;.

53. OIL/WATER SEPARATOR VAULT NO. 3 .-.,* I '

• 1 2*

                                                                                                                                            ,, .                                              _,,./' ,i                                          '\ 3 0

(--=-~~~'<.--'

54. WAREHOUSE NO. l/M&TE CALIBRATION FACILITY/CONFERENCE CENTER 't,'w*,

                                                                                                                                                                                       '\\ - ______ /                                                  \     '\
                                                                                                                                                                                        --~~"""

55. WAREHOUSE NO. 2

56. WAAEMOUSE NO. 3

57. EMPLOYEE ALLEGATION RESOLUTION OFFICE

                                                                                                                              -- ......                                                   '\                               i' \
                                                                                                                                                                                                                          -* I             -,,;__.-;;;
                                                                                                                                                                                                                                                *-*1 *,.,__

58. LUMBER MILL FACILITY 5q, EQUIPMENT MAINTENANCE FACILITY

60. SIREN MA[NTENANCE FACILITY

61. FIRE PROTECTION FACILITY

62. FABRICATION FACILITY ...---,_..,,,.-c

63. HIGH RCSE 6UILDING

64. TECHNICAL TRAINING CENTER ,,.,..-r--------

65. SF6 REFURBISHMENT & TEST F.:t.CILITY

66. WELD TRAINING CENTER

                                                                                                                                                                                                                                    '*                           SE

67. UNIT 2 STORAGE BUILDINGS

68. OPERATIONAL SUPPORT BUILOINC sq, OFFICE EQUIPMENT STORACE BUILDING 7IC'I, PRODUCTION WAREHOUSE

71. ASPHALT BUILOINC

72. L.USE. OIL. STORACE BUILDING

73. MAINTENANCE FACILITY 236° LEGEND SW 214° SSW 1 91 ° s 1 68° SSE 1 45° 7<4. RCA STORAGE FACILITY

75. GAS BOTTLE STOR.:t.GE FACILITY

                                                              -------WATER BOUNDARY

76. CONOENS.:t.TE POLISHER FACILITY - - ROADS & BUILDINGS

77. SUPPLEt-tENTAL EMERGENCY POWER SYSTEM ENCLOSURES

                                                              -------MARSH BOUNDARY                         SCALE
                                                              *-**-**-*- POWER LINES                                                                  SEABROOK STATION                     SITE LAYOUT

78. ORY FUEL STORAGE FAC[LITY 0 500 7q, ALTERNATE RP CHECK POINT *""*- PERMANENT SECURITY FENCE PARKING llN l'EETI

                                                                                                                        .                 RADIOLOGICAL EMERGENCY PLAN
                                                             --VEHICLE BARRIER SYSTEM IVBSI 9/18/09          EPLAN:E0!0489.DGN                                                                                                                                               SSREP REV. 58                I                  FIGURE 4.3

N NNW NNE 19,968 I 110,7831 132,0651

                                              -\ -   1.862 NW                                                                        NE 115,7061                                                                 I6,297 I WNW                                                                                                  ENE 18,747   I                                                                                           [iliJ I

E 0 I [ill] WSW ESE 117,5131 \ []ill SE [ill] 45

                                                                             -- _,'    10 Miles to EPZ Boundary SSW                            SSE 118,6351                       I3,94o I          N Resident Population Miles   Subtotal by Ring Cumulative Total 0-1                895              895 1-2              6,631            7,526 2-3             10,662          18188 3-4             10,938          29,126                       w                                              E 4-5             12,988          42,114 5-6             14,668           56,782 6-7             19,372          76,154 7-8             16,547          92,701 8-9             14,132         106,833 9-10             13,950         120,783 10 - EPZ          43,424         164,207 Total:        164,207 2010 RESIDENT POPULATION SEABROOK STATION                 WITHIN A 0-10 MILE RADIUS OF RADIOLOGICAL EMERGENCY PLAN                     SEABROOK STATION SSREP REV. 66           FIGURE 4.4

N NNW NNE l 2,243 l [ill] l 8,370 I NW NE l 3,276 l  ; I2,634 I WNW ENE o:::J ls,136 I I W. I E IIQ[QJ;m O I [1ITJ

           ,_                                                                                     -i I

I I WSW I ESE

  ~\                                                                                                    ((g]

SW '

                                                                                 ;           SE I3,221 I                                                                []ill 0
                                                                              -- _,'   10 Miies to EPZ Boundary SSW                         SSE

[ill] s 14,344 I N I1,111 I Transients Miles subtotal by Ring Cumulative Total 0-1 0 0 1-2 6,411 6,411 2-3 3,978 10,389 3-4 1,967 12,356 w E 4-5 3,610 15,966 5-6 4,217 20,183 6-7 4,794 24,977 7-8 1,131 26,108 8-9 291 26,399 9-10 149 26,548 10- EPZ 8,999 35,547 Total: 35,547 0- 2 Miles s ESTIMATED PEAK SEABROOK STATION TRANSIENT POPULATION RADIOLOGICAL EMERGENCY PLAN (0-10) MILES SSREP REV. 66 FIGURE4.6

                                 ,,I I

(

                                            ** J 10 MILE 5 MILE
                      \\~
                           \
                             \
                         ' \
                        ~\
                             ~- \
                               *-/

SEABROOK STATlON NEW HAMPSHlRE YANKEE 'PLUME EXPOSURE" SEABROOK STATION EMERGENCY PLANNING ZONE RADIOLOGICAL EMERGENCY PLANi--------.----...;._-; SSREP REV 5 flGURE 4.7

('---- ( PUBLIC SERVICE COMPANY OF NEW HAMPSHIRE SEABROOK STATION "INGESTION EXPOSURE" SEABROOK STATION - UNITS 1 & 2 EMERGENCY PLANNING ZONE FINAL SAFETY ANALYSIS REPORT * (COUNTY DESIGNATIONS) RADIOLOGICAL EMERGENCY PLAN I FIGURE 4.8

FISSION PRODUCT BARRIER DEGRADATION MATRIX Modes 1, 2, 3, and 4 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Category R- Abnormal Rad Levels/Radiological Effluent RG1 Release of gaseous radioactivity RS1 Release of gaseous radioactivity RA1 Release of gaseous or liquid RU1 Release of gaseous or liquid resulting in offsite dose > 1,000 resulting in offsite dose > 100 mrem radioactivity resulting in offsite dose radioactivity > 2 times the ODCM mrem TEDE or 5,000 mrem thyroid TEDE or 500 mrem thyroid CDE > 10 mrem TEDE or 50 mrem thyroid limits for 60 minutes CDE Op. Modes: All CDE Op. Modes: All Op. Modes: All Op. Modes: All RG2 Spent fuel pool level cannot be RS2 Spent fuel pool level at 1.5 ft. (Level 3) RA2 Significant lowering of water level RU2 UNPLANNED loss of water level restored to at least 1.5 ft. (Level 3) Op. Modes: All above, or damage to, irradiated fuel. above irradiated fuel for 60 minutes or longer. Op. Modes: All Op. Modes: All Op. Modes: All RA3 Radiation levels that IMPEDE access to equipment necessary for normal plant operations, shutdown or cooldown. Op. Modes: All Category E - Events Related to ISFSI Malfunction EU1 Damage to a loaded cask CONFINEMENT BOUNDARY Op. Mode: All Category H - Hazards and Other Conditions Affecting Plant Safety HS1 HOSTILE ACTION within the HA1 HOSTILE ACTION within the HU1 Confirmed SECURITY CONDITION PROTECTED AREA. OWNER CONTROLLED AREA or or threat. Op. Modes: All airborne attack threat within 30 Op. Modes: All minutes Op. Modes: All HU2 Seismic event greater than OBE levels. Op. Modes: All HU3 Hazardous event. Op. Modes: All HU4 FIRE potentially degrading the level of safety of the plant. Op. Modes: All HA5 Gaseous release impeding access to equipment necessary for normal plant operations, shutdown or cooldown Op. Modes: All HS6 Inability to control a key safety function HA6 Control Room evacuation resulting in from outside the Control Room transfer of plant control to alternate Op. Modes: All locations Op. Modes: All HG7 Other conditions exist which in the HS7 Other conditions exist which in the HA7 Other conditions exist which in the HU7 Other conditions exist which in the judgment of the STED/SED warrant judgment of the STED/SED warrant judgment of the STED/SED warrant judgment of the STED/SED warrant declaration of a General Emergency declaration of a Site Area Emergency declaration of an Alert declaration of an Unusual Event Op. Modes: All Op. Modes: All Op. Modes: All Op. Modes: All Category M - System Malfunction MG1 Prolonged loss of all offsite and all MS1 Loss of all offsite and all onsite AC MA1 Loss of all but one AC power source MU1 Loss of all offsite AC power onsite AC power to emergency buses power to emergency buses for 15 to emergency buses for 15 minutes capability to emergency buses for AND minutes or longer or longer 15 minutes or longer

• Restoration of at least one AC Op. Modes: 1, 2, 3, 4 Op. Modes: 1, 2, 3, 4 Op. Modes: 1, 2, 3, 4 emergency bus in less than 4 hours is not likely.

OR

• Core Cooling (C) CSF RED entry conditions met Op. Modes: 1, 2, 3, 4 MA2 UNPLANNED loss of Control Room MU2 UNPLANNED loss of Control Room indications for 15 minutes or longer indications for 15 minutes or longer with a significant transient in Op. Modes: 1, 2, 3, 4 progress.

Op. Modes: 1, 2, 3, 4 MU3 Reactor coolant activity greater than Technical Specification allowable limits Op. Modes: 1, 2, 3, 4 MU4 RCS leakage for 15 minutes or longer Op. Modes: 1, 2, 3, 4 MS5 Inability to shutdown the reactor MA5 Automatic or manual trip fails to MU5 Automatic or manual trip fails to causing a challenge to core cooling or shutdown the reactor, and shutdown the reactor RCS heat removal subsequent manual actions taken at Op. Modes: 1 Op. Modes: 1 the Main Control Board are not successful in shutting down the reactor Op. Modes: 1 MU6 Loss of all onsite or offsite communications capabilities Op. Modes: 1, 2, 3, 4 MU7 Failure to isolate containment or loss of containment pressure control Op Modes: 1, 2, 3, 4 MG8 Loss of all AC and Vital DC power MS8 Loss of all Vital DC power for sources for 15 minutes or longer 15 minutes or longer Op. Modes: 1, 2, 3, 4 Op. Modes: 1, 2, 3, 4 MA9 Hazardous event affecting a SAFETY SYSTEM needed for the current Op. Modes: 1, 2, 3, 4 Modes 1, 2, 3 and 4 Figure 5.6 SSREP Rev. 57

EMERGENCY INITIATING CONDITION MATRIX Modes 5, 6, and Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Category R - Abnormal Rad Levels/Radiological Effluent RG1 Release of gaseous radioactivity RS1 Release of gaseous radioactivity RA1 Release of gaseous or liquid RU1 Release of gaseous or liquid resulting in offsite dose > 1,000 resulting in offsite dose > 100 mrem radioactivity resulting in offsite dose radioactivity > 2 times the ODCM mrem TEDE or 5,000 mrem thyroid TEDE or 500 mrem thyroid CDE > 10 mrem TEDE or 50 mrem thyroid limits for 60 minutes CDE Op. Modes: All CDE Op. Modes: All Op. Modes: All Op. Modes: All RG2 Spent fuel pool level cannot be RS2 Spent fuel pool level at 1.5 ft. (Level 3) RA2 Significant lowering of water level RU2 UNPLANNED loss of water level restored to at least 1.5 ft. (Level 3) Op. Modes: All above, or damage to, irradiated fuel. above irradiated fuel for 60 minutes or longer. Op. Modes: All Op. Modes: All Op. Modes: All RA3 Radiation levels that IMPEDE access to equipment necessary for normal plant operations, shutdown or cooldown. Op. Modes: All Category E - Events Related to ISFSI Malfunction EU1 Damage to a loaded cask CONFINEMENT BOUNDARY Op. Mode: All Category H - Hazards and Other Conditions Affecting Plant Safety HS1 HOSTILE ACTION within the HA1 HOSTILE ACTION within the HU1 Confirmed SECURITY CONDITION PROTECTED AREA OWNER CONTROLLED AREA or or threat Op. Modes: All airborne attack threat within 30 Op. Modes: All minutes Op. Modes: All HU2 Seismic event greater than OBE levels. Op. Modes: All HU3 Hazardous event. Op. Modes: All HU4 FIRE potentially degrading the level of safety of the plant. Op. Modes: All HA5 Gaseous release impeding access to equipment necessary for normal plant operations, shutdown or cooldown Op. Modes: All HS6 Inability to control a key safety function HA6 Control Room evacuation resulting in from outside the Control Room transfer of plant control to alternate Op. Modes: All locations Op. Modes: All HG7 Other conditions exist which in the HS7 Other conditions exist which in the HA7 Other conditions exist which in the HU7 Other conditions exist which in the judgment of the STED/SED warrant judgment of the STED/SED warrant judgment of the STED/SED warrant judgment of the STED/SED warrant declaration of a General Emergency declaration of a Site Area Emergency declaration of an Alert declaration of an Unusual Event Op. Modes: All Op. Modes: All Op. Modes: All Op. Modes: All Category C - Cold Shutdown/Refueling System Malfunction CG1 Loss of reactor vessel/RCS inventory CS1 Loss of reactor vessel/RCS inventory CA1 Loss of reactor vessel/RCS inventory CU1 UNPLANNED loss of reactor affecting fuel clad integrity with affecting core decay heat removal Op. Modes: 5, 6 vessel/RCS inventory for 15 containment challenged capability minutes or longer Op. Modes: 5, 6 Op. Modes: 5, 6 Op. Modes: 5, 6 CA2 Loss of all offsite and all onsite AC CU2 Loss of all but one AC power source power to emergency buses for 15 to emergency buses for 15 minutes minutes or longer or longer Op. Modes: 5, 6, Defueled Op. Modes: 5, 6, Defueled CA3 Inability to maintain the plant in cold CU3 UNPLANNED increase in RCS shutdown temperature. Op. Modes: 5, 6 OR Loss of ALL RCS temperature and reactor vessel/RCS level indication for 15 minutes or longer Op. Modes: 5, 6 CU4 Loss of Vital DC power for 15 minutes or longer Op. Modes: 5, 6 CU5 Loss of all onsite or offsite communications capabilities Op. Modes: 5, 6, Defueled CA6 Hazardous event affecting a SAFETY SYSTEM needed for the current operating mode Op. Modes: 5, 6 Modes 5, 6, and Defueled Figure 5.7 SSREP Rev. 57

FISSION PRODUCT BARRIER DEGRADATION MATRIX Modes 1, 2, 3, and 4 Fuel Clad Barrier Reactor Coolant System Barrier Containment Barrier Sub-Category Loss Potential Loss Loss Potential Loss Loss Potential Loss Core Cooling (C) ORANGE entry conditions RCS Integrity (P) RED entry conditions met Core Cooling (C) RED entry conditions met for 15 minutes or longer met with RCS press > 300 psig. Core Cooling (C) RED entry conditions met. OR

1. CSF Status OR OR (Note 1) Containment (Z) CSF - RED entry conditions Heat Sink (H) RED entry conditions met. Heat Sink (H) RED entry conditions met. met.

(Note 1) (Note 1) (Note 1) RCS activity > 300 uCi/gm Dose Equivalent I-131 (as determined per Procedure

2. RCS Activity CS0925.01, Reactor Coolant Post Accident Sampling)

Operation of a second charging pump in the An automatic or manual SI actuation is normal charging mode is required by EITHER required by EITHER of the following: of the following: Indications of RCS leakage outside of

3. RCS Leakage 1. UNISOLABLE RCS leakage

1. UNISOLABLE RCS leakage containment.

OR OR

2. SG tube RUPTURE

2. SG tube leakage.

A leaking or RUPTURED SG is FAULTED

4. S/G Rupture or Fault outside of containment.

Containment isolation is required Containment H2 concentration 6% AND EITHER of the following: OR

1. Containment integrity has been lost 1. Containment pressure > 18 psig

5. Containment Integrity based on STED/SED judgment. AND OR 2. Less than one full train of Containment

2. UNISOLABLE pathway from the Building Spray (CBS) is operating per containment to the environment exists. design for 15 minutes or longer

6. Containment Post-LOCA Radiation Monitors Post-LOCA Radiation Monitors Post-LOCA Radiation Monitors Radiation Monitor RM-6576A-1 or RM-6576B-1 95 R/hr RM-6576A-1 or RM-6576B-1 16 R/hr RM-6576A-1 or RM-6576B-1 1,305 R/hr Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED Any condition in the opinion of the STED/SED

7. STED/SED Judgment that indicates a Potential Loss of the Fuel Clad that indicates a Potential Loss of the RCS that indicates a Loss of the Containment that indicates a Potential Loss of the that indicates a Loss of the Fuel Clad Barrier. that indicates a Loss of the RCS Barrier.

Barrier. Barrier. Barrier. Containment Barrier. Barrier Status General Emergency Alert Site Area Emergency FG1 - Loss of ANY Two Barriers AND Loss FA1 - ANY Loss or Potential Loss FS1 - Loss or Potential Loss of ANY Two Barriers or Potential Loss of Third Barrier of EITHER Fuel Clad or RCS Barriers Fuel Clad Loss Enter Fuel Clad Potential Loss Enter RCS Loss Enter RCS Potential Loss Enter Containment Loss Enter Containment Potential Loss Enter Emergency Classification GE GE GE GE SAE SAE SAE SAE SAE SAE SAE SAE SAE SAE SAE SAE ALERT ALERT ALERT ALERT NOTE 1: Refer to ER 1.1, Section 1.1, Discussion concerning the proper use of CSFSTs as EALs Figure 5.8 SSREP Rev. 57

06122120 Maine State EOG~ (Augusta) Carroll ~ ~umber/and Grafton 1'11

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          -{           \_.   - - \ State EOC 1                        \ rconcordJ I                         \--"""\..... J I                                    V\..J I                                          \   Rockingham L,                                     \,....
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                                          ~

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                                                             ~                \

Note: Areas designated by County T!tle EPLAN:E010163.DGN LOCATION OF EMERGENCY SEABROOK STATION OPERATION CENTERS AROUND THE RADIOLOGICAL EMERGENCY PLAN SEABROOK STATION SITE SSREP REV. 57 FIGURE 6.1

,--,-----r---------------------------------=

                                           ~

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                                   ====:===='-===.=                          MONITORS MEN'S CLEAN _

LOCKER ROOM WHOLE BODY ALARA AREA - COUHT ROOM

        *DSC ORGANIZATION BOARD EOUJPHENT LDC IC ER ONE EOUIPMENT LOCKER NOT DEPICTED ON THE                              CHEMISTRY HOT LAB DIAGRAM IS LOCATED IN THE OECON SHOWER AREA.                                                  NOT'E: LAYOUT IS TYPICAL

• NEED TO REMOVE TOP COYER BOARD EPLAN\E010003.0GN 5/4/04

            .-~~----------~~----r-----------~~~---1 OPERATIONAL SUPPORT CENTER SEABROOK STATION            ,,....                  LAYOUT RADIOLOGICAL EMERGENCY PLAN SSREP REV. 47       FIGUREG.5

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Seabrook Station EOFLAYOUT Plan SSREP Rev. 64 Figure 6.6 f _p ~ *tF ¥

Notes: (1) SEE STATE RESPONSE PLAN FOR DESCRIPTION OF COMMUNICATION OTHER STATE AGENCIES CHANNELS NOTE (1) (NOTE2)

                                                                        ----0**1 HEALTH DEPT (2) SEE STATE RESPONSE PLAN FOR LOCALS AND OTHER STATE AGENCIES TO                                                                                        EMERG~NCY TEAM CHIEFS BE NOTIFIED.

MAINE EMERGENCY NEW HAMPSHIRE MANAGEMENT NOTE {1) STATE POLICE _ _ _ __,___ __,EMERGENCY NOTE(1) , ~ I ... 1 DISPATCHER MANAGEMENT \GOVERNOR I IL+-1' OTHER STATE

• AGENCIES (NOTE2)

NOTE (1) i ROCKINGHAM ... 1LOCAL COMMUNITIES (NOTE 2)

                                                                                                                       ~*--~*-------~*

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                                                                        '---~~1 COUNTY       -1
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1 HEALTH DEPT l NOTE (1) *

                                                                                                                   ... OTHER ~TATE AGENCIES

___j (NOTE 2)

                                                                                                                       ~---'-------_]

LEGEND: iMASSACHUSETTS (P) PRIMARY EMERGENCY NOTE(1) EMERGENCY NOTE (1) IOTHER $TATE AGENCIES (B) BACKUP . MANAGEMENT '--------+----__..,..!MANAGEMENT (NOTE2) ~NUCLEAR ALERT SYSTEM I AGENCY I DISPATCHER _ ___,..,._ 800 mHz RADIO NOTE (1)

                                                                        '--                                            ILOCAL GOMMUNITIES (NOTE 2)

NOTE: commercial telephone is available as additional backup notification method. Seabrook Station EMERGENCY NOTIFICATION Radiological Emergency Plan SSREP Rev. 64 Fie:ure 7.1

Notes: (1) SEE STATE RESPONSE PLANS FOR COMMUNICATION CHANNELS BETWEEN r-**-- STATE EOC'S AND FORWARD EOC'S 1 COMMONWEALTH OF

                                                                                          - I      MASSACHUSETTS I

I EMERGENCY OPERATIONS CENTER (EOC) INDUSTRY 'II ORGANIZATIONS , I

                                          ~,    FEDERAL AGENCIES (FEMA - DOE - ETC.

II y EMERGENCY I [

                                                           ~                          I OPERATIONS FACILITY (EOF)   l i            *-*-------

I(B) I NOTE (1) STATE OF I i LEGEND: NEW HAMPSHIRE I EMERGENCY (P) PRIMARY OPERATIONS CENTER I (B) BACKUP (EOC) I __s-+ NUCLEAR ALERT SYSTEM _ _ .,._ 800 mHz RADIO NOTE: commercial telephone is available as additional backup notification method. Seabrook Station COORDINATION CHAN~ELS WITH STATES Radiological Emergency Plan SSREP Rev. 64 I Figure 7.2

EOF Control Base CH 1 -NH-A CH 2- NH-B Tone CH 3-NH DIR Remote CH 4-MA-A CH 5-MA B

                                                                                            -------------EOF,-Portsmoulh;-NH --

l ER01 MA Portable Mobile Radio Radio r---.. ........... _........... ------*--- --~ r.. --- -- -------- ....... ------ ................ MA 1,2,3 NH-A ~~-~~--~-~~~-- 1'W MA-B

                                                      ~                  ::~:::~

ER02 8 f__-1---lr ..-*-1* Mobile Radio Primary Siren H Control Repeater A  : Control Repeater B rtable adio TX: 451.050 MHz lX: 451.675 MHz I~ ER03 T1,2,3 RX: 456.050 MHz PL: 179_9 Hz In RX: 456.675 MHz PL IN: 146.2 Hz I Mobile Radio PL: 118_6 Hz Out PL OUT; 118.8 Hz i

~i_I Kensington Kensington Tower Tower

                                                                        ' .. /  /               r-*-~:~~:J-f!+/-[:=:=i--.                                                                                                  MA-A Secondary Siren                                                         ...'

Primary Siren Control Repeater A TX: 451.675 MHz RX: 456.675 MHz PL IN: 179.9 Hz PL OUT: 118.8 Hz Pow Wow Hill Amesbury, MA ~~~~~i?i _, Pow Wow Hill,

                                                                                                                                                                                            --------------. !.'!'::~~~ .!'!.~ ---

Seabrook Station Offsite Monitoring Team Radiological Emergency Plan Radio Communications SSREP Rev 64 Figure 7.3

PUBLIC SWITCHED r------....,.------- 1 TELEPHONE I I NETWORK ~ L-~-~-~~~J I I

                    'H
                                      ~

EMERGENCY

                                                                                                          ~

SEABROOK OPERATIONS ' STATION FACILITY (EOF) i PBX; I '----~---....J r I DIESEL DIESEL I GENERATOR GENERATOR SIP PHONES VIA POINT TO POINT DARK FIBER STATION PBX Seabrook Station TELEPHONE COMMUNICATION SYSTEMS OVERVIEW Radiological Emergency Plan SSREP Rev. 64 I: Figure 7.4

UHF RADIO SYSTEM

                              \[7 CONTROL                           CONTROL
                      .. . STATroN*             ... ........ STATION I

CONTROL ROOM REMOTE

                           --~

RP CONTAINMENT II TECHNICAL SUPPORT ~----< CHECKPOINT CENTER REMOTE !i REMOTE

       -*----~---

OPERATIONS SUPPORT CENTER REMOTE UHF TRUNKED RADIO SYSTEM TRUNKING CONTROLLER, REPEATERS, AND RF MIXING EQUIPMENT TURBINE BUILDING RADIO ROOM Seabrook Station UHF Radio Communication Radiological Emergency Plan Systems Overview SSREP Rev 64 Figure 7.5

(1) SHORT TERM EMERGENCY DIRECTOR (STED) CR 1 STA QUALIFIED SENIOR REACTOR OPERATOR** CR 1 (2) CONTROL WORK CONTROL UNIT ROOM FIRE BRIGADE (3) EMT SECURITY SUPERVISOR SUPERVISOR COMMUNICATOR OS 1 CR 1 OS 5 OS 1 OS

• CR 1 CONTROL ROOM OPERATORS CR 2 NUCLEAR RADIATION (5) MAINTENANCE (5) MAINTENANCE CHEMISTRY (5) I & C SYSTEM PROTECTION MECHANIC ELECTRICIAN TECHNICIAN TECHNICIAN OPERATORS TECHNICIAN CR 2 (4) OS 1 OS 1 OS 1 OS 1 OS 1 KEY (1) Shift Manager or Unit Supervisor CR - CONTROL ROOM (2) Fire Brigade Leader or Work Control Supervisor POSITION TITLE OS - ON-SITE (3) EMT may be staffed by a Fire Brigade Member * - STAFFING PER SECURITY PLAN (4) Per Technical Specifications and the OPMM ** - IF THE STED IS NOT STA QUALIFIED (5) as available; not included in minimum staffing per Figure 8.15 LOCATION NUMBER NOTE: On-shift staffing analysis shows that the on-shift ERO is not assigned responsibilities that would prevent the timely performance of its assigned functions as specified in the SSREP.

SEABROOK STATION ON-SHIFT EMERGENCY RESPONSE ORGANIZATION RADIOLOGICAL EMERGENCY PLAN SSREP Rev. 70 Figure 8.1

RESPONSE

MANAGER

• 1 (1) SITE EMERGENCY ERO TECHNICAL EMERGENCY NEWS EOF COORDINATOR DIRECTOR LIAISON MANAGER
• 1 CR/TSC 1 TSC 1 JIC* 1 NEWS SERVICES SUPPORT STAFF FIGURE 8.16 (1) OPERATIONS (1) TECH SERVICES (1) HEALTH PHYSICS CONTROL ROOM TECHNICIAN COORDINATOR COORDINATOR PERSONNEL CR/TSC 1 CR/TSC 1 CR/TSC 1 FIGURE 8.1 KEY NOTE (1):

POSITION TITLE IF THE CONDITIONS THAT CAUSED THE UNUSUAL LOCATION NUMBER EVENT COMPLETELY CLEARS PRIOR TO PRIMARY CR - CONTROL ROOM RESPONDER NOTIFICATION, THE STED MAY TSC - TECHNICAL SUPPORT CENTER DETERMINE WHICH IF ANY OF THESE INDIVIDUALS JIC - JOINT INFORMATION CENTER NEED TO REPORT TO THE SITE.

   *     - DOES NOT REPORT TO THE SITE AUGMENTED EMERGENCY SEABROOK STATION                                        RESPONSE ORGANIZATION FOR UNUSUAL EVENT RADIOLOGICAL EMERGENCY PLAN SSREP REV. 61                   FIGURE 8.2

RESPONSE

MANAGER EOF 1 f EMERGENCY SITE EMERGENCY COMMUNICATIONS EOF STAFF DIRECTOR STAFF FIGURE 8.4 FIGURE 8.9 TSC 1 CONTROL ROOM TSC STAFF PERSONNEL FIGURE 8.6 FIGURE 8.1 OSC STAFF FIGURE 8.5 POSITION TITLE

 '-OCATION  I NUMBEF EOF - EMERGENCY OPERATIONS FACILITY TSC - TECHNICAL SUPPORT CENTER AUGMENTED EMERGENCY SEABROOK STATION                  RESPONSE ORGANIZATION FOR ALERT, SITE AREA EMERGENCY RADIOLOGICAL EMERGENCY PLAN                    AND GENERAL EMERGENCY SSREP REV. 60              FIGURE 8.3

RESPONSE

MANAGER EOF 1 ADMINISTRATIVE EMERGENCY EOF SECURITY TECHNICAL SERVICES NEWS COORDINATOR COORDINATOR ASSISTANT COORDINATOR MANAGER EOF 1 EOF 1 EOF 1 EOF 1 JIC 1 EOF SUPPORT STAFF DOSE EOF ACCESS SECURITY TRAINING TECHNICAL ASSESSMENT CONTROL EOF 2 PERSONNEL CENTER STAFF ADVISORS SPECIALIST OFFICER EOF 1 EOF 3 EOF 1 EOF 1 JIC 2 INDUSTRY LIAISON JOINT INFORMATION EOF 1 DOSE ERO CENTER HPN ASSESSMENT TECHNICAL SUPPORT COMMUNICATOR MATERIALS & PERSONNEL LIAISON STAFF LOGISTICS EOF 1 EOF 1 EOF 1 JIC 5 COORDINATOR EOF 1 RADDOSE INFORMATION OPERATOR MANAGEMENT SPECIALIST EOF 1 DOSIMETRY RECORDS ENVIRONMENTAL EOF 1 PERSONNEL ANALYSTS OFFSITE EOF 1 EOF 2 MONITORING COORDINATOR EOF 1 KEY POSITION TITLE OFFSITE OFFSITE RADIOLOGICAL MONITORING MONITORING ASSISTANT COMMUNICATOR PERSONNEL LOCATION NUMBER EOF 1 EOF 1 EOF 4 Emergency Operations Facility Staff Seabrook Station SSREP Figure 8.4 Revision 68

OSC COORDINATOR OSC 1 RADIOLOGICAL TECHNICAL WORK CONTROL CHEMISTRY CONTROLS SPECIALIST SUPERVISOR COODINATOR COORDINATOR COORDINATOR OSC 1 OSC 1 OSC 1 OSC 1 MECHANICAL RADIATION MM/MV WORK MAINTENANCE CHEMISTRY PROTECTION PLANNNER PERSONNEL TECHNICIANS TECHNICIANS OSC 1 OSC 2 OSC 2** OSC 6*

• One (1) may be the **One (1) may be the on-ELECTRICAL on-shift RP Technician shift Chemistry Technician ME/IC WORK MAINTENANCE and two 2 may be PLANNER PERSONNEL Junior RP Technicians OSC 1 OSC 2 SPECIALTY I & C PERSONNEL TECHNICAL ASSISTANTS OSC NOTE OSC 1 NOTE: Called out as needed; functions vary.

STOREKEEPER OSC 1 POSITION KEY LOCATION NUMBER CR OPERATOR - OSC OSC 1 NUCLEAR SYSTEMS OPERATORS OSC 5 OPERATIONAL SUPPORT CENTER STAFF SEABROOK STATION SSREP REV. 60 FIGURE 8.5

SITE EMERGENCY LOGKEEPER DIRECTOR TSC 1 TSC 1 TECH SERVICES HEALTH PHYSICS EMERGENCY SECURITY LEADER COORDINATOR COORDINATOR OPERATIONS MGR TSC 1 TSC 1 TSC 1 TSC 1 ENGINEERING TSC WORK OPERATIONS COORDINATOR CONTROL SUPV TECHNICIAN TSC 1 TSC 1 TSC 1 ENS COMMUNICATOR TSC 1 KEY POSITION TITLE LOCATION NUMBER TSC MECHANICAL TSC ELECTRICAL REACTOR NUCLEAR SAFETY ENGINEER ENGINEER ENGINEER ADVISOR TSC 1 TSC 1 TSC 1 TSC 1 I&C SUPPORT ENGINEER C306 1 TECHNICAL SUPPORT CENTER SEABROOK STATION (TSC) STAFF RADIOLOGICAL EMERGENCY PLAN SSREP REV. 60 FIGURE 8.6

RESPONSE MANAGER EOF 1 EMERGENCY NEWS MANAGER CORPORATE JIC MANAGER JOINT INFORMATION JOINT INFORMATION 1 1 CENTER CENTER EMERGENCY TECHNICAL ADVISORS COMMUNICATION TEAM (ECT) JIC 1 JIC Note 1 JOINT INFORMATION CENTER SUPPORT STAFF Corporate JIC Manager and ECT may work remotely or at JIC location based on severity of event. JIC 3 Note 1 - Size of ECT based on event. Reference EP-AA-100-1010 KEY POSITION TITLE LOCATION NUMBER Seabrook Station Joint Information Center Staff Radiological Emergency Plan SSREP Rev. 66 Figure 8.9

Figure 8.12 On-Shift Emergency Response Organization Actions SHIFT MANAGER RADIATION PROTECTION (Short Term Emergency Director) TECHNICIAN (respond to OSC) I. Review Station conditions and define 1. Provide radiological monitoring capability. emergency classification.

2. Assist STED with in-plant radiological

2. Notify Station personnel by Station advice.

announcement. SECURITY PERSONNEL

3. Request additional assistance, as required.

1. Activate ERO notification scheme.

4. Project consequences of potential or actual

2. Monitor personnel accountability.

airborne radioactivity releases, when applicable. 3. Provide Station access and egress control measures.

5. Notify State and NRC authorities of acciqent. FIRE BRIGADE LEADER

6. Evaluate system failures and recommend 1. Assume role of CR Communicator.

interim operating procedures/Station 2. hnplement CR Communicator Checklist modifications. responsibilities. UNIT SUPERVISOR WORK CONTROL SUPERVISOR

1. Recognize accident conditions and notify 1. Provide plan implementation assistance to Shift Manager. theSTED.

2. Command activities of Control Room staff 2. Make initial notification to offsite to restore Station to a safe operating authorities.

condition.

3. May assume role of CR Communicator if CONTROL ROOM OPERATORS Fire Brigade Leader is not available.

1. Implement appropriate procedures and MAINTENANCE PERSONNEL (respond actions to maintain reactor safety. to OSC)

2. Monitor operational parameter trends. 1. As available, perform corrective action

3. Advise Unit Supervisor of operating activities.

conditions. CHEMISTRY TECHNICIAN (respond to NUCLEAR SYSTEMS OPERATORS OSC)

l. Perform operational activities required to 1. Obtain and analyze samples, as appropriate.

maintain Station safety. 2. Assist in radiological monitoring actions.

2. Perform immediate mechanical and electrical corrective actions.

SSREP Rev. 50

EPLAN:E070089.DGN REVISED 12/02/93 KEY ....I

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Figure 8.15 Comparison of NUREG-0654 Emergency Response Staffing Goals with the Seabrook Station On-Shift Emergency Response Organization (ERO) (Sheet 1 of 6) NUREG-0654 Table B-1 Position Title On SS On-Shift Major Functional Area Major Tasks or Expertise Shift* Number On-Shift ERO Title Plant Operations and Shift Supervisor (SRO) Shift Manager Assessment of Shift Foreman (SRO) Unit Supervisor Operational Aspects Control Room Operators 2 2 Control Room Operators Auxiliary Operators 2 2 Nuclear Systems Operators Emergency Direction and Shift Technical Advisor, I** I** Shift Manager Control (Emergency Shift Supervisor or Coordinator)*** designated facility manager Notification/ Notify licensee, State, 3 Control Room Communicator, Communication**** local and Federal personnel Security Officer, Work Control and maintain communication Supervisor Radiological Accident Emergency Operations Senior Manager Assessment & Support of Facility (EOF) Director Operational Accident Offsite Dose Assessment Senior Health Physics (HP) Assessment Expertise Offsite Surveys Onsite (out-of-plant) In-plant surveys HP Technicians Radiation Protection Technician Chemistry/Radiochemistry Rad/Chem Technicians Chemistry Technician Plant System Engineering, Technical Support Shift Technical Advisor l** Shift Manager or SRO qualified to Repair and Corrective Core/Thermal Hydraulics stand shift as STA Actions Electrical (STA required in Modes 1 through 4 Mechanical only per Tech. Specs.) Repair & Corrective Actions Mechanical Maintenance/ I** I** Nuclear Systems Operator Rad Waste Operator Electrical Maintenance/ I** I** Nuclear Systems Operator Instrument & Control (l&C) Technician SSREP Rev. 55

Figure 8.15 Comparison of NUREG-0654 Emergency Response Staffing Goals with the Seabrook Station On-Shift Emergency Response Organization (ERO) (Sheet 2 of 6) NUREG-0654 Table B-1 Position Title On SS On-Shift Major Functional Area Major Tasks or Expertise Shift* Number On-Shift ERO Title Protective Actions Radiation Protection HP Technicians 2** 1** Radiation Protection Technician (In-Plant) NOTE: Functions a, c and d

a. Access Control do not require an RP Technician.

b. HP Coverage for repair, Function b can be performed by other corrective actions, onshift personnel including NSOs, search and rescue, first- Firefighter/EMTs, and Chemistry aid & firefighting Technician.

c. Personnel monitoring

d. Dosimetry Firefighting Fire Brigade Per Operations per Technical Management Specifications Manual Rescue Operations and 2** 2**

First-Aid Site Access Control and Security, firefighting Security Personnel All per Per Security Personnel Accountability communications, personnel Security Plan accountability Plan Total 10 11 Notes:

• For each unaffected nuclear unit in operation, maintain at least one shift foreman, one control room operator and one auxiliary operator except that units sharing a control room may share a shift foreman if all functions are covered.
  • May be provided by shift personnel assigned other functions.
    • Overall direction of facility response to be assumed by EOF director when all centers are fully manned. Director of minute-to-minute facility operations remain with senior manager in technical support center or control room.
      • May be performed by engineering aide to shift supervisor.

SSREP Rev. 55

Figure 8.15 Comparison of NUREG-0654 Emergency Response Staffing Goals with the Seabrook Station Augmented Emergency Response Organization (ERO) (Sheet 3 of 6) NUREG-0654 Capability for ERO Capability NUREG-0654 Table B-1 Position Title Additions for Additions On-Shift ERO Title Major Functional Area Major Tasks or Expertise 30min 30min Performing Task Plant Operations and Shift Supervisor (SRO) Assessment of Shift Foreman (SRO) Operational Aspects Control Room Operators Auxiliary Operators Emergency Direction and Shift Technical Advisor, Control (Emergency Shift Supervisor or Coordinator)*** designated facility manager Notification/ Notify licensee, State, 0 Control Room Communicator, Communication**** local and Federal personnel Security Personnel, STED and and maintain communication Work Control Supervisor Radiological Accident Emergency Operations Senior Manager 0 0 NIA Assessment & Support of Facility (EOF) Director Operational Accident Offsite Dose Assessment Senior Health Physics (HP) 0 STED or Work Control Supervisor Assessment Expertise Offsite Surveys 2 0 None Onsite (out-of-plant) HP Technicians I 0 Radiation Protection Technician, NSO Firefighter/EMT or Chemistry Technician In-plant surveys HP Technicians 1 0 Sarne as above Chemistry/Radiochemistry Rad/Chem Technicians 0 0 None Plant System Engineering, Technical Support Shift Technical Advisor Repair and Corrective Core/Thermal Hydraulics 1 0 Shift Technical Advisor Actions Electrical 0 0 NIA Mechanical 0 0 NIA Repair & Corrective Actions Mechanical Maintenance/ 0 0 NIA Rad Waste Operator Electrical Maintenance/ 1 0 None Instrument & Control 1 0 None (I&C) Technician SSREP Rev. 55

Figure 8.15 Comparison of NUREG-0654 Emergency Response Staffing Goals with the Seabrook Station Augmented Emergency Response Organization (ERO) (Sheet 4 of 6) NUREG-0654 Capability for ERO Capability NUREG-0654 Table 8-1 Position Title Additions for Additions On-Shift ERO Title Major Functional Area Major Tasks or Expertise 30 min 30 min Performing Task Protective Actions Radiation Protection HP Technicians 2 0 Radiation Protection Technician, (In-Plant) NSO, Firefighter/EMT, or Chemistry

a. Access Control Technician

b. HP Coverage for repair, corrective actions, search and rescue, first-aid & firefighting

c. Personnel monitoring

d. Dosimetry Firefighting Local Support Rescue Operations and Local Support First-Aid Site Access Control and Security, firefighting Security Personnel Personnel Accountability communications, personnel accountability Total 11 0 Notes:

• For each unaffected nuclear unit in operation, maintain at least one shift foreman, one control room operator and one auxiliary operator except that units sharing a control room may share a shift foreman if all functions are covered.
  • May be provided by shift personnel assigned other functions.
    • Overall direction of facility response to be assumed by EOF director when all centers are fully manned. Director of minute-to-minute facility operations remain with senior manager in technical support center or control room.
      • May be performed by engineering aide to shift supervisor.

SSREP Rev. 55

Figure 8.15 Comparison of NUREG-0654 Emergency Response Staffing Goals with the Seabrook Station Augmented Emergency Response Organization (ERO) (Sheet 5 of 6) NUREG-0654 Capability for ERO Capability NUREG-0654 Table B-l Position Title Additions for Additions Augmented ERO Major Functional Area Major Tasks or Expertise 60min 60min Title Plant Operations and Shift Supervisor (SRO) Assessment of Shift Foreman (SRO) Operational Aspects Control Room Operators Auxiliary Operators Emergency Direction and Shift Technical Advisor, Control (Emergency Shift Supervisor or Coordinator)*** designated facility manager Notification/ Notify licensee, State, 3 3 Site Emergency Director, Communication**** local and Federal personnel Operations Technician, and maintain communication ERO Technical Liaison Radiological Accident Emergency Operations Senior Manager 1 1 Response Manager Assessment & Support of Facility (EOF) Director Operational Accident Offsite Dose Assessment Senior Health Physics (HP) 1 1 EOF Coordinator Assessment Expertise Offsite Surveys 4 4 Offsite Monitoring Sampling Personnel (2 Monitors/2 Drivers) Onsite (out-of-plant)+ 2 2 Radiation Protection (RP) Technician /Junior RP Technician In-plant surveys + HP Technicians 2 2 RP Technician/ Junior RP Technician Chemistry/Radiochemistry Rad/Chem Technicians 1 1 Chemistry Technician Plant System Engineering, Technical Support Shift Technical Advisor Repair and Corrective Core/Thermal Hydraulics l 1 Reactor Engineer Actions Electrical 1 1 TSC Electrical Engineer Mechanical 1 I TSC Mechanical Engineer Repair & Corrective Actions Mechanical Maintenance/ 2 2 Mech. Maintenance Personnel Rad Waste Operator Electrical Maintenance/ 2 2 Elec. Maintenance Personnel Instrument & Control 1 1 I&C Personnel (I&C) Technician SSREP Rev. 55

Figure 8.15 Comparison of NUREG-0654 Emergency Response Staffing Goals with the Seabrook Station Augmented Emergency Response Organization (ERO) (Sheet 6 of 6) NUREG-0654 Capability for ERO Capability NUREG-0654 Table B-1 Position Title Additions for Additions Augmented ERO Major Functional Area Major Tasks or Expertise 60min 60 min Title Protective Actions Radiation Protection + HP Technicians 4 3 Health Physics (In-Plant) Coordinator, Radiological

a. Access Control Controls Coordinator, RP

b. HP Coverage for repair, Technicians corrective actions, Junior RP Technician search and rescue, first-aid

                                       & firefighting

c. Personnel monitoring

d. Dosimetry Firefighting Local Support Rescue Operations and Local Support First-Aid Site Access Control and Security, firefighting Security Personnel Personnel Accountability communications, personnel accountability Total 26 25 Notes:

• For each unaffected nuclear unit in operation, maintain at least one shift foreman, one control room operator and one auxiliary operator except that units sharing a control room may share a shift foreman if all functions are covered.
  • May be provided by shift personnel assigned other functions.
    • Overall direction of facility response to be assumed by EOF director when all centers are fully manned. Director of minute-to-minute facility operations remain with senior manager in technical support center or control room.
      • May be performed by engineering aide to shift supervisor.

+ Tasks may be performed by Junior Radiation Protection Technicians as directed by the Radiological Controls Coordinator. SSREP Rev. 55

EMERGENCY NEWS MANAGER JOINT INFORMATION 1 CENTER (JIC) NEWS SERVICES TECHNICAL ADVISORS SUPPORT STAFF JIC AS NEEDED JIC AS NEEDED Response may be to the Joint Information Center or as directed by the Emergency News Manager KEY POSITION TITLE LOCATION NUMBER Seabrook Station Seabrook Station News Services Staff Radiological Emergency Plan SSREP Rev. 33 Figure 8.16

1. NOTIFICATION METHODS LOCATION NOTIFICATION METHOD INSIDE THE PROTECTED AREA GAI-TRONICS ALARM AND PLANT ANNOUNCEMENT - ALARM MAKES A PULSATING SOUND OUTSIDE THE PROTECTED AREA SITE SIREN - THE SIREN MAKES AN ALTERNATING HI-LO SOUND WORKING ON A LAN CONNECTED PC POP-UP MESSAGE ON THE PC MONITOR SCREEN SELECTED SITE OFFICE BUILDINGS SECURITY CALL TO CERTAIN WORK AREAS - CALL RECIPIENT WILL NOTIFY CO-W0RKERS ANYWHERE ONSITE WORD-OF-MOUTH FROM ERO PERSONNEL NOTIFIED BY PAGER

2. EXPECTED RESPONSE TO NOTIFICATIONS NOTIFICATION METHOD EXPECTED RESPONSE GAI-TRONICS ALARM/ANNOUNCEMENT LISTEN TO ANNOUNCEMENT AND FOLLOW INSTRUCTIONS SITE SIREN NON-ERO PERSONNEL GO TO VEHICLES AND LEAVE THE SITE AS DIRECTED BY SECURITY POP-UP MESSAGE ON PC SCREEN FOLLOW INSTRUCTIONS PROVIDED IN POP-UP MESSAGE ON PC SCREEN SECURITY CALL TO OFFICE AREAS FOLLOW INSTRUCTIONS FROM PERSON WHO RECEIVED CALL FROM SECURITY WORD-OF-MOUTH FROM ERO MEMBER FOLLOW INSTRUCTIONS PROVIDED BY ERO MEMBER

3. REPORTING INSTRUCTIONS PERSONNEL/RESPONDER CLASS REPORTING INSTRUCTIONS ON-DUTY PRIMARY RESPONDERS* REPORT TO ASSIGNED EMERGENCY RESPONSE FACILITY**

OFF-DUTY PRIMARY RESPONDERS* REPORT TO ASSIGNED EMERGENCY RESPONSE FACILITY** SUBJECT-TO-CALL RESPONDERS REPORT TO ASSIGNED EMERGENCY RESPONSE FACILITY** REPORT TO ASSIGNED EMERGENCY RESPONSE FACILITY** SECONDARY RESPONDERS NORMAL WORKING HOURS: IF FACILITY POSITION HAS BEEN FILLED, GO TO THE ASSEMBLY AREA FOR ASSIGNMENT TO ADDITIONAL SHIFTS NON-ASSIGNED STATION PERSONNEL GO HOME OR GO TO REMOTE MONITORING AREA AS DIRECTED** SITE VISITORS LEAVE SITE OR GO TO REMOTE MONITORING AREA AS DIRECTED**

• NOT REQUIRED FOR RESPONSE MANAGER, EOF COORDINATOR AND EMERGENCY NEWS MANAGER AT UNUSUAL EVENT

  ** FOR SECURITY EVENTS, A GAI-TRONICS ANNOUNCEMENT AND ERO PAGER MESSAGE OR CODE MAY INDICATE DIFFERENT REPORTING INSTRUCTIONS.

METHOD OF NOTIFICATION AND SEABROOK STATION REPORTING INSTRUCTIONS FOR ONSITE RADIOLOGICAL EMERGENCY PERSONNEL PLAN SSREP REV. 68 Figure 9.1

Figure 10.1 Emergency Center Protection EVACUATE EXTERNAL 3+-~~~----l~~~~~~---+~~~~~~~~~~----t DOSE RATE (REM/HR) CONSIDER RESPIRATORS 0 100 200 300 400 500 600 700 800 900 1000 DAC - (PARTICULATE & IODINE) SSREP Rev. 30

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EVACUATION ROUTES -,. ' SEABROOK STATION RADIOLOGICAL EMERGENCY PLAN SSREP REV. 48 FIGURE 10.2

APPENDIX A EMERGENCY RESPONSE ORGANIZATION POSITION DEFINITIONS (Protected: Ref. NRC IR 85-32[15b]) SSREP Rev. 67

APPENDIX A INDEX TITLE PAGES TABLE 1 ERO ASSIGNMENT PREREQUISITES AND BACKGROUND A-1 to A-12 TABLE 2 ERO POSITION INFORMATION A-13 to A-22 Summary of Changes A-23 NOTE The prerequisites and backgrounds prescribed for ERO positions in Table 1 will apply to position holders assigned to the ERO. Under extraordinary conditions, the Emergency Preparedness Manager may make exceptions to Table 1 requirements to ensure that an emergency response organization is maintained. Exceptions to training requirements shall be processed in accordance with the requirements of the Training and Qualification Manual (NAQM). SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Administrative Services Coordinator No specific position prerequisites. Appropriate management or supervisory experience as determined by EP management. Assembly Area Coordinator No specific position prerequisites. No specific background requirement. Chemistry Coordinator Applicable Radiation Worker qualification, Chemistry Department personnel. Respiratory Protection qualification. Chemistry Technician Completed appropriate department Chemistry Technician. qualification program. Applicable Radiation Worker qualification GT1070I/GT5004C (Protected: Ref. SEP911077), Respiratory Protection qualification, GT1074J. Control Room Communicator Applicable Radiation Worker qualification. Fire Brigade Leader. Control Room Operators Licensed Reactor Operator. Applicable Individuals assigned by Operations. Radiation Worker qualification, Respiratory Protection qualification. Dose Assessment Personnel No specific position prerequisites. No specific background requirement. PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-1 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Dose Assessment Specialist Assigned from the Health Physics Personnel with appropriate technical skills Department or working knowledge of Station and experience as determined by HP HP programs (e.g., dosimetry, access management. controls) and of radiological consequence assessment (e.g., core damage, effluent pathways, release components). (Protected: Ref. NRC IR 98-03 and CR 98-1743). Electrical Maintenance Personnel Completed appropriate department Electrical Maintenance Department qualification program. Applicable Radiation personnel or Training Department Worker qualification, Respiratory Protection personnel for this discipline. qualification. Electricians Applicable Radiation Worker qualification, Station Electricians. Respiratory Protection qualification. Emergency News Manager Personnel assignments must receive Personnel with appropriate knowledge of concurrence from the Seabrook Station communications activities as determined by Communications Department. the Communications Dept. management. Emergency Operations Manager Currently licensed SRO, supervisor or higher Shift Managers or Assistant Operations (Protected: Ref. NRC IR 98-03 and CR Managers jointly assigned by Operations 98-1743). Applicable Radiation Worker and Emergency Preparedness. qualification TS1003C - Mitigation of Core Damage (Protected: Ref. NRC IR 86-18 (4) and ISEG # R8905-003). PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-2 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Engineering Coordinator Engineering background or degree, principal Routinely engaged in engineering-related engineer or past or current supervisor or activities. higher. Applicable Radiation Worker qualification, TS8072I-TS8081I (Protected: Ref. NRC IR 98-03/CR 98-1743). ENS Communicator Applicable Radiation Worker qualification. Current or past experience in Operations, Operations Training, Engineering, or Licensing. Environmental Analyst No specific position prerequisites. Background in Chemistry or Radiation Protection. EOF Access Control Personnel No specific position prerequisites. Routinely engaged in inprocessing access control activities. EOF Coordinator Knowledge of Station HP programs Personnel with appropriate technical skills (e.g., dosimetry, access controls) and and experience as determined by radiological consequence assessment Emergency Preparedness Department (e.g., core damage, effluent pathways, management. release components). EOF Support Staff No specific position prerequisites. No specific background requirement. ERO Technical Liaison Working knowledge of Seabrook Station No specific background requirement. (construction and system features). Health Physics Coordinator HP experience. Applicable Radiation Worker Present or past experience with Radiation qualification. Protection-related duties. PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-3 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND HPN Communicator No specific position prerequisites. Personnel with appropriate knowledge of nuclear power plant operations as determined by EP Department management. I&C Personnel Completed appropriate department I&C Department personnel or Training qualification program. Applicable Radiation Department personnel for this discipline. Worker qualification, Respiratory Protection qualification. I&C Support Engineer Engineering background or degree. Routinely engaged in engineering related Applicable Radiation Worker qualification. activities. I&C Technicians Applicable Radiation Worker qualification, Station I&C Technicians. Respiratory Protection qualification. Industry Liaison No specific position prerequisites. No specific background requirement. Information Management (IM) Specialist No specific position prerequisites Routinely engaged in IM related activities. Joint Information Center Support Staff No specific position prerequisites. No specific background requirement. Joint Information Center Technical Advisors Working knowledge of Seabrook Station No specific background requirement. (construction and system features). PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-4 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Junior Radiation Protection Technician Applicable Radiation Worker qualification, Experienced with or trained on Radiation Respiratory Protection qualification, Protection related duties. HP1066Z, HP1067Z, or equivalent training on RP Fundamentals. Material and Logistic Coordinator Ability to use the current corporate Routinely engaged in purchasing and purchasing system. procurement-related activities. Mechanical Maintenance Personnel Completed appropriate department Mechanical Maintenance Department qualification program. Applicable Radiation personnel or Training Department Worker qualification, Respiratory Protection personnel for this discipline. qualification. Mechanics Applicable Radiation Worker qualification, Station Mechanics. Respiratory Protection qualification. Nuclear Safety Advisor Engineering background, degree, or PRA Routinely engaged in engineering or PRA experience. Applicable Radiation Worker activities. qualification. Nuclear Systems Operator Completion of appropriate department Nuclear Systems Operator. qualifications for standing watch. Applicable Radiation Worker qualification, GT1070I/GT5004C (Protected: Ref. SEP911077), Respiratory Protection qualification. Offsite Monitoring Communicator No specific position prerequisites. No specific background requirement. PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-5 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Offsite Monitoring Coordinator No specific position prerequisites. Personnel with appropriate experience and training as determined by RP or Chemistry Department management. Offsite Monitoring/Sampling Team Personnel HP1044Z, RW1032Z or equivalent (HP Experienced with or trained on Radiation Fundamentals). Applicable Radiation Protection related duties. Worker qualification, Respiratory Protection qualification. Offsite Monitoring/Sampling Team Driver Valid driver's license. Applicable Radiation No specific background requirement. Worker qualification, Respiratory Protection qualification. Operations Technician Past or current SRO license at Seabrook Routinely engaged in operations-related Station or current licensed operator training activities, including licensed operator instructor with SRO certification at Seabrook training. Station. Applicable Radiation Worker qualification. OSC Coordinator Past or current SRO license for Seabrook Past or current Unit Supervisors jointly Station. Applicable Radiation Worker assigned by Operations and Emergency qualification, Respiratory Protection Preparedness. qualification. Raddose Operator No specific position prerequisites No specific background requirement. (Protected: Ref. NRC IR86-18 [5]). PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-6 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Radiation Protection Technician Completed appropriate department Radiation Protection. qualification program. Applicable Radiation Worker qualification, Respiratory Protection qualification, GT1074J, HP1075I. Radiological Assistant HP1044Z, RW1032Z or equivalent Experienced with or trained on Radiation (HP Fundamentals). Applicable Radiation Protection-related duties. Worker qualification. Radiological Controls Coordinator HP experience. Applicable Radiation Experienced with or trained on Radiation Worker qualification, Respiratory Protection Protection related duties. qualification. Reactor Engineer Applicable Radiation Worker qualification. Routinely engaged in reactor engineering-related activities. Response Manager TS8072I-TS8081I or past or current SRO Appropriate management or supervisory license or certification, past or current experience as determined by senior station supervisor or higher, documented management. concurrence of assignment by the Site Vice President. (Protected: Ref. NRC IR 98-03 and CR 98-1743). Security Coordinator Security Department Manager, Supervisor or Routinely engaged in security-related Senior Analyst. activities. Security Leader Security department supervisor or security Routinely engaged in security-related shift coordinator. activities. PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-7 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Security Personnel Completed appropriate department Per Security Plan qualification program per Security Plan. Applicable Radiation Worker qualification, Respiratory Protection qualification Short Term Emergency Director Licensed SRO. Applicable Radiation Worker Shift Manager, Unit Supervisor. qualification, Respiratory Protection qualification (Protected: Ref. NRC 86-18-01) PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-8 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Site Emergency Director Applicable Radiation Worker qualification, Appropriate management or supervisory TS1003C, SRO or TS8072I-TS8081I Plant experience as determined by senior station Operations Course (Protected: Ref. NRC IR management. 86-18 (4) and ISEG #R8905-003), past or current SRO license or certification, past or current supervisor or higher (Protected: Ref. NRC IR 98-03 and CR 98-1743). Specialty Technical Assistant Applicable Radiation Worker qualification. Individuals selected based on unique (Protected: Ref. NRC IR 88-09) technical knowledge, skills or abilities. Storekeeper Routinely engaged in stores-related Materials Management Department activities. Applicable Radiation Worker personnel. qualification, Respiratory Protection qualification. Technical Assistant Working knowledge of Seabrook Station Personnel with appropriate experience and (construction and system features), past or training as determined by Training Dept. current SRO license or certification, licensed management. operator training experience. (Protected: Ref. NRC IR 98-03 and CR 98-1743). PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-9 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Technical Services Coordinator Applicable Radiation Worker qualification, Personnel with appropriate knowledge and SRO or TS8072I-TS8081I Plant Operations experience as determined by the assignee's Course (Protected Ref. ISEG# R8905-003), department management with concurrence or past or current SRO license or of EP department management. certification, assigned from Engineering, Maintenance, Work Control or Outage Management (Protected: Ref. NRC IR 98-03 and CR 98-1743). Technical Specialist Coordinator Applicable Radiation Worker qualification, No specific background requirement. (Protected: Ref. NRC IR 88-09) Respiratory Protection qualification. Training Center Staff Operations Training Instructor. Operations Training Department Personnel. TSC Engineer - Electrical Applicable Radiation Worker qualification. Present or past experience with electrical engineering-related duties. TSC Engineer - Mechanical Applicable Radiation Worker qualification. Present or past experience with mechanical engineering-related duties. TSC Logkeeper Applicable Radiation Worker qualification. No specific background requirement. Work Control Supervisors Licensed SRO. Applicable Radiation Individuals assigned by Operations. Worker qualification Respiratory Protection qualification. Work Planner - Mechanical/Valve Maintenance Applicable Radiation Worker qualification. Experienced work planners assigned by the Maintenance Department. PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-10 SSREP Rev. 67

POSITION DEFINITION TABLE 1 ERO ASSIGNMENT PREREQUISITES and BACKGROUND (Protected: Ref. NRC IR 85-32 [15b]) POSITION TITLE PREREQUISITES POTENTIAL CANDIDATES BACKGROUND Work Planner - Electrical/I&C Maintenance Applicable Radiation Worker qualification. Experienced work planners assigned by the Maintenance Department. PREREQUISITE COURSE NUMBERS GT1074J = FIREHAWK SCBA Use TS8072I-TS8081I = Plant Operations Course HP 1044Z = HP Fundamentals HP1066Z = HP Fundamentals for Junior HP Technicians GT1070I = Supplemental Radiation Worker HP1075I = Response to Contaminated Injured Person HP1067Z = OSC Junior HP Technician GT5004C = WBT Supplemental Radiation Worker Requalification RW1032Z = HP Fundamentals for Radwaste TS1003C = Mitigation of Core Damage A-11 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Administrative Alert through General Emergency Response Manager Provides administrative support and obtains Services Coordinator Emergency Operations Facility additional resources to support the emergency (STC) effort. Assembly Area Alert through General Seabrook Station Administrative Coordinates operation of the Assembly Area for Coordinator (S) Emergency (normal Conference Center Services backup ERO responders and maintenance work hours only) Coordinator technicians during normal work hours. Chemistry Alert through General Operational Support OSC Coordinator Coordinates post-accident sampling and analysis Coordinator (STC) Emergency Center functions during an emergency. Chemistry Technician Alert through General Operational Support Chemistry Obtains and analyzes post-accident samples. (OS and STC) Emergency Center Coordinator Control Room Unusual Event CR Short Term Assists STED with NRC and primary responder Communicator (OS) Emergency notification. Maintains ENS communications. Director Control Room Alert through General Operational Support OSC Coordinator One is dispatched to the Control Room to staff Operators (S) Emergency Center the 4-way data link and one staffs 4-way data link in the OSC. (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-12 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Dose Assessment Alert through General Emergency Dose Assessment Provides administrative and clerical support to Personnel (S) Emergency Operations Facility Specialist the Dose Assessment Specialist. Dose Assessment Alert through General Emergency EOF Coordinator Determines projected/actual offsite dose Specialist (STC) Emergency Operations Facility conditions. Coordinates the evaluation of sample analysis data. Electrical Alert through General Operational Support OSC Coordinator Performs electrical system repair and corrective Maintenance Emergency Center action activities. Personnel (STC) Electricians (S) Staffing Based on Assembly Area/ Electrical Perform repair and corrective actions as directed Event Operational Support Maintenance by the OSC Coordinator. Center Personnel Emergency News Unusual Event Seabrook Station Site Emergency Manages the emergency public information Manager (P) through General News Service or Joint Director or function, information dissemination, media and Emergency Information Center Response Manager public relations. Coordinates emergency public information and rumor control with state and federal public information officials. Emergency Alert through General Technical Support Site Emergency Provides overall direction and coordination of Operations Manager Emergency Center Director emergency response activities performed by (S) Operations Department personnel. Engineering Alert through General Technical Support Technical Services Coordinates engineering assessment and technical Coordinator (STC) Emergency Center Coordinator support activities conducted from the TSC. Performs Severe Accident Management Evaluator functions. (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-13 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION ENS Communicator Alert through General Technical Support Operations Maintains communications with NRC. (S) Emergency Center Technician Environmental Alert Through Emergency Dose Assessment Conducts radiological analysis of environmental Analyst (S) General Emergency Operations Facility Specialist samples. EOF Access Control Alert Through Emergency Security Controls access to Emergency Operations Facility Personnel (S) General Emergency Operations Facility Coordinator EOF Coordinator (P) Unusual Event Emergency Response Manager Coordinates radiological and protective action through General Operations Facility assessments and performs state notifications from Emergency the EOF. EOF Support Staff (S) Alert through General Emergency Administrative Provides administrative and clerical support. Emergency Operations Facility Services Coordinator ERO Technical Unusual Event Control Room/ Site Emergency Notifies and interacts with the New Hampshire Liaison (P) through General Emergency Director or Public Utilities Commission, Massachusetts Emergency Operations Facility Response Manager Emergency Management Agency and Maine Emergency Management Agency staff. Health Physics Unusual Event Control Room/ Site Emergency Coordinates radiological and protective action Coordinator (P) through General Technical Support Director assessment activities conducted from the TSC. Emergency Center HPN Communicator Alert through General Emergency Dose Assessment Maintains Health Physics Network (S) Emergency Operations Facility Specialist communication with the NRC. (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-14 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION I&C Technicians (S) Staffing Based on Assembly Area/ I & C Personnel Perform repair and corrective actions as directed Event Operational Support by the OSC Coordinator. Center I&C Personnel (STC) Alert through General Operational Support OSC Coordinator Performs instrument and control system repair Emergency Center and corrective action activities. I&C Support Alert through General Technical Support Engineering Assists Engineering Coordinator in performing Engineer (S) Emergency Center Coordinator engineering assessment. Industry Liaison (S) Alert through General Emergency Admin. Services Coordinates interfaces with industry Emergency Operations Facility Coordinator organizations and Joint Owners during an emergency. Information Mgmt. Alert through General Emergency Admin. Services Performs or coordinates corrective actions as (IM) Specialist (S) Emergency Operations Facility Coordinator needed for IM equipment in emergency facilities. Joint Information Alert through General Joint Information Emergency News Assists the Emergency News Manager with Center Support Staff Emergency Center Manager performing functions of the Joint Information (S) Center. (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-15 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Joint Information Alert through General Joint Information Emergency News Obtains technical information from the EOF, Center Technical Emergency Center Manager updates Emergency News Manager, reviews Advisors (S) news statements for technical accuracy, assists with news briefings. This position may also perform the duties of the SSNS Technical Advisor for an Unusual Event. Junior Radiation Alert through General Operational Support Radiological Performs health physics tasks as assigned by the Protection Technician Emergency Center Controls Radiological Controls Coordinator. (STC) Coordinator Materials and Alert through General Emergency Administrative Provides the EOF staff with the resources Logistics Coordinator Emergency Operations Facility Services necessary to complete assignments. Assists in (S) Coordinator acquisition of resources not immediately available. Mechanical Alert through General Operational Support OSC Coordinator Performs mechanical system repair and corrective Maintenance Emergency Center action activities. Personnel (STC) Mechanics (S) Staffing Based on Assembly Area/ Mechanical Perform repair and corrective actions as directed Event Operational Support Maintenance by the OSC Coordinator. Center Personnel Nuclear Systems Alert through General Operational Support OSC Coordinator Performs operational activities directed by the Operator (S) Emergency Center TSC. (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-16 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Offsite Monitoring Alert through General Emergency Offsite Monitoring Relays messages to and from offsite monitoring Communicator (S) Emergency Operations Facility Coordinator teams and maintains a log of team locations and reported radiological data. Offsite Monitoring Alert through General Emergency Dose Assessment Coordinates offsite monitoring and sampling Coordinator (STC) Emergency Operations Facility Specialist during an emergency. Offsite Monitoring/ Alert through General Emergency Offsite Monitoring Performs emergency environmental sampling and Sampling Personnel Emergency Operations Facility Coordinator monitoring as directed by the Offsite Monitoring (HP) (STC) Coordinator. Offsite Monitoring/ Alert through General Emergency Offsite Monitoring Assists offsite monitoring/sampling personnel Sampling Personnel Emergency Operations Facility Coordinator (HP) and drives offsite monitoring/sampling (Utility) (STC) vehicle. Operations Unusual Event Control Room/ SED or Emergency Relieves the Control Room of NRC notification Technician (P) through General Technical Support Operations and communications responsibilities. Assists the Emergency Center Manager Emergency Operations Manager. Performs Severe Accident Management Evaluator functions. OSC Coordinator Alert through General Operational Support Maintenance Directs emergency response activities performed (STC) Emergency Center Coordinator at and by the OSC. Radiation Protection Alert through General Operational Support Radiological Performs onsite/in-plant surveys, provides HP Technician (OS and Emergency Center Controls coverage, implements radiological exposure STC) Coordinator controls, performs personnel monitoring/decontamination. (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-17 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Radiological Alert through General Emergency Offsite Monitoring Coordinates radiological control measures at the Assistant (S) Emergency Operations Facility Coordinator EOF. Issues dosimetry and tracks dose reporting for emergency response personnel. Radiological Controls Alert through General Operational Support OSC Coordinator Directs implementation of in-plant radiation Coordinator (STC) Emergency Center protection measures associated with Station emergency response efforts. Raddose Operator (S) Alert through General Emergency Dose Assessment Operates the Raddose-V dose assessment Emergency Operations Facility Specialist program computer Reactor Engineer Alert through General Technical Support Engineering Analyzes reactor core and plant transient (STC) Emergency Center Coordinator response. Provides core protection recommendations. Performs Severe Accident Management Evaluator functions. Response Manager Unusual Event Emergency Chief Nuclear Provides overall direction to the emergency (P) through General Operations Facility Officer response organization. Authorizes notifications Emergency and protective action recommendations to the states.* Approves news releases.* Authorizes requests for industry assistance.* Primary interface with state and federal emergency response officials.

                                                                                                                          *Responsibilities that cannot be delegated.

(Protected: Ref. NRC IR85-32 [5]) (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-18 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Security Coordinator Alert through General Emergency Response Manager Coordinates security response actions during an (S) Emergency Operations Facility (when reporting to emergency. Advises the Response Manager on (or site Incident the EOF) potential security issues pertaining to an event Command Center for such as tampering or sabotage of plant an HAB event) equipment. Security Leader (S) Alert through General Technical Support Site Emergency Coordinates security response onsite with Emergency Center Director Technical Support Center staff Security Personnel (S) Unusual Event Per Security Plan Security Implements Security Department procedures for a through General Procedures Coordinator declared radiological emergency. Emergency Short Term Unusual Event Control Room Site Emergency Makes initial emergency classification and Emergency Director through General Director notifications.* Initiates activation of the (STED) (OS) Emergency emergency response organization.* Approval of protective action recommendations to the states, reclassification of the emergency, authorization of workers to exceed 10CFR20 radiation exposure limits, and overall responsibility for directing the Station emergency response until relieved by the Site Emergency Director.*

                                                                                                                          *Responsibilities that cannot be delegated.

(Protected: Ref. NRC IR 86-18 [01]) (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-19 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Site Emergency Unusual Event Control Room/ Response Manager Relieves the STED of overall responsibility for Director (P) through General Technical Support directing the onsite emergency response.* Emergency Center Assumes responsibility for emergency classification.*Authorizes notifications and protective action recommendations to the states, approves news releases and requests industry emergency response assistance until relieved by the Response Manager.

• Authorizes workers to exceed 10CFR20 radiation exposure limits.

                                                                                                                          *Performs Severe Accident Management Decision Maker functions.
                                                                                                                          *Responsibilities that cannot be delegated.

(Protected Ref. NRC IR 86-18[01]) Specialty Technical Alert through General Technical Support Tech. Services Called in as needed to the TSC, OSC or EOF to Assistant (S) Emergency Center, Operational Coord., Tech. provide specific skills, knowledge and expertise Support Center or Specialist Coord. required during an emergency. Emergency or Admin Services Operations Facility Coord. Storekeeper (S) Alert through General Operational Support OSC Coordinator Issues tools and equipment to emergency repair Emergency Center and corrective action teams. Technical Assistant Alert through General Emergency Response Manager Coordinates technical assessment and support (STC) Emergency Operations Facility activities conducted from the EOF. (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-20 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Technical Services Unusual Event Control Room/ Site Emergency Monitors the TSC activation process and assists Coordinator (P) through General Technical Support Director the Site Emergency Director in managing and Emergency Center coordinating onsite emergency response efforts. Technical Specialist Alert through General Operational Support OSC Coordinator Provides assistance in the evaluation of, and Coordinator (STC) Emergency Center preparations for, repair and corrective actions. Training Center Staff Alert through General Emergency Technical Assistant Assists the Technical Assistant with monitoring (S) Emergency Operations Facility plant operational data. TSC Engineer - Alert through General Technical Support Engineering Assists the Engineering Coordinator with Electrical (STC) Emergency Center Coordinator engineering assessment and technical support. Maintains TSC status boards. TSC Engineer - Alert through General Technical Support Engineering Assists the Engineering Coordinator with Mechanical (STC) Emergency Center Coordinator engineering assessment and technical support. Maintains TSC status boards. TSC Logkeeper (S) Alert through General Technical Support Site Emergency Maintains log and provides administrative Emergency Center Director support for the Site Emergency Director. Work Control Alert through General Operational Support OSC Coordinator Performs duties as assigned by the OSC Supervisor - OSC (S) Emergency Center Coordinator (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-21 SSREP Rev. 67

POSITION DEFINITION TABLE 2 ERO POSITION INFORMATION POSITION TITLE ACTIVATION RESPONSE REPORTS TO PRIMARY RESPONSIBILITIES AND TYPE LEVEL LOCATION Work Control Unusual Event Control Room Short Term Assists the Short Term Emergency Director with Supervisor - On-shift through General Emergency implementing emergency response actions in the (OS) Emergency Director (STED) Control Room and initial notification of offsite authorities. Work Control Alert through General Operational Support OSC Coordinator Dispatched to the TSC to report to the Supervisor - TSC (S) Emergency Center Maintenance Coordinator and to staff the 4-way data link in the TSC. Work Planner - Alert through General Operational Support Tech Specialist Assemble work packages for mechanical MM/MV (S) Emergency Center Coordinator maintenance and valve repair teams deployed from the OSC as directed by the Technical Specialist Coordinator Work Planner - Alert through General Operational Support Tech Specialist Assemble work packages for electrical ME/IC (S) Emergency Center Coordinator maintenance and instrumentation and control repair teams deployed from the OSC as directed by the Technical Specialist Coordinator. (OS) = On shift ERO position (P) = Primary Responder - Rotating duty augmented ERO position (STC) = Subject to Call Responder- Non-rotating augmented ERO position that should be staffed prior to facility activation (S) = Secondary Responder -Non-rotating ERO staff position A-22 SSREP Rev. 67

SUMMARY

OF CHANGES Rev. 67 (AR 2386017 March 2022) Removed BOP Support Engineer, Electrical Support Engineer, Maintenance Coordinator, NSSS Support Engineer, and Licensing Coordinator. Rev. 66 (AR 02355399 January 2021) Table 1 -- Removed bargaining unit restrictions from the potential candidates background from the Chemistry Coordinator, Electrical Maintenance Personnel, I&C Personnel, and Mechanical Maintenance Personnel. Revised Potential Candidates Background section for the Radiological Controls Coordinator, Junior Radiation Protection Personnel, Radiological Assistant and Offsite Monitoring Team Personnel to state Experienced with or trained on Radiation Protection related duties. Moved Dosimetry Records Personnel position functions to the Radiological Assistant and eliminated the Dosimetry Records Personnel position. Rev. 65 (AR 02291007 March 2019): Removed Document Control Center Personnel and TSC RMD Personnel (CMP 02226221). Removed HP6002I course from Junior Radiation Protection Technician Prerequisites. Rev. 64: Added Security Personnel to Table 1 which had been inadvertently deleted in a previous revision (AR 2092861). Rev. 63: Replaced some course numbers with qualification. Removed reference to GT4000I, Enhanced Radiation Worker (AR 1888575). Revised to allow Engineering Coordinator, Response Manager, and Site Emergency Director to be past or current supervisor (AR 1928340). Revised Assembly Area Coordinator potential candidate background. Added Environmental Analysts which replaces the services provided by a vendor. Rev. 62: In Appendix A changed media center to Joint Information center, added new position EOF Access Control Personnel (AR#1721945) Changed Table 1 Operations Technician prerequisite to read, Past or current SRO license at Seabrook Station or SRO certification at Seabrook Station and current operations training instructor. Also changed potential candidate background to read, Routinely engaged in operations-related activities, including operations training. (AR 1861084) A-23 SSREP Rev. 67

Changed Table 1 Engineering Coordinator prerequisite to read, Engineering background or degree, principal engineer or supervisor or higher. A-24 SSREP Rev. 67

APPENDIX B CANCELED SSREP Rev. 42

APPENDIX C EVACUATION TIME ESTIMATES SSREP Rev. 49

Evacuation Time Estimate Scenario Descriptions Scenario Season(1) Day Time Weather Special 1 Summer Mid-Week Mid-Day Good None 2 Summer Mid-Week Mid-Day Rain None 3 Summer Weekend Mid-Day Good None 4 Summer Weekend Mid-Day Rain None 5 Summer Mid-Week, Evening Good None Weekend 6 Winter Mid-Week Mid-Day Good None 7 Winter Mid-Week Mid-Day Rain None 8 Winter Mid-Week Mid-Day Snow None 9 Winter Weekend Mid-Day Good None 10 Winter Weekend Mid-Day Rain None 11 Winter Weekend Mid-Day Snow None 12 Winter Mid-Week, Evening Good None Weekend 13 Summer Mid-Week, Evening Good July 4th Fireworks Show at Hampton Beach Weekend 14 Summer Mid-Week Mid-Day Good Roadway Impact - Lane closure on SH 101 WB (1) Winter assumes that school is in session (also applies to spring and autumn). Summer assumes that school is not in session C-1 SSREP Rev. 49

TIME TO CLEAR THE INDICATED AREA OF 90 PERCENT OF THE AFFECTED POPULATION TABLE 1: 2 Mile Radius & 5 Miles Downwind / Wind Direction (deg from) and Affected ERPAs Scenario 303-33.9 34-100.9 101-122.9 123-167.9 168-191.4 191.5-258.9 259-281.4 281.5-302.9 Number AB ABC AC ACD AD AD AD A 1 3:05 3:05 1:40 2:20 2:15 2:15 2:15 1:40 2 3:20 3:15 1:50 2:25 2:25 2:25 2:25 1:45 3 3:00 3:00 1:30 2:10 2:10 2:10 2:10 1:25 4 3:20 3:15 1:35 2:15 2:20 2:20 2:20 1:30 5 3:00 3:00 1:40 2:20 2:25 2:25 2:25 1:35 6 2:50 2:50 1:40 2:15 2:15 2:15 2:15 1:35 7 3:05 3:05 1:45 2:20 2:20 2:20 2:20 1:40 8 3:25 3:25 2:05 2:40 2:35 2:35 2:35 1:55 9 2:45 2:45 1:30 2:05 2:10 2:10 2:10 1:25 10 2:50 2:55 1:35 2:10 2:10 2:10 2:10 1:30 11 3:15 3:15 1:50 2:30 2:25 2:25 2:25 1:45 12 2:50 2:50 1:40 2:15 2:15 2:15 2:15 1:35 13 3:00 3:00 1:40 7:00 7:00 7:00 7:00 1:35 14 3:05 3:05 1:40 2:30 2:30 2:30 2:30 1:40 C-2 SSREP Rev. 49

TIME TO CLEAR THE INDICATED AREA OF 90 PERCENT OF THE AFFECTED POPULATION TABLE 2: 5 Mile Radius & 10 Miles Downwind / Wind Direction (deg from) and Affected ERPAs Scenario 303-33.9 34-100.9 101-122.9 123-167.9 168-191.4 191.5-258.9 259-281.4 281.5-302.9 Number ABCDE ABCDEF ABCDF ABCDFG ABCDFG ABCDG ABCD ABCD 1 2:55 3:30 3:30 3:50 3:50 3:35 3:00 3:00 2 3:05 3:45 3:50 4:10 4:10 3:50 3:05 3:05 3 2:45 3:05 3:10 3:25 3:25 3:15 2:50 2:50 4 2:55 3:20 3:20 3:40 3:40 3:25 3:00 3:00 5 2:55 2:55 2:55 3:10 3:10 3:05 2:50 2:50 6 2:45 3:20 3:15 3:40 3:40 3:30 2:50 2:50 7 2:50 3:40 3:40 4:00 4:00 3:40 2:55 2:55 8 3:15 4:05 4:00 4:30 4:30 4:00 3:15 3:15 9 2:35 2:55 2:55 3:10 3:10 3:00 2:35 2:35 10 2:35 3:05 3:05 3:20 3:20 3:10 2:45 2:45 11 3:05 3:30 3:25 3:40 3:40 3:30 3:05 3:05 12 2:40 2:50 2:50 3:00 3:00 2:55 2:40 2:40 13 6:10 5:50 6:00 5:50 5:50 6:15 6:20 6:20 14 2:55 4:15 4:10 4:15 4:15 3:45 3:00 3:00 C-3 SSREP Rev. 49

TIME TO CLEAR THE INDICATED AREA OF 90 PERCENT OF THE AFFECTED POPULATION TABLE 3: Staged Evacuation - 2 Mile Radius Evacuates then Evacuate Downwind to 5 Miles / Wind Direction (deg from) and Affected ERPAs Scenario 303-33.9 34-100.9 101-122.9 123-167.9 168-191.4 191.5-258.9 259-281.4 281.5-302.9 Number AB ABC A C A C D A D A D A D A 1 3:30 3:25 1:55 2:30 2:35 2:35 2:35 1:40 2 3:40 3:35 1:55 2:35 2:35 2:35 2:35 1:45 3 3:35 3:35 1:45 2:35 2:30 2:30 2:30 1:25 4 3:45 3:40 1:50 2:35 2:35 2:35 2:35 1:30 5 3:35 3:35 2:00 2:45 2:45 2:45 2:45 1:35 6 3:15 3:10 1:55 2:35 2:35 2:35 2:35 1:35 7 3:20 3:30 1:55 2:35 2:35 2:35 2:35 1:40 8 3:50 3:50 2:15 3:00 3:00 3:00 3:00 1:55 9 3:10 3:10 1:45 2:35 2:35 2:35 2:35 1:25 10 3:25 3:20 1:45 2:35 2:35 2:35 2:35 1:30 11 3:45 3:45 2:10 3:05 3:05 3:05 3:05 1:45 12 3:25 3:25 2:00 2:45 2:50 2:50 2:50 1:35 13 3:40 3:35 2:00 6:45 6:40 6:40 6:40 1:35 14 3:30 3:25 1:55 2:35 2:35 2:35 2:35 1:40 C-4 SSREP Rev. 49

SUMMARY

OF CHANGES Rev. 49: Added note to scenario descriptions to when school is in session. Updated ETE values from the 2013 ETE Study, as amended on June 10, 2014 (AR 01963782). Corrected affected ERPAs in Table 3 for 281.5-302.9 degrees. Rev. 48: Throughout Appendix C incorporated revised scenario descriptions and updated ETE values from the 2012 ETE Study. C-5 SSREP Rev. 49

APPENDIX D LETTERS OF AGREEMENT WITH EMERGENCY RESPONSE ORGANIZATIONS SSREP Rev. 64

APPENDIX D LETTERS OF AGREEMENT TABLE OF CONTENTS Date of Agreement

1. Exeter Hospital January 2012

2. [Deleted AR 02276102 September 2018] [Deleted]

3. Wentworth-Douglass Hospital August 2019

4. Seabrook Fire Department June 2016

5. State of New Hampshire and Commonwealth of Massachusetts July 2017

6. Institute of Nuclear Power Operations See NOTE 1

7. Portsmouth Police Department May 2013

8. Pease Development Authority (EOF) May 2013

9. Alternate EOF location for beyond Design Basis Events April 2014 (Protected: Ref. NRC IR 85-32[7])

(Protected: Ref. NRC IR 85-32[12]) (Protected: Ref. FPL Common Letter L-2005-214) NOTE 1: The INPO emergency assistance agreement is initiated by INPO with its member utilities. The agreement is certified to remain in effect annually by INPO by letter of agreement to its member utilities. The current letter of certification is posted annually by INPO on the INPO website under emergency preparedness. For that reason, the current INPO letter of agreement is not maintained in the SSREP. SSREP Rev. 64

LETTER OF AGREEMENT between

                        ~extEra  Energy Seabrook, LLP and Exeter Hospital, Inc.

AGREEMENT This emergency medical assistance and support agreement is made this date between Exeter Hospital, Inc., 5 Alumni Drive, Exeter, New Hampshire 03833 (hereinafter referred to as "hospital") and NextEra Energy Seabrook, Lafayette Road, Seabrook, New Hampshire 03874, acting as agent for Seabrook Joint Owners ("Agent"), The Seabrook Joint Owners are Agent, the Massachusetts Municipal Wholesale Electr~c Company, Hudson Light & Power Department, and Taunton Municipal Lighting Plant. In consideration of the mutual covenants and agreements set out below, Exeter Hospital and Agent agree as follows:

1. Hospital will accept as patients any personnel from Seabrook Station who may be considered to have substantial radiation related injuries, or who may have been exposed to and contaminated by radioactive materials, provided that:

a) arrangements for transportation of all such patients shall be made by Agent and the patients will be accompanied by appropriately equipped and trained personnel; and b) Agent will assign appropriately equipped and trained staff to assist Hospital staff with radiation monitoring and control; and c) Agent shall take all appropriate precautionary measures designed to minimize the possibility of spread of radioactive materials and will advise the Hospital in advance of the patient's arrival, of the patient's physical status, and any associated radiological hazard.

2. Agent will:

a) Compensate Hospital for its normal charges for use of facilities and medical services rendered. b) Reimburse Hospital for (i) materials and equipment consumed or which must be destroyed or replaced due to radioactive contamination in excess of normal background, (ii) the costs of training time for Hospital personnel required to maintain the treatment capabilities envisioned by this agreement; and (iii) the costs of special equipment or renovations to existing hospital areas necessary to provide services hereunder. cl To the extent not directly and fully covered by Agent's nuclear liability insurance, reimburse Hospital and its employees and agents and contractors for all expenses incurred for the care and treatment of any hospital IT-I SSREP Rev. 58

personnel (including Hospital's normal charges for any services rendered in the Hospital) who are injured or contaminated as a result of coming into contact with Agent's personnel who are contaminated with radioactive material. d) Be responsible for decontaminating Hospital's equipment and property and for proper disposal of any radioactive materials brought by Agent's personnel or produced by Hospital as a result of the treatment of Agent's personnel. e) Provide Hospital with all radiation survey equipment that is necessary under applicable laws and regulations or sound medical practice for making determinations of radioactive contamination and maintaining said equipment. f) Through mutual agreement and Agent's expense (i) provide and maintain for Hospital all appropriate equipment for treatment of patients with radioactive contamination, and (ii) make available appropriate training of Hospital staff, including training exercises, in which both Hospital and Agent will participate. g) To advise Hospital as to any reports to be filed under applicable state or federal law concerning any treatment or incident arising under this agreement.

3. This agreement shall be for an initial period of one (1) year from the date hereof and shall automatically be renewed for successive one (1) year periods unless either party, at least 90 days prior to the next scheduled expiration date, give notice of termination. No cause is required for termination.

4. Agent shall indemnify and hold Hospital harmless from all costs, liabilities, claims and expenses (including reasonable counsel fees) made by any party and arising from the performance of services by Hospital or Agent under this agreement and whether or not the Hospital or its employees, agents and contractors, failed to exercise due care in the provision of such services, but only to the extent permitted by applicable law. Notwithstanding this provision, no obligation of indemnification shall arise with respect to any claim to the extent the same resulted from the willful misconduct or bad faith of the indemnified party.

5. The Seabrook Joint owners share ownership of Seabrook Station in the following proportions: NextEra Energy Seabrook owns 88.2%;

Massachusetts Municipal Wholesale Electric Company, 11.6%; Taunton Municipal Lighting Plant, 0.1%; Hudson Light & Power Department, 0.07%. Hospital understands and agrees that the Seabrook Joint Owners are severally liable under this Agreement in proportion to their respective ovmership shares, and that the Seabrook Joint Owners are neither jointly nor jointly and severally liable hereunder. Thus, an individual joint owner may not be made responsible for the entire amount of a judgement against the joint owners. 2 D-1a SSREP Rev. 58

6. This agreement may be amended at any time by written agreement between Exeter Hospital and Agent. If this agreement is terminated in accordance with its terms or by mutual agreement, all equipment will remain property of Hospital except for all radiation survey instrumentation which will be returned to Agent.

IN WITNESS WHEREOF, the parties have caused the agreement to be executed by their duly authorized officials as of the day and year written below. By:~_,___,r--~~~~~~~~--f-+- Ti By:_a_~_'C::. __ ~_ Paul Freeman Site Vice President As agent for Seabrook Joint Owners 3 D-1b SSREP Rev. 58

[Deleted AR 02276102 September 2018] D-2 SSREP Rev. 63

D-3 SSREP Rev. 47 D-3a SSREP Rev. 47 D-3b SSREP Rev. 47 D-4 SSREP Rev. 61 D-5 SSREP Rev. 57 D-5a SSREP Rev. 57 D-5b SSREP Rev. 57 D-5c SSREP Rev. 57 Institute of Suite 100 Nuclear Power 700 Galleria Parkway, SE Operations Atlanta, GA 30339-5943 770-644-8000 FAX 770-644-8549 October 30, 2012

Dear Ladies and Gentlemen:

This letter certifies that the plant emergency assistance agreement between INPO and its member utilities remains in effect. In the event of an emergency at your utility, INPO will assist you in acquiring the help of other organizations in the industry, as described in Section 1 of the Emergency Resources Manual, INPO 03-001, and in the United States Nuclear Industry Response Framework. If requested, INPO will provide the following assistance:

• coordinate technical information flow from the affected utility to the nuclear industry and government agencies
• coordinate the procurement and shipping of equipment and supplies
• locate personnel with technical expertise
• facilitate industry vendor and commercial supplier support
• obtain technical information and industry operating experience regarding plant components and systems
• provide an INPO liaison to facilitate interface This agreement will remain in effect until terminated in writing. Should you have any questions, please call Steve Meng at (770) 644-8548 or e-mail at MengSW@inpo.org.

Sincerely,

                                                               /1I Jfh *r/; ~~~
                                                                         !           £_/

Jeffrey T. Gasser Vice President Emergency Response JTG:cjm D-6 SSREP Rev. 61

LETTER OF AGREEMENT between NexlEra Energy Seabrook and the Portsmouth, New Hampshire Police Department The purpose of this agreement is to establish arrangements with the Portsmouth, New Hampshire Police Department .to provide a security detail for the Seabrook Station Emergency Operations Facility (EOF) when requested by an authorized representative of NextEra Energy Seabrook, operator of Seab\Ook Station. The EOF ls located at 1O~ Corporate Drive, Portsmouth, NH. The faciUly Is activated by the Seabrook Station emergency response organization (ERO) if an emergenoy classified as an Alert or higher Is declared at the station. For most emergency conditions, ~he Seabrook Station Security Department would provide security for the EOF, which 9onslsts primarily of patrolllng the facility and monitoring clo_sed circuit sutvelllance cameras of !he EOF premises. A security event at Seabrook Station (e.g. 1 UtJaUthorlzed entry of persons into the Seabrook Station protected area) may cause Seabrook Station to staff the EOF. If such a11 event prompts an emergency declaration, Seabrook Station ERO members wlll staff the EOF. For th~se condltlons, the Seabrook Station Security Department may not be available to provide security at the EOF. For such an event, a Seabrook ~talion Emergency Response Organization official or Security Department representative may contact the Portsmouth Police Department and request assignment of a police detail to the EOF. The Seabrook Station representative will call the main Portsmouth Police Department telephone number to request a security detall. When requesting Portsmouth Police Department assistance, the Seabrook Station representative wlll provide his/her name, position, current location and telephone numbe~. and will request a Portsmouth Police Department detail at the EOF. After giving due consideration to exigencies affecting the city and Jaw enforcement priorities at the time of the request, the Portsmouth Police Department will assign a number of police officers to the EOF as agreed by the requesting Seabrook Station representative and Portsmouth Police Department managemel')t. The Portsmouth Police Department detail will provide' security services at the EOF In consultation with Seabrook Station management at the EOF. In the event that the Portsmouth Police Department responds to the request to provide security at the EOF1 NextEra Energy Seabrook will reimburse the Portsmouth Police Department for requested services per this Agr(!ement at the standard police detali rate utilized by the City of Portsmouth at the* time the services per this Agreement are rendered. No compensation will be due and owing to Portsmouth Police Department in the event that Portsmouth Police Department cannot provide a .pollce detail In response to a request for assistance by NextEra Energy Seabrook pursuaaz;;;;:ont. _,JrZ2::JZ__ Kevin Walsh Stephen Dubois Site Vice President Chief of Police NextEra Energy, Seabrook J } Portsmouth, New Hampshire Date: SI ~;), ~ ~O \~ D-7 SSREP Rev. 59

SUBLEASE AMENDMENT NO. 1 Sublessor: Pease Development Authority ("Sublessor" or "PDA") Sublessee: PIONEER NEW HAMPSHIRE LLC ("Sublessee,, or "Pioneer") Premises: 108-114 Corporate Drive (former Brackett School) at Pease International Tradepm1, P011smouth, New Hampshil'e 03801 Sublease Date: December 23, 1999 This Sublease Amendment No. I effective September 6, 2012, by and between the above referenced Sublessor and Sublessee: WHEREAS, Sublessee desires to modify the Sublease to incorporate revised terms and conditions related to the constrnction of a proposed office building of approximately 21,000 square feet with related paving lighting, utilities, landscaping, drainage and associated site improvements in accordance with the Site Plan and stipulations of the Planning Boa1*d of the City of Portsmouth which recommended approval on May 17, 2012; WHEREAS, the proposed office building with an address of 108 Corporate Drive is also known as Building 4 and or the 11 l08 Facility" and is intended to be purchased and occupied by the Seabrook Joint Owners namely, NextEra Energy Seabrook, LLC, Massachusetts Municipal Wholesale Electric Company, Hudson Light & Power Depat1ment, and Taunton Municipal Lighting Plant acting thl'Ough their agent, NextEra Energy Seabrook, LLC ("NextErn11), (collectively, the "Joint Owners); WHEREAS, as a condition of this Sublease Amendment No. 1 and to permit the purchase by the Joint Owners of Building 4, PDA has consented to the creation of a leasehold condominium with such limitations and conditions as are set forth in the Pioneer new Hampshire Condominium Declaration dated April_, 2013 and recorded [INSERT RECORDING D~TA]. NOW, THEREFORE, Sublessor and Sublessee agree for good and valuable consideration, the receipt and sufficiency of which is hereby acknowledged, that the Sublease be amended as set forth below: a.) Recital Dis amended to update Sublessee's address of its principal place of business to: Summit Land Development 340 Central Avenue, Suite 202 Dover, NH 03820 b.) Ai1icle 1, Section 1.1 is amended to include the following land description of the 1 p:\pion~r\corpornte centcr\sublease amendment no I (s020S000*2).docx D-8 SSREP Rev. 59

Premises or Subleased Premises: a ce11ain parcel of land in P011smouth, New Hampshire, located at 108-114 Corporate Drive, which premises are located in the Business Commercial Zone of Pease International Tradeport. The Leased Premises are estimated to contain 11.54+/- acres. c.) Atticle 2.A is amended to include the following new Section 2A.6: 2A.6 Transpo11ation Infrastructure Improvement Fee Sublessee acknowledges that the construction and operation of Building 4 may generate additional traffic at Pease International Tradeport and consequently may have a direct impact on traffic patterns and conditions at the Tradepo1t. Sublessee agrees to pay a proportional share of any Transportation Infrastructure Improvement Fee ("TII fee") for infrastructure improvements including, but not limited to, signals, signage, markings, geometric changes to intersections and/or roadways and othe1* traffic control devices. Sublessee's proportional share of the TII fee shall be based upon a formula which will be established by Sublessor and applied uniformly and proportionally to all projects which are subject to said fee. Sublessee's TII fee shall not exceed the best estimate of its reasonable share of these improvements based on the actual traffic impact caused by the additional p.m. peak hour trnffic generated by the Facility as determined by PDA 's transp011ation consultant, Vanasse, Hangen & Brnstlin, Inc. based on information pl'ovided by Sublessee or otherwise verified by PDA. Once established by the PDA and billed to all similarly situated projects, payment of the Transportation Infrastructure Improvement Fee shall be made in the same manner as Ground Rent payments set forth in Article 4 and may be paid in equal installments over a period of time determined by PDA commencing on the first day of the month following authorization by the PDA Board of Directors and notification to Sublessee of the its share of the fee. The cuncnt estimated proportional share of the TII Fee assessed to the Premises is $7,710. d.) Aiticle 2A is amended to include the following new Section 2A.7: 2A.7. Improvements to Subleased Premises Required Pursuant to This Sublease Amendment No.1 In order to induce Sublessor to enter into this Sublease Amendment No. 1, and in lieu of the construction of the Facility as defined in A1ticle 2A, Section 2A.l of the S1.1blease, Sublessee covenants at its sole cost and expense on or after September 61 2912, to construct a one story 17,664 square foot office building ("Building 4" or the "108 Facility") with related paving, lighting, utilities, landscaping, drainage and associated site improvements as shown on the Site Plan dated April 6, 2012 (last revision dated May 7, 2012) consisting of fifteen (15) sheets and entitled "Proposed Office Building 108 Corporate Drive Po1tsmouth, NH and stamped by Matthew Bryan McCormack, Registered Professional Engineer in the State of New Hampshire and associated with the firm of Hoyle Tam1er & Associates, Inc. (the "108 Site Plan") attached 2 p:\pioneer\corporale ccnter\sublease amendment no I (s0205000*2).docx D-8a SSREP Rev. 59

hereto and incorporated in the Sublease as Exhibit "A-2" and as further set f01th in the Site Review Agreement dated July 27, 2012. Subless01* has further agreed to upgrade and improve landscaping associated with the entirety of the Subleased Premises and to upgrade existing signage at its sole cost and expense. e.) Article 3, Section 3.1 is amended to restate the remaining base term and options available to the Sublessee: 3.1. This Sublease shall be effective upon execution, and shall continue for a base term of twenty-five (25) years which terms shall commence on December 1, 1999 ("Term Commencement Date"). Sublessee shall have up to six (6) consecutive options to extend the base term of the Sublease, exercisable by Sublessee at its sole discretion, each of which options, if exercised, shall extend the Base Term as set forth below: a) Option 1 Five (5) years and four (4) months through March 31, 2030 b) Options 2 through 6 Five (S) years each expiring on March 31 of the applicable yea1* In no event shall the Base Term and all option periods extend beyond fifty-five (55) years and four (4) months from the Term Commencement Date. Any extension of the term through exercise of an option shall be upon the same terms and conditions applicable to the Base Term, provided that rental rates shall escalate as provided in Article 4 (and any other applicable pl'ovision addressing rental rates). The pa11ies acknowledge that in accordance with the original terms and conditions of the Sublease, the Adjustment Date for the purposes of calculating the Building Area Rent due to Sublessor shall be December 1st of each applicable year. By Quitclaim Deed (and Exhibits A - G, inclusive) made and entered into on October 15, 2003 and Quitclaim Deed dated September 16, 2005 (the 11Deeds 11), the Government, acting by and through the Secretary of the Afr Fo1'Ce did grant to PDA the land and improvements located in the City of Portsmouth, Town of Newington and Town of Greenland, as contemplated by the Master Lease, Application and Acceptances, and which deed dated October 15, 2003 included the Leased Premises. The Parties acknowledge that the Deeds impose certain requirements on Sublessee with respect to leases which are addressed in the terms and conditions of this Lease. Copies of the Deeds are attached hereto and incorporated in the Sublease as Exhibit J. f.) Beginning on the effective date of this Sublease Amendment No. 1, Article 4, Section 4.1 is amended, to the extent applicable, by a new Article 4A: [REMAINDER OF PAGE LEFT INTENTIONALLY BLANK] ARTICLE4A. 3 p:lpioncer\corpornte center\subJease amendment no I (s020S000*2),docx D-8b SSREP Rev. 59

BUILDING AREA RHNT DUIUNO AND IMMEDIATELY FOLLOWING CONSTRUCTION . OJ~ 'lllE 108 FACILITY 4A.1 Building Arca Rent During Conslruclion:Period of 108 Facilily: Commencing on December 1, 2012 - Year 14 of the Sublease, the building area rent ("Building Area Rent"), as defined in Article 4, Section 4.1 of the Sublease, for Buildings 1, 2 and 3 (the former Brackett School) and the contemplated Facility is a combined annual rate of$241,138.75. Commencing on December 1, 2013 - Year 15 of the Sublease, the Building Area Rent for Buildings 1, 2 and 3 and the contemplated Facility is a combined annual rate of $250,202.50. Notwithstanding the provisions of the preceding parag1*aphs, fo1* the one year period beginning September 1, 2012 ("Construction Petfod of 108 Facility"), the Building Area Rent shall be subject to a credit of $64,000 applied in equal monthly installments of one twelfth thereof through August 31, 2013. 4A.2 Building Area Rent Adjustment beginning September 1, 2013: Commencing on September 1, 2013 and continuing through the base term of the sublease plus any applicuble option year, the Building Area Rent contemplated in Article 4, Section 4. lB and attributable solely to the Facility, as defined, shall be subject to. a reduction of 25%. By way of example, the Building Area Rent attributable to Building 4, commencing on September 1, 2013, shall be at an annual rate of $48,000 subject to further adjustment beginning on December 1, 2014 - Year 16 of the Sublease. Building Area Rent for Building 1, 2 and 3 are not subject to any rent reduction, except as set forth in 4A.1 above and 4A.3 below. 4A.3 Building Aren Rent Adhistmcnt Rent C1*edit fol' hilp1*ovcn'le11ts to Buildings I. 2dancl 3: Upon completion of the 108 Facility and the commencement of building area rent payments for the 108 Facility, the Building Area Rent for Buildings 1, 2 and 3 (and specifically excluding the 108 Facility) will be subject to a rent credit equal to the lesser of (a) $23,374.75 or (b) one-half of the

• cost of (i) for removal of existing pavement and installation of 740 linear feet of 5' concrete sidewalks; and (ii) installation of3 light pole bases including excavation, backfill and conduit but excluding light poles and fixtures.

END OF ARTICLE 4A [REMAINDER OF PAGE LEFT INTENTIONALLY BLANK] 4 p:lpioncc1\corpornte ccntcr\sublease amendment no I (s0205000*2).iloox D-8c SSREP Rev. 59

g.) A1iicle 7, Insurnnce add the following new Section 7.8: 7.8 Over the tetm of this Sublease and any extensions thereof, Sublessor reserves the right to request increases in mandatory insurance coverage limits for each respective coverage area required under this Sublease as the same may be appropriate, commercially reasonable and prudent in view of then existing conditions and circumstances, Sublessor agrees to provide Sublessee with a thilty (30) day written notice when making any request for an increase in required insurance coverage limits. h.) Atiicle 14, Section 14.5 is deleted in its entirety as a result of Sublessee having met its payment obligation in full. i) Article 23, Notices is amended to include the following corrected addresses for Sublessor and Sublessee: If to Sub lessor: Pease Development Authority 55 International Drive Portsmouth, NH 03801 Attn: Executive Director If to Sublessee: Pioneer New Hampshire LLC c/o Summit Land Development 340 Central Avenue, Suite 202 Dover, NH 03 820 j.) All other terms and conditions of the Sublease shall remain in full force and effect and shall continue to be binding upon the Patiies. [SIGNATURE PAGE FOLLOWS] 5 p:\pionm\corporate center\sublease amendment 110 t (s020S000-2).docx D-8d SSREP Rev. 59

IN WI1NESS WHEREOF, Sublessor and Sublessee have executed this Sublease Amendment No. 1 effective September 6, 2012. Sublessee: PIONEER NEW HAMPSHIRE LLC By: Its: .~~ Sublessor: By: Its: STATE OF NEW HAMPSHIRE: ss. COUNTY OF P.ott<..1wt. ~""' Onthis~~dayof \-\.+\'I ,2013,befol'emo, \1\\Q..'l S. J\~e\(.~~ the und~rsigned officer, pel'sonally appeared c!.\.l.~ '6"(," l\...t 1C.l *. * . .~ personally known to me (01* proved to me on the brisis of stitisfoctory evidence) to be the of Pionee1* New Hampshire LLC, and on oath stated that he was authorized to execute this instl'Ument and acknowledged it to be his free and voluntary act for the uses and purposes set fo1th herein.

                                                   ~tu..M.~.~                                      .

N~tary P\1bllo In and. for siiid lf,\~Nl1~Aruf4'yStatc . Pnnted Nome: Coriinitjstoneror>>ccds Petmt1l~Ol6 My commission c~pi"res: J4yCommlsslon llxplres * . STATE OF NEW HAMPSH_IRE: ss. COUNTY OF ROCKINGHAM On this 3o!"day of \1 ¢>.,"/ , 2013, befo1*e me \1 At.l l. $.. Q L £.KS/ , the undersigned officer, pel'sonally appeared David R. Mullen, personally known to me (ol' proved to me on the basis of satisfactory evidence) to be *the Executive Director of the Pease Development Authority and on oath stated that he was authorized to execute this instrument and acknowledged It to be his free and voluntary act fOI' the uses and purposes set forth herein. Notary Public in and for said Coun and State Printed Name: Martes.Ale~y

                                                                 * *

• CommlulonerofDeiils My comm1ss1on expll'es: MyCammlsslelllliq>lruJebr11aqr2,2016 6

p:\ploneer\corporato center\sublease amendment no I (s020S000*2).docx D-8e SSREP Rev. 59

                                          . AGREEMENT Between New Hampshire Homeland Security & Emergency Management (NHHSEM) and NextEra Energy Seabrook, LLC, (Seabrook Station) for Relocation of Seabrook Station Personnel to the New Hampshire Ineident PlamiinK arid Operations Center (IPOC) in the Event the Seabrook Station Emergency Operations Facility. (EOF) is Unavailable Recitals:*

In consideration of the dedication of space in th_e Seabrook Station EOF for the New Hampshire Incident Field Office and agreement by Seabrook Station for use of the space by NHHSEM in the event the NH Emergency OperatiOns Center (EOC) becomes unavailable during an emergency, and * *

• Whereas, the NH IPOC is equipped with dedicated emergency *communications with the Sea~rook Station control room and With the Massachusetts. State EOC, and Whereas, the.NH IPOC is capable ofreceiving Seabrook Station plant data via the NRC Emergency Response Data System, and .

Whereas, the NH IPOC is equipped with dose assessment softWare used.by the Seabrook Station dose assessment personnel for calculating dose projections in the Seabrook Station emergency planning zone (Raddose V and RASCAL), and Whereas, the NH IPOC is the location of State ofNew Rampshir~ protective action decision makers and supporting emergency response offi.cials*iri: the event of a declared radiological emergency at Seabrook Station; ** Agreement: NOW THEREFORE, for.good and valuable consideration'~*ihe*receipt and sufficiency of which is hereby acknowledge, the parties agree *as follows: .. * *

1. In the unlikely event the Seabrook Statfon.EOF sho1:Jld become unavailable during a Seabrook Station emergency or an external event, space will be made available

              .in the NH IPOC for Seabrook Station EOF response personnel, who are designated by Seabrook Station.             *     .      * .     * *      *

2. NHHSEM will defer to Seabrook Station officials about specific Seabrook Station Emergency Response Organization (ERO) personnei who would relocate to the IPOC; however, unless otherwise agreed to by the parties, the number of Seabrook Station ERO personnel shall not exceed 15.:. * * **.

3. Relocated Seabrook Station personnel shall indude at least the EOF facility lead (Response Manager), personnel with radiological dose assessment expertise, and personnel capable of explaining technical plant status information to State of New Hampshire personnel co-located in the IPOC; D-9 SSREP Rev. 60

4. The personnel relocations allowed and authodzed hereunder shall be implemented by request from either the Seabrook Station ERO Response Manager or authorized designee to the Director or Assistant Director, NHHSEM.

5. Each party agrees to bear: its own costs arising from or relating to this agreement.

6. Notwithstanding anything to the contrary, and to the extent permitted by applicable law, Seabrook Station shall not be liable for consequential, exemplary, punitive, incidental, or indirect damages arising from or relating to its performance or non-performance under this agreement.

7. This agreement shall be governed and construed in accordance with the laws of the State of New Hampshire, without regard to conflicts of laws principles.

8. TOTHEEXTENTPERMITTEDBY APPLICABLE LAW, THEPARTIES HEREBY IRREVOCABLY WAIVE, TO THE FULLEST EXTENT PERMITTED BY LAW,. ANY AND ALL RIGHT TO TRIAL BY JURY IN ANY LEGAL PROCEEDING ARISING OUT OF OR RELATING TO THIS AGREEMENT OR THE TRANSACTIONS CONTEMPLATED HEREBY.

9. This written agreement constitutes the entire agreement between the parties regarding the* relocation of Seabrook Station personnel to the IPOC. No promises or representations o{any kind or* character other than those stated herein have been made to induce any party to ~nter into this agreement.

10. This agreement inay be executed in any number of counterpaits, each of which when so executed. and delivered shall be an original hereof and shall have the same effect as if all parties simultaneously executed a single document. Delivery of an executed counterpart of this agreement by _telefacsimile or electronic mail shall be equally as effective as delivery of an original executed counterpart of this agreement. Any party delivering an executed counterpart of this agreement by telefacsimile or electronic mail also shall deliver an original executed counterpart of this agreement, but the failure to deliver an original executed counterpart shall not affect the :vali<lity; enfol'ceability and binding effect of this Agreement.

11. No modification, amendment or waiver of any of the provisions contained in this agreement, shail *be binding upon any patty unless made l.n writing and signed by such party.

12. Each provision of this agreement shall be interpreted in such manner as to be effective and valid under applicable law, but if any provision of this agreement is held to be invalid or unenforceable in any respect, such invalidity or unenforceability shall not render invalid or unenforceable any other provision of this agreement.

13. This agreement shall be effective as of the date last signed below (the "Effective Date").

D-9a SSREP Rev. 60

IN WI1NESS WHEREOF the parties have caused.the agreement to be executed by their duly aufuori ~ * ~ ~

 * *ect r                                        ** Site Vice President ew Hampshire Homeland Security                     NextEra Energy Seabrook, LLC

& Emergency Management Date: #'f . Date: D-9b SSREP Rev. 60

SUMMARY

OF CHANGES Rev. 64: (PCR 02308922 November 2019) Updated Appendix D with the revised letter of agreement between the site and Wentworth Douglas Hospital. Rev. 63: (PCR 02276102 September 2018) Deleted letter of agreement with the Portsmouth Land Acquisition because the property that the Remote Monitoring Area is located on has been sold. Rev. 62: (PCR 2217534 August 2017) Updated Appendix D with the revised letter of agreement between the site and the State of New Hampshire and Commonwealth of Massachusetts. Rev. 61: In Appendix D updated agreements for Portsmouth Land Acquisition (Remote Monitoring Area), Seabrook Fire Department, and Institute of Nuclear Power Operations. Rev. 60: In Appendix D added agreement for alternative EOF for beyond design basis events. Rev. 59: In Appendix D removed PSNH Newington Station and Newington Police Department. Added Portsmouth Police Department and Pease Development Authority. Changed Jask Realty to Portsmouth Land Acquisition. (AR#1721945) Rev. 58: Added new lease agreement for relocated remote monitoring area and updated letters of agreement for Exeter Hospital and Seabrook Fire Department. Rev. 57: Inserted most recent Institute of Nuclear Power Operations emergency assistance agreement. Rev. 56: Updated letter of agreement with the Commonwealth of Massachusetts and the State of New Hampshire. Updated lease agreements with Public Service New Hampshire for the Emergency Operations Facility at Newington Station and for the remote monitoring/decontamination facility at Schiller Station. Rev. 55: Updated the letter of agreement with the Seabrook Fire Department with agreement dated August 2007. D-10 SSREP Rev. 64

APPENDIX E SEABROOK STATION PUBLIC ALERT AND NOTIFICATION SYSTEM SSREP Rev. 58

1.0 INTRODUCTION

The design objective of the Seabrook Station Public Alert and Notification System (PANS) is to have the capability to essentially complete the initial notification of the public within the plume exposure pathway Emergency Planning Zone (EPZ) (Reference 1) within about 15 minutes.1 This meets the requirements of 10 CFR 50.47 and Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities," and the guidance of NUREG-0654/FEMA-REP-1, Rev. 1, Appendix 3. Notification of the public in the plume exposure pathway Emergency Planning Zone (EPZ) is conducted primarily through the use of sirens where:

            "The expected siren sound pressure level generally exceeds 70 dBC where the population exceeds 2,000 persons per square mile and 60 dBC in other inhabited areas; The expected siren sound pressure level generally exceeds the average measured summer daytime ambient sound pressure levels by 10 dB (geographical areas with less than 2,000 persons per square mile)." (Reference 2)

If these criteria cannot be achieved, other notification means will be utilized for those specific geographical areas not covered by sirens. These provisions will assure that "...the prompt public notification system shall have the capability to essentially complete the initial notification of the public within the plume exposure pathway EPZ..." (Reference 1). Primary public alerting within the Seabrook Station EPZ will be accomplished through the activation of pole-mounted fixed sirens positioned throughout the EPZ. A total of 121 electronic sirens will be used in the EPZ to perform the initial alerting function. Of these, 94 sirens are permanently mounted in the New Hampshire portion of the EPZ. In Massachusetts, there are 27 permanently mounted sirens. Public information and instructional messages will be broadcast over the Emergency Alert System (EAS) by designated commercial radio stations. A public education program will be maintained to advise people in the EPZ that when the sirens are heard, they should tune to the designated commercial EAS radio stations for information about the emergency. The sirens have both tone and public-address capability. The siren tone is used to provide the alert function at all siren locations. Along the public beaches in Seabrook and Hampton, New Hampshire, sirens will provide both alerting tones and public address messages. Beach voice messages may be used in-season (i.e., May 15 - September 15) 1 A complete description of the design is given in the "Seabrook Station Public Alert and Notification System FEMA-REP-10 Design Report" dated April 30, 1988 and its Addendums. E-1 SSREP Rev. 58

1.1 Backup Alert and Notification System (ANS) Code Red Emergency Communications Network serves as a backup method of public alerting and notification capable of being used in the event the primary method of alerting and notification is unavailable during an emergency in compliance with 10CFR50, Appendix E (IV)(D)(3). Code Red is a telephone notification system providing coverage to the 17 New Hampshire communities and 6 Massachusetts communities in the Seabrook Station EPZ. In New Hampshire, the Rockingham County Dispatch Center (RCDC) in Brentwood and the New Hampshire State Police Communications Center in Concord have the capability to activate the backup system for the 17 NH EPZ communities. In Massachusetts, the MEMA Communications Center in Framingham and the Massachusetts State Police Troop A Headquarters in Danvers have the capability to activate the backup system in the 6 MA EPZ communities. 2.0 SIRENS Seabrook Station uses two types of sirens for public alert and notification:

1. Whelen Model WS-3000: oscillating very high power electronic sirens (rated at 122 dBC at 550 Hz at 100 feet).

2. Whelen Model WPS-4000: oscillating ultra-high power electronic sirens (system rated at 129 dBC at 550 Hz at 100 feet).

The functional design of the two models is almost identical with the main difference being siren output. Each model is modular which allows easy replacement and/or field maintenance of the power amplifiers, tone generators, radio receivers and decoders, battery-chargers and batteries. All are capable of tone or voice operation. Both New Hampshire and Massachusetts utilize Whelen Model WS-3000 and WPS-4000 sirens. 2.1 Siren Sound Level Prediction The sound level coverage for each siren location was predicted utilizing a computer model developed by Wyle Laboratories. The Wyle model accounts for sound attenuation due to spherical sound spreading, air and ground absorption, scattering of acoustic energy, reflection and diffraction of acoustic energy by barriers formed by hills, refraction by temperature gradient, and refraction by wind speed gradient. The sound coverage provided by each siren is displayed in the form of sound contours, which are lines of equal sound level surrounding the siren location. The computerized propagation model calculates the sound level in increments of 200 feet along equally spaced radials from the siren location taking into account the rated siren sound output level (measured at 100 feet), meteorological conditions, and the ground cover and topography along each radial. Contours of equal sound level are then generated using an interpolative procedure along each radial. This somewhat irregular contour is then smoothed by fitting cubic curves passing through and matching smoothly at the calculated points on each radial. E-2 SSREP Rev. 58

2.2 Control of Sirens The sirens in the State of New Hampshire will be activated by radio signal from the Rockingham County Dispatch Center (RCDC) in Brentwood, NH. Backup activation capability exists at New Hampshire State Police headquarters, New Hampshire Homeland Security & Emergency Management headquarters and the local EOCs. The State of New Hampshire siren activation protocols and methodology are fully described in the New Hampshire Radiological Emergency Response Plan (NHRERP). In Massachusetts, activation of the sirens will be accomplished by a combination of a wireline and radio signal from the Massachusetts Emergency Management Agency headquarters in Framingham. Backup activation capability exists at the Massachusetts State Police Troop A headquarters, local EOCs and the MEMA Region I EOC in Tewksbury, MA. The Commonwealth of Massachusetts siren activation protocols and methodology are fully described in Massachusetts Radiological Emergency Response Plan (MARERP), and local plans. 3.0 ACTIVATION PROCESS 3.1 New Hampshire Portion of EPZ Procedures have been established in the New Hampshire Radiological Emergency Response Plan to ensure that the public is provided with the alert signal within 15 minutes of the time that the decision to activate the siren system is made. The New Hampshire Homeland Security & Emergency Management (NHHS&EM) is informed of the incident at Seabrook Station, either through the State Police Communications Center (SPCC) or, upon activation of the State EOC, directly from Seabrook Station. If the incident is a SITE AREA EMERGENCY or GENERAL EMERGENCY, NHHS&EM directs the RCDC (or a backup activation point if necessary) to activate the sirens and directs the activation of EAS. The NHHS&EM will coordinate the activation of the siren systems with the EAS broadcasts. The NHHS&EM can also direct the local siren activation points to activate the sirens within their boundaries. In the event of a GENERAL EMERGENCY, where NHHS&EM is not contacted within 10 minutes, the SPCC (the State's 24-hour communication point) can also direct RCDC to activate the sirens and EAS. The NHHS&EM will initiate an EAS broadcast from NHHS&EM headquarters or will contact the primary EAS radio station, explain that there is an immediate Site Area Emergency (or General Emergency) and instruct the radio station operators on the appropriate EAS message to commence broadcasting. NHHS&EM will provide follow-up public information messages to the primary EAS station for broadcast. If an early precautionary action for the beach is recommended, the sirens covering the beach areas will be used to alert and notify the beach population of the beach closing. NHHS&EM will direct RCDC to activate its special beach closing procedures. RCDC will first activate the alert signal on the beach sirens. A pre-recorded voice message may be broadcast over the sirens, using their public address mode of operation. The voice message would inform the beach population that the beaches have been closed and instruct them to leave the beach area. The NHHS&EM will notify the U.S. Coast Guard and the Federal Aviation Administration that there is a Site Area Emergency (or General Emergency) at Seabrook Station. E-3 SSREP Rev. 58

3.2 Massachusetts Portion of EPZ Procedures have been established in the Massachusetts Radiological Emergency Response Plan to ensure that the public is provided with the alert signal within 15 minutes of the time that the decision to activate the siren system is made. The Massachusetts Emergency Management Agency (MEMA) headquarters in Framingham is informed of the incident at Seabrook Station directly from Seabrook Station. If the incident is a SITE AREA EMERGENCY or GENERAL EMERGENCY (including a fast-breaking GENERAL EMERGENCY), MEMA will activate the sirens and direct activation of EAS. MEMA will coordinate the activation of the siren systems with the EAS broadcasts. MEMA can also direct the local siren activation points to activate the sirens within their boundaries. Massachusetts and New Hampshire will coordinate activation of their respective siren and EAS activation systems. Massachusetts will verify the State of New Hampshire's initial notification to the U.S. Coast Guard and the Federal Aviation Administration. The U.S. Coast Guard is responsible for notification of transients in waters under their jurisdiction, and the FAA is responsible for notifying and restricting air traffic in the area. The Department of Interior will perform notification in the Parker River National Wildlife Refuge. Massachusetts also maintains the capability for door-to-door notification of the hearing-impaired population. This capability and the process for implementing it are described in the Massachusetts Radiological Emergency Response Plan. E-4 SSREP Rev. 58

SUMMARY

OF CHANGES Rev. 58: Section 2.2 replaced the word landline with wireline. Rev. 57: Added description of Code Red, the backup Alert and Notification System. (AR 02016739) E-5 SSREP Rev. 58

APPENDIX F EMERGENCY EQUIPMENT Equipment and supplies supporting the Seabrook Station Radiological Emergency Plan are maintained in accordance with the Seabrook Station Emergency Preparedness Facility Inventory Manual. This manual details the inventory and preparedness checks of Emergency Preparedness equipment and supplies for all ERO emergency response facilities and facilities of selected support organizations. (Protected: Ref. NRC IR 85-32[16]) SSREP Rev. 33

APPENDIX G SEABROOK STATION SUPPORTING EMERGENCY PLANS AND PROCEDURES LISTING G-1 SSREP Rev. 56

APPENDIX G SUPPORTING PLANS AND PROCEDURES I. FEDERAL PLAN National Response Framework, Nuclear/Radiological Incident Annex (NRP) II. STATE PLANS New Hampshire Radiological Emergency Response Plan Massachusetts Radiological Emergency Response Plan for Licensed Nuclear Power Plants - Appendix 2 to Hazard Specific Supplement No. 6 Maine Ingestion Pathway Plan for Seabrook Station III. LOCAL PLANS New Hampshire EPZ includes the following: Seabrook Portsmouth Greenland Rye North Hampton South Hampton Hampton Hampton Falls Stratham Exeter Newfields Brentwood Kingston East Kingston Kensington Newton New Castle Massachusetts EPZ includes the following: Salisbury Newburyport Newbury West Newbury Amesbury Merrimac IV. Severe Accident Management Guidelines V. Seabrook Station Emergency Preparedness Department Procedures (EPDP), EP-AA-101-1000 Nuclear Division Drill and Exercise Procedure, and Emergency Preparedness Facility Inventory Manual (EPFI) G-2 SSREP Rev. 56

VI. SUPPORTING STATION SECURITY DEPARTMENT PROCEDURES GN1332.00, Security Response to a Declared Radiological Emergency GN1336.04, Security Related Emergency Preparedness Equipment and Systems Testing VII. SUPPORTING STATION OPERATIONS DEPARTMENT PROCEDURES OS1290.03, Response to a Land Based Security Event OS1290.04, Response to an Airborne Security Threat VIII. SUPPORTING STATION CHEMISTRY PROCEDURES (The following procedures meet post-accident assessment program requirements of NUREG-0578, NUREG-0737, and Technical Requirement Program 5.6) CS0932.17, Post Accident Sample System (PASS) Operational Surveillance CS0925.01, Reactor Coolant Post Accident Sampling CS0925.16, Post Accident Containment Recirculation Sump (RHR) Liquid Sampling CS0925.10, Preparation for Post-Accident Sampling CS0925.07, Post Accident Gas Sampling IX. STATION EMERGENCY RESPONSE PROCEDURES SEABROOK STATION REP SECTION CHAPTER 1: CLASSIFICATION AND RESPONSE ER 1.1: Classification of Emergencies 5.0 ER 1.2: Emergency Plan Activation 5.0, 9.0, 11.2 ER 1.3: Cancelled. Information from this procedure has been incorporated into Procedure ER 1.2. ER 1.4: Cancelled. Information from this procedure has been incorporated into Procedure ER 1.2. ER 1.5: Cancelled. Information from this procedure has been incorporated into Procedure ER 1.2. ER 1.7 Unusual Event Procedure for Primary Responders CHAPTER 2: NOTIFICATION ER 2.0: Emergency Notification Documentation Forms 10.4 Procedure ER 2.1: Cancelled. Information from this procedure has been incorporated into Security Procedure GN 1332.00 G-3 SSREP Rev. 56

SEABROOK STATION REP SECTION ER 2.2: Cancelled. ER 2.3: Cancelled. Information from this procedure has been incorporated into Procedures ER 1.4 and ER 1.5. CHAPTER 3: EMERGENCY FACILITY ACTIVATION ER 3.1: Technical Support Center (TSC) Operations 6.1.1, 7.0, 10.3, 10.4.2 ER 3.2: Operational Support Center (OSC) Operations 6.1.2 ER 3.3: Emergency Operations Facility (EOF) Operations 7.0, 6.1.3, 6.2.3.1, 9.4, 10.3, 10.4.2 ER 3.4: Seabrook Station News Services Operation 6.1.6, 8.4, 11.1, 11.2, 11.3 ER 3.5: Joint Information Center Operations 6.1.6, 8.4, 11.1, 11.2, 11.3 ER 3.6: Assembly Area Operations N/A CHAPTER 4: PERSONNEL PROTECTION ER 4.1: Cancelled. Information from this procedure has been incorporated into Procedure ER 3.1 and Security Procedure GN 1332.00 ER 4.2: Reserved ER 4.3: Radiation Protection During Emergency Conditions 10.4.5 ER 4.4: Cancelled. Information from this procedure has been incorporated into Operations Department Instruction (ODI) 32 ER 4.5: Reserved ER 4.6: Offsite Monitoring and Decontamination 10.1.2, 10.4.2, 10.4.3 ER 4.7: Cancelled. Information from this procedure has been incorporated into Procedure ER 3.3. ER 4.8: Cancelled. Information from this procedure has been incorporated into Procedure ER 3.2. CHAPTER 5: RADIOLOGICAL ASSESSMENT ER 5.1: Cancelled. ER 5.2: Site Perimeter and Offsite Monitoring and 10.1.2 Environmental Sampling G-4 SSREP Rev. 56

SEABROOK STATION REP SECTION ER 5.3: Operation of the Raddose-V 10.1.1 ER 5.4: Protective Action Recommendations 10.2 ER 5.5: Cancelled. Information from this procedure has been incorporated into Procedure ER 3.3. ER 5.6: Cancelled. Information from this procedure has been incorporated into Procedure ER 3.3. ER 5.7: Cancelled. Information from this procedure has been incorporated into Procedure ER 5.3. ER 5.8: Cancelled. Information from this procedure has been incorporated into Procedure ER 3.3. CHAPTER 6: RECOVERY ER 6.0 Recovery Planning 9.3 CHAPTER 7: CANCELLED ER 7.1: Cancelled. ER 7.2: Cancelled. Information from this procedure has been incorporated into Procedures ER 3.1 and ER 3.3. ER 7.3: Cancelled. Information from this procedure has been incorporated into Procedures ER 3.1 and ER 3.3. ER 7.4: Cancelled. Information from this procedure has been incorporated into Procedure ER 2.0. CHAPTER 8: CANCELLED ER 8.1 Cancelled. This procedure has been incorporated into the 12.4 Site Services Facilities Department Inventory Manual. ER 8.2: Cancelled. This procedure has been incorporated into the 12.2 Training Department ERO Program Description and Nuclear Training procedures. ER 8.3: Cancelled. This procedure has been incorporated into the 12.1 Radiological Emergency Preparedness Drill and Exercise Manual. ER 8.4: Cancelled. This procedure has been incorporated into the 12.3 Station Management Manual (SSMM) ER 8.5: Cancelled. This procedure has been incorporated into the 12.1.2.1 G-5 SSREP Rev. 56

SEABROOK STATION REP SECTION Site Services Facilities Department Inventory Manual ER 8.6: Cancelled. Information from this procedure has been incorporated into Procedure ER 8.4. ER 8.7: Cancelled. This procedure has been incorporated into a 9.2.2 Support Services department level procedure. CHAPTER 9: CANCELLED ER 9.1: Cancelled. This procedure has been incorporated into Procedures ER 3.4 and ER 3.5. G-6 SSREP Rev. 56

SUMMARY

OF CHANGES Rev. 56: (PCR 02386017 March 2022) Replaced Emergency Preparedness Drill and Exercise Manual (EPDE) with EP-AA-101-1000, Nuclear Division Drill and Exercise Procedure. Rev. 55: (PCR 02183129 February 2017) Cancelled ER 5.7 as there is now only one standard procedure for all Raddose V users (ER 5.3). Rev. 54: In Appendix G updated title to ER 3.5N and added ER 1.7 to list (AR#1721945) G-7 SSREP Rev. 56

APPENDIX H NUREG-0654/SEABROOK STATION RADIOLOGICAL EMERGENCY PLAN CROSS REFERENCE SSREP Rev. 47

NUREG-0654/SEABROOK STATION RADIOLOGICAL EMERGENCY PLAN CROSS REFERENCE NUREG-0654, REVISION 1 SEABROOK STATION REFERENCE SECTION REP SECTION A.1.a 8.6, and Figures 8.13 and 8.14 A.1.b 3.0, 8.0, 9.0 A.1.c Figure 3.2, Figures 8.1 through 8.6 and Figure 8.9 A.1.d Figures 8.1 through 8.6 and Figure 8.9, 9.0 and Appendix A A.1.e 7.1, Figure 7.1, 8.2.1, Figure 8.1, Figure 8.12 A.3 Appendix D A.4 8.0 and 9.0 B.1 8.0 and Appendix A B.2 8.2.1, 9.2 B.3 8.0, Figures 8.1 through 8.3 B.4 Appendix A, ER 1.2 (Sec. 2.1), ER 3.1 (Sec. 2.1), ER 3.3D (1.i.) B.5 8.0, Figure 8.15 B.6 8.0 and Figures 8.1 through 8.6 and Figure 8.9 B.7.a 8.4 and Appendix A B.7.b 8.5 and 8.6 B.7.c 8.7 B.7.d 11.3 B.8 6.1.4 and 8.6.3 B.9 8.6.1 and Appendix D C.1.a 8.6.2 C.1.b 3.4 and the National Response Framework, Nuclear/Radiological Incident Annex H-1 SSREP Rev. 47

NUREG-0654, REVISION 1 SEABROOK STATION REFERENCE SECTION REP SECTION C.1.c 3.4, 7.0 C.2.b 8.7 C.3 6.2.5 C.4 6.1.4, 6.1.6, 8.6.3, Appendix D D.1 5.0 D.2 5.0 E.1 3.2, Figure 3.1, 7.1, Figure 7.1 and 11.1 E.2 9.0 E.3 11.1, ER 1.2 and ER 2.0B E.4 a-n 11.1 and ER 2.0C E.6 11.2 and Appendix E E.7 11.1 and 11.3 F.1.a 7.0 F.1.b 7.0 F.1.c 7.0 F.1.d 7.0 F.1.e 7.0 and 9.2 F.1.f 7.0 F.2 7.0 and 10.5 F.3 12.1.2 G.1 11.3 G.2 11.3 G.3.a 11.3 G.3.b 6.1.5 H-2 SSREP Rev. 47

NUREG-0654, REVISION 1 SEABROOK STATION REFERENCE SECTION REP SECTION G.4.a 11.3 G.4.b 11.3 G.4.c 11.3 G.5 11.3 H.1 6.0 H.2 6.0 H.4 9.0 H.5 6.2.2 H.5.a 6.2.3 H.5.b 6.2.2 H.5.c 6.2.1 H.5.d 6.2.4 H.6.a 6.2.3 H.6.b 6.2.5 H.6.c 6.2.5 H.7 6.1.3 H.8 6.2.3.1 H.9 6.1.2 H.10 12.4 and Appendix F H.11 Appendix F H.12 6.1.3 and 10.1.2 I.1 5.0, 10.0 I.2 6.2, 10.0 I.3.a 6.2, 10.0 H-3 SSREP Rev. 47

NUREG-0654, REVISION 1 SEABROOK STATION REFERENCE SECTION REP SECTION I.3.b 6.2, 10.0 I.4 6.2.2, 10.0 I.5 6.2.3.1, 10.0 I.6 6.2.2, 10.0 I.7 6.0, 10.0 I.8 6.2.2, 10.1.2 and ER 5.2 I.9 10.1.2 I.10 6.2.2, 10.1.2 J.1.a Figure 9.1 and 10.4.2 J.1.b Figure 9.1 and 10.4.2 J.1.c Figure 9.1 and 10.4.2 J.1.d Figure 9.1 and 10.4.2 J.2 10.4.2 J.3 10.4.2 J.4 10.4.2 J.5 10.4.1 J.6.a 10.4.5 J.6.b 10.4.5 J.6.c 10.4.5 and Table 10.3 J.7 3.0, 10.2, Table 10.1 J.8 Appendix C J.10.a 4.2.3, Figure 4.2, Figure 4.4, Figure 4.6, Figure 4.7, 10.0 and Figure 10.2 J.10.b Table 4.1, Figure 4.4 and Figure 4.6 J.10.c 11.0 and Appendix E H-4 SSREP Rev. 47

NUREG-0654, REVISION 1 SEABROOK STATION REFERENCE SECTION REP SECTION J.10.m 10.2, Table 10.1 and Appendix C K.1.a 10.3, 10.4, 10.5 K.1.b 10.3, 10.4 K.1.c 10.3 K.1.d 10.4 K.1.e 10.4 K.1.f 10.5 K.1.g 10.5 K.2 10.3 K.3.a 10.3 K.3.b 10.3 K.5.a 10.4.4, ER 4.6 K.5.b 10.4.4 K.6.a 10.4.2 K.6.b 10.3, ER 4.3 K.6.c 10.3, ER 4.3 K.7 10.4.4 L.1 10.5 L.2 10.5 L.4 10.5 M.1 8.5, 9.3 and ER 6.0 M.2 8.5, 9.3, ER 6.0 M.3 8.5, 9.3 and ER 6.0 M.4 10.1.1 H-5 SSREP Rev. 47

NUREG-0654, REVISION 1 SEABROOK STATION REFERENCE SECTION REP SECTION N.1.a 12.1 N.1.b 12.1 N.2.a 12.1.2.1, 12.1.2.2 N.2.b 12.1.2.3 N.2.c 12.1.2.4 N.2.d 12.1.2.5 N.2.e 12.1.2.6 N.3.a 12.1.3 N.3.b 12.1.3 N.3.c 12.1.3 N.3.d 12.1.3 N.3.e 12.1.3 N.3.f 12.1.3 N.4 12.1.4 N.5 12.1.4 O.1 12.2 O.1.a 12.2.2 O.2 12.2 O.3 10.5 O.4.a-j 12.2 O.5 12.2 P.1 12.2.4 P.2 12.5 P.3 12.5 H-6 SSREP Rev. 47

NUREG-0654, REVISION 1 SEABROOK STATION REFERENCE SECTION REP SECTION P.4 12.3 P.5 12.3 P.6 Appendix G P.7 Appendix G P.8 Table of Contents P.9 12.3 P.10 12.3 H-7 SSREP Rev. 47}}