ML18102A533

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Revision 56 to Emergency Plan, MP-26-EPI-EPMP
ML18102A533
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 03/16/2018
From: Cloutier J
Dominion Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
MP-26-EPI-EPMP, Rev 56
Download: ML18102A533 (192)
v • d • e


Text

TIPCK02 PASSPORT DOCUMENT To DOCUMENT CONTROL DESK Facility MP Department TRANSMITTAL Address U.S. NUCLEAR REGULATORY COMMISSION DOCUMENT CONTROL DESK (7108)

WASHINGTON, DC 20555-0001 From CONTROLLED DOCUMENTS Date/Time 03/12/18 11:17 fln1 II ( 11111111 Trans No. 000163495 Transmittal Group Id: 1811215 Total Items: 00001 Item Facility Type Sub Document Number/ Title Sheet Revision Doc Date Copy # Media Copies

  • 0001 MP PROC EP MP-26-EPI-EPMP 056 99 p 01 MILLSTONE POWER STATION EMERGENCY PLAN Please check the appropriate response and return form to NDS Bldg 475/3 Millstone Power Station or Fax to 860-440-2057.

§ Date:

All documents received.

Documents noted above not received (identify those not received).

I no longer require distribution of these documents.

Signature: ----------------;-~--------

Administrative P cedure or Guidance and Reference Document Approval

';Dominion AD-AA-101 - Attachment 4 Page 1 of 1

  • 1. Document Number: 2. Revision: 3. Document Type:

MP-26-EPI-EPMP 56 [gj Administrative Procedure 0GARD 4.

Title:

Millstone Power Station Emergency Plan

5. Requestor(s) Print Name(s) I Locations 6. Date 7. Requester Phone Jerry Cloutier 12/18/17 2040
8. Document Request D New ~ Revision D Cancel D Supersede 0Temporary
9. Applicable Nuclear Station(s)

Millstone [gj North Anna D SurryO

10. Reason and Brief Description of Change:

Added 7.5, State Emergency Operations Center Deleted Joint Media Center 8.2.2.a., Fire Drills, revised schedule and conduct Updated letters of agreement Updated titles, references, definitions, and acronyms

11. Records Retention Requirements Affected? 12. Change Management:

0 Yes (Complete NRRS form from RM-AA-101) [gj No Attach Appropriate PI-AA-4000 Attachment(s)

13. Level of Use:

D Continuous Use D Reference Use [gj Information Use D Multiple Use Fleet Approval

14. Fleet Approval Required by: (Check one box only. Enter Peer Group Name, if applicable)

D Peer Grou OR D Functional Area Mana er FAM 15.. Printed Approver Name 16. Signature 17. Date N/A N/A N/A Site Approval

18. Implementation Prerequisites: (Items in addition to those listed on Document Traveler or Change Management Plan)
20. Date 1

1 /rz-1/.?

22. Site Approval (Print Name of FAM) .

David Smith

25. Facility.Safety Review Committee RlJquired?

0No (gjYes M1--IB

28. Site Vice President Required?

[gj No D Yes NOTE: The individual s ostin a new or revised document to EDMS are res onsible for ensurin Nuclear E-Forms is u dated.

31. Nuclear E-Forms Updated forSite(s)? 32. Nuclear E-Forms Updated Print Name/Signature 33. Date D MP D NA D SU [gj N/A
34. Document Number: 35. Revision: 37. Expiration Date MP-26-EPI-EPMP 56 NIA
  • Key: GARD-Guidance and Reference Document, EDMS-Electronic Document Management System Form No. 728620(0ct 2014)

a -p*

  • P' 1, Dominion Energy

Title:

Millstone Power Station Emergency Plan Emergency Plan Revision Number: Effective Date:

56 3/16/18 Revision Summary:

  • Section 5, minimum staffing list, changed Chief Technical Spokesperson to Millstone Emergency Offsite Representative
  • 5.1.4, added (EC)
  • 5.2.15 and 5.2.16, changed Chief Technical Spokesperson (CTS) to Millstone Emergency Offsite Representative (MEOR)
  • 5.2.22, added COEL
  • 5.3.2 and 5.3.19, changed CTS to MEOR
  • 5.3.17, added Staff Section 5.4, added acronym to titles; 5.4.5, changed CTS to MEOR Table 5-1, for Communications and Note o., changed Chief Technical Spokesperson (CTS) to Millstone Emergency Offsite Representative (MEOR); for Plant System Engineer Repair and Corrective Action, changed Generation Test Services (GTS)

Specialist to Control Operations Electrical (COEL) Specialist

  • Figure 5-1, changed CTS to MEOR (page 1 of 3); changed GTS to COEL and added MRCA under MRCA (page 2 of 3); changed Emergency Communicator to EC (page 3 of 3)
  • 6.1, changed Chief Technical Spokesperson to Millstone Emergency Offsite Representative
  • 6.2.4.h.5), changed Thermoluminescent Dosimeters (TLDs) to Dosimeters of Legal Record (DLRs)
  • 6.4.4, added Self Reading Dosimeters (SRDs); changed permanent recording dosimeters (TLDs) to dosimeter of legal record (DLRs)
  • 6.5.2, changed TLD to DLR and pocket dosimeter to SRD
  • 6.6, changed Chief Technical Spokesperson (CTS) to Millstone Emergency Offsite Representative (MEOR) and Dominion to Dominion Energy
  • 7.1, deleted PLC, changed number of control stations from two to one, and deleted alarm printer for Unit 1 CMS; added PLC for Unit 2 control room
  • 7 .2.2, changed Tagging Area to office area in the back of the Control Room
  • Added 7.5 State Emergency Operations Center
  • Deleted Joint Media Center (added into 7.5)

Revision Summary: (Continued)

Table 7-1, On-site, changed Unit 3 CR Tagging Area to Unit 3 Control Room (Office area in the back of the Control Room)

Figure 7-la, added Suffolk County (NY) to Affected Community Responsible Official Figure 7-lc, changed Dominion to Dominion Energy

  • 8.1.1, changed TR-MP-TPG-2400 to TR-AA-TPG-2400
  • 8.2.2.a., Fire Drills, revised schedule and conduct
  • 8.2.2.g., Post-Exercise Critique, reformatted
  • Appendix A, revised Radiological Control Area definition and added State Emergency Operations Center definition; updated acronyms
  • Appendix B, updated letters of agreement for Amtrak, Shipman's, Teledyne, Norwich Fire, Salem Fire
  • Figure C-5, added footnote for pedestrian route
  • Appendix D, deleted MP-26-EPA-FAP07 and RPM Section 2.3.4; added EP-AA-105; changed TR-MP-TPG-2300 and 2400 to TR-AA-TPG-2300 and 2400
  • Figure F-2, revised areas for Boiler, Mechanical, Waterford, and RL and changed FEMA to FEMA/DEEP
  • Appendix K, changed (TPG) 7.212 to TR-AA-TPG-2400

TABLE OF CONTENTS Section Page

  • List of Appendices ....................................................................................................................... viii List of Tables ................................................................................................................................. ix List of Figures ................................................................................................................................ xi
1. Concept of Emergency Operations ...................................................................................... 1-1 1.1 Description of the Millstone Emergency Planning Zones .............................................. 1-1 1.2 Interrelationships of State/Local/Licensee Emergency Plans ......................................... 1-2 1.3 Actions ............................................................................................................................ 1-2 1.4 Assistance ....................................................................................................................... 1-3 1.5 Public Notification ......................................................................................................... 1-3 1.6 Public Information Program ........................................................................................... 1-3
2. Applicability and Supporting Plans .................................................................................... 2-1
3. Section Intentionally Left Blank (Reserved) ....................................................................... 3-1
4. Classification System ............................................................................................................. 4-1
5. Emergency Response Organization ..................................................................................... 5-1 5.1 On-Shift Positions .......................................................................................................... 5-3 5.1.1 Shift Manager (SM) ............................................................................................ 5-3 5.1.2 Shift Technical Advisor (STA) .......................................................................... 5-4 5.1.3 Manager Of Control Room Operations (MCRO) ............................................... 5-4 5 .1.4 Emergency Communicator ................................................................................. 5-4 5.1.5 On-shift Operators .............................................................................................. 5-4 5.1.6 Health Physics Technicians (HP) ....................................................................... 5-4 5.1.7 Chemistry Technician ......................................................................................... 5-4 5.1.8 Security Shift Operations Supervisor and Security Personnel ........................... 5-4 5.1.9 Station Duty Officer (SDO) ................................................................................ 5-5 5.1.10 Fire Brigade ........................................................................................................ 5-5 5.1.11 First Aid Team .................................................................................................... 5-5
  • Revision 56 March 2018

TABLE OF CONTENTS Section 5.2 Minimum Staffing Positions .......................................................................................... 5-5 5.2.1 Director of Station Emergency Operations (DSEO) .......................................... 5-5 5.2.2 Assistant Director, Technical Support (ADTS) .................................................. 5-5 5.2.3 Manager of Technical Support Center (MTSC) ................................................. 5-6 5.2.4 Manager*of Operational Support Center (MOSC) ............................................. 5-6 5.2.5 Assistant Director, Emergency Operations Facility (ADEOF) ........................... 5-6 5.2.6 Manager of Radiological Consequence Assessment (MRCA) ........................... 5-7 5.2.7 Manager of Radiological Dose Assessment (MRDA) ....................................... 5-7 5.2.8 Manager of Communications (MOC) ................................................................ 5-7 5.2.9 Radiological Monitoring Team (RMT #2-NAP and SAP) ................................. 5-7 5.2.10 Radiological Monitoring Team (RMT #3-#4-#5) .............................................. 5-8 5.2.11 EOF HP Technician ............................................................................................ 5-8

  • 5.2.12 EOF Emergency Communicator (EC) ................................................................ 5-8 5.2.13 OSC - Assistant Radiation Protection Supervisor (ARPS) ................................ 5-8 5.2.14 Emergency Information Specialist (EIS) ............................................................ 5-8 5.2.15 Millstone Emergency Offsite Representative (MEOR) ...................................... 5-8 5.2.16 Nuclear News Manager (NNM) ......................................................................... 5-8 5.2.17 Manager of Resources (MOR) ........................................................................... 5-8 5.2.18 Technical Support Center-Reactor Engineer (TSCRE) ...................................... 5-9 5.2.19 Technical Information Coordinator (TIC) .......................................................... 5-9 5.2.20 Technical Support Center - Electrical Engineer (TSCEE) ................................. 5-9 5.2.21 Technical Support Center- Mechanical Engineer (TSCME) ............................. 5-9 5.2.22 Mechanic, Electrician, l&C Technician, COEL ................................................. 5-9 5.2.23 Corporate Support Director (CSD) ..................................................................... 5-9

TABLE OF CONTENTS Section 5.3 Full Staffing Positions .................................................................................................... 5-9 5.3.1 Control Room Data Coordinator (CRDC) .......................................................... 5-9 5.3.2 Technical Assistant (TA) .................................................................................... 5-9 5.3.3 Meteorological Assistant .................................................................................. 5-10 5.3.4 Technical Support Center- Shift Manager (TSCSM) ....................................... 5-10 5.3.5 Operational Support Center (OSC) Assistant ................................................... 5-10 5.3.6 CBETS Operator .............................................................................................. 5-10 5.3.7 Radiological Assessment Engineer (RAE) {two positions} ............................ 5-10 5.3.8 Radiological Communicators {two positions} (RADCOM) ............................ 5-10 5.3.9 Assistant Manager, Radiological Dose Assessment (AMRDA) {two positions} 5-10 5.3.10 Field Team Data Coordinator (FTDC) ............................................................. 5-10 5.3.11 Manager of Security (MOS) ............................................................................. 5-11

  • 5.3.12 Accident Management Team (AMT) ............................................................... 5-11 5.3.13 Regulatory Liaison (RL) ................................................................................... 5-11 5.3.14 Media Center Liaison (MCL) ........................................................................... 5-11 5.3.15 Technical Briefer (TB) ..................................................................................... 5-11 5.3.16 Radiological Briefer (RB) ................................................................................ 5-11 5.3.17 Offsite Monitoring Facility (OMF) .................................................................. 5-11 5.3.18 Station Emergency Preparedness Representative (SEPR) ................................ 5-11 5.3.19 Station Emergency Planning Liaison (SEPL) ................................................... 5-12 5.4 Corporate Support .................................................................... '. ................................... 5-12 5.4.1 Corporate Support Coordinator (CSC) ............................................................. 5-12 5.4.2 Corporate Plant Information Coordinator (CPIC) ............................................ 5-12 5.4.3 Corporate External Affairs Manager (CEAM) ................................................. 5-12

TABLE OF CONTENTS Section Page 5.4.4 Corporate Emergency Plan Specialist (CEPS) ................................................. 5-12 5.4.5 Corporate Executive Spokesperson (CES) ....................................................... 5-13 5.5 Other Organizations Providing Assistance ................................................................... 5-13 5.5.1 State/ Local Assistance .................................................................................... 5-13 5.5.2 Private Agency Assistance ............................................................................... 5-13 5.5.3 Federal Assistance ............................................................................................ 5-13

6. Emergency Measures ............................................................................................................ 6-1 6.1 Notification and Activation of Emergency Organizations ............................................. 6-1 6.2 Assessment Actions ......................................................................................................... 6-3 6.2.1 Initial Assessment ................................................................................................ 6-3 6.2.2 Protective Action Recommendations (PARs) .................................................... 6-3 6.2.3 Dose Assessment ................................................................................................ 6-4
  • 6.3 6.2.4 Release Rate and Dose Estimate Methodology .................................................. 6-6 6,2.5 Secondary Dose Assessment ............................................................................ 6-10 Corrective Actions ........................................................................................................ 6-10 6.3.1 Fire Fighting ..................................................................................................... 6-10 6.3.2 Damage Control, Repair and Decontamination ................................................ 6-10 6.4 Protective Actions ......................................................................................... ;.............. 6-11 6.4.1 On-site Protective Actions ................................................................................ 6-11 6.4.2 Use of On-site Protective Equipment and Supplies ......................................... 6-14 6.4.3 Contamination Control Measures ..................................................................... 6-14 6.4.4 Personnel Radiation Dose Determination ........................................................ 6-14 6.5 Aid to Affected Personnel ....................................................................................... :.... 6-15 6.5.1 Exposure Control Guidelines ........................................................................... 6-15 6.5.2 Emergency Exposure Control Guidelines for Off-Si~e Personnel.. .................. 6-15 Millstone Station Emergency Plan iv Revision 56 March 2018

TABLE OF CONTENTS Section Page 6.5.3 Decontamination .............................................................................................. 6-16 6.5.4 First Aid ............................................................................................................ 6-16 6.5.5 Medical Transportation .................................. :********************** .. ************************* 6-16 q.5.6 Medical Treat:Jnent. ........................................................................................... 6-17 6.6 Public Information ........................................................................................................ 6-17

7. Emergency Facilities and Equipment ................................................................................. 7-1 7.1 Control Room ................................................................................................................. 7-1 7 .1.1 Normal Operations ............................................................................................. 7-2 7.1.2 Alert and Notification ......................................................................................... 7-2 7.1.3 Communications ................................................................................................. 7-2 7.2 Emergency Operations Facility ...................................................................................... 7-3 7.2.1 Function .............................................................................................................. 7-3
  • 7.2.2 Location .............................................................................................................. 7-3 7.2.3 Structure and Habitability................................................................................... 7-3 7.2.4 Layout ........................................................................................ .-........................ 7-3 7.2.5 Communications ................................................................................................. 7-4 7.2.6 Power Supplies ................................................................................................... 7-4 7.2.7 Technical Data and Data Systems ...................................................................... 7-4 7.2.8 Records Availability and Management .............................................................. 7-4 7.3 Technical Support Center/Operational Support Center .................................................. 7-4 7.3.1 Function .............................................................................................................. 7-4 7.3.2 Location .............................................................................................................. 7-5 7.3.3 Structure and Habitability................................................................................... 7-5 7.3.4 Layout. .........................................................._....................................................._. 7-5

TABLE OF CONTENTS Section Page 7.3.5 Communications ................................................................................................. 7-6 7.3.6 Power Supplies ................................................................................................... 7-6 7.3.7 Technical Data and Data Systems ...................................................................... 7-6 7 .3. 8 Records Availability ........................................................................................... 7-6 7.4 Operational Support Center (OSC) and OSC Assembly Area ....................................... 7-6 7.4.1 Function .............................................................................................................. 7-6 7 .4.2 Location and Size ............................................................................................... 7-6 7.4.3 Structure and Habitability................................................................................... 7-7 7.4.4 Communications ................................................................................................. 7-7 7.4.5 Emergency Equipment ....................................................................................... 7-7 7 .5 State Emergency Operations Center. .............................................................................. 7-8 7.5.1 Function .............................................................................................................. 7-8

  • 7.5.2 7.5.3 7.5.4 Location .............................................................................................................. 7-8 Structure and Habitability................................................................................... 7-8 Layout ................................................................................................................. 7-8 7.5.5 Communications ................................................................................................. 7-8 7.5.6 Technical Data and Data Systems ...................................................................... 7-9 7.5.7 Records Availability and Management .............................................................. 7-9 7.6 Emergency Equipment ................................................................................................... 7-9 7.6.1 Emergency Response Data System (ERDS) ....................................................... 7-9
7. 7 Security Posts ................................................................................................................. 7-9 7.8 Alternate Location ........................................................................................................ 7-10 7.9 Communication Systems .............................................................................................. 7-10 7.10 Assessment Facilities ................................................................................................... 7-11 7.11 First Aid and Medical Facilities ................................................................................... 7-11 .

Millstone Station Emergency Plan vi Revision 56 March 2018

TABLE OF CONTENTS Section 7.12 Damage Control Equipment ......................................................................................... 7-11 7.13 Meteorological Data Acquisition ................................................................................. 7-11 7.14 funsbrook Corporate Support Center (ICSC) ............................................................... 7-12

8. Maintaining Emergency Preparedness ................................................................................ 8-1 8.1 Training .......................................................................................................................... 8-1 8.1.1 SERO Training ................................................................................................... 8-1 8.1.2 Off-Site Emergency Response Training ............................................................. 8-2 8.1.3 Additional Emergency Preparedness Training ................................................... 8-2 8.2 Tests, Drills, and Exercises ............................................................................................ 8-3 8.2.1 Off-Site and On-Site Testing of the Notification, Communication, and Alerting Systems ............................................................................................................... 8-3 8.2.2 Additional Tests, Drills, and Exercises ........................ ;..................................... 8-4 8.3 Administration of Station Emergency Plan and Procedures .......................................... 8-7 8.4 Public Information Programs ......................................................................................... 8-8
  • 8.5 Media Information Program ........................................................................................... 8-8
9. Recovery ................................................................................................................................. 9-1 9.1 Recovery Phase............................................................................................................... 9-1 9.2 Recovery Organization ................................................................................................... 9-1 9.2.1 Site Vice President - Millstone .......................................................................... 9-1 9.2.2 Director of Recovery Operations (DRO) ............................................................ 9-1 9.2.3 Manager of Technical Support ........................................................................... 9-1 9.2.4 Manager of Plant Operations .............................................................................. 9-2 9.2.5 Manager of Radiation Control/Radwaste ........................................................... 9-2 9.2.6 Manager of Engineering Systems ....................................................................... 9-3 9.2.7 Advisory Support Staff ....................................................................................... 9-3 9.2.8 Corporate External Affairs Manager .................................................................. 9-3

TABLE OF CONTENTS Section *Page 9.2.9 Licensing Department. ........................................................................................ 9-3 9.2.10 Millstone Representative in the SEOC and Joint Media Center ........................ 9-3

TABLE OF CONTENTS Section LIST OF APPENDICES Appendix A - Definitions, Abbreviations and Acronyms ...................................................... A-1 Appendix B - Letters of Agreement ........................................................................................ B-1 Appendix C -Maps of Plume and Ingestion Exposure EPZ, Locations of On-Site And Off-Site Radiological Monitoring Stations, Station Evacuation Routes ...................................... C-1 Appendix D - Supporting Procedures List ............................................................................. D-1 Appendix E - Millstone Emergency Equipment.. .................................................................... E-1 Appendix F - Diagrams and Arrangement of Emergency Facilities ....................................... F-1 Appendix G - Cross-Reference To NUREG-0654 Criteria ......................................... ,.......... G-1 Appendix H - Radiological Assessment Equipment and Facilities ........................................ H-1 Appendix I - Emergency Action Level Scheme ....... ;............................................................... I-1 Appendix J - Evacuation Time Estimate: Plume Exposure Pathway ....................................... J-1 Appendix K- SERO Personnel Training Summary ................................................................ K.:1

TABLE OF CONTENTS

  • Section LIST OF TABLES 1-1 Off-Site Host Community and Reception Centers ................................................................ 1-4 2-1 Supporting Plans and Sources ............................................................................................... 2-1 4-1 Unusual Event - Licensee Actions ......................................................................................... 4-2 4-2 Alert - Licensee Actions ........................................................................................................ 4-3 4-3 Site Area Emergency- Licensee Actions .............................................................................. 4-4 4-4 General Emergency- Licensee Actions ................................................................................. 4-5 5-1 Station Emergency Response Organization ... ;..................................................................... 5-14 6-1 Emergency Exposure Limits ................................................................................................ 6-18 7-1 Locations of Emergency Response Centers ......................................................................... 7-11 H-1 On-Site Assessment Equipment and Facilities .................................................................... H-2 H-2 Off-Site Assessment Equipment and Facilities ................................................................... H-9 J-1 Millstone Evacuation Time Estimate Summary ..................................................................... J-2

TABLE OF CONTENTS Section LIST OF FIGURES 1-1 Emergency Response Organizations Responsibilities ........................................................... 1-5 1-2 Responsibilities of State and Local Agencies For The Various Incident Classifications ...... 1-6 1-3 Licensee Emergency Response Facility Responsibilities ...................................................... 1-7 5-1 Organization of Station Emergency Management Personnel .............................................. 5-19 7-1 a Notification of Emergency Response Organizations ......................................................... 7-12 7-lb NRC Emergency Notification System and Health Physics Network ................................ 7-13 7- lc Lines of Communications Between Emergency Response Centers Millstone Station ...... 7-14 9-1 Recovery Organization .......................................................................................................... 9-4 C-1 Map of Millstone Emergency Planning Zone, Host Communities and Evacuation Routes .C-2 C-2 Locations of On-Site and Off-Site Radiological Monitoring Stations .................................. C-3 C-3 Map of Millstone 10 Mile Emergency Planning Zone .......................................................... C-4 C-4 Map of Millstone 50 Mile Emergency Planning Zone .......................................................... C-5 C-5 Map of Millstone Station Evacuation Routes ....................................................................... C-6 E-1 Millstone Emergency Equipment Summary ......................................................................... E-2 F-1 Diagram ofTSC / OSC Layout ............................................................................................. F-2 F-2 Diagram of Emergency Operations Facility .......................................................................... F-3 F-3 Diagram of OSC Assembly Area Layout .............................................................................. F-4

1. Concept of Emergency Operations
  • 1.1 Description of the Millstone Emergency Planning Zones The Millstone Power Station is located on Long Island Sound within the Town of Waterford, Connecticut. Millstone has three nuclear power plants: Unit 1, a boiling water reactor, which is permanently shutdown and defueled 1 and being decommissioned; and Units 2 and 3 which are pressurized water reactors. Millstone also has an Independent Spent Fuel Storage Installation (ISFSI), which is located east of the facility within the Protected Area. Millstone has an approximate 10-mile Emergency Planning Zone (EPZ) for the plume exposure pathway and an approximate SO-mile planning zone for the Ingestion Exposure Pathway (IPZ). Millstone Station occupies approximately 500 acres and is located 3.2 miles west-southwest of New London and 40 miles southeast of Hartford.

Local communities within the Millstone plume exposure pathway EPZ include East Lyme, Fishers Island (NY), Groton City, Groton Town, Ledyard, Lyme, Montville, New London, Old Lyme, and Waterford. The Plum Island Animal Disease Center, while physically located within 10 miles of Millstone, is a non-residential federal facility. There are two states within the plume exposure pathway EPZ, Connecticut and New York. The states within the IPZ are Connecticut, Rhode Island, and New York (see Appendix C).

Although a small portion of Massachusetts is within the SO-mile radius of Millstone, this area has intentionally been omitted from the Emergency Plan due to the distance from the site and the insignificant amount of land area involved. The Federal Emergency Management Agency (FEMA) has agreed that Massachusetts shall be excluded from the Millstone approximate SO-mile IPZ.

The Millstone Plume EPZ is primarily a residential area, with some urban sections. Peak population totals, including year round residents, seasonal residents, and transients are approximately 205,600 (based on 2010 census data). Appendix J provides a population distribution within the approximate 10-mile EPZ.

The Millstone approximate 10-mile EPZ contains three major industrial facilities: Dow Chemical Corporation (Ledyard), Pfizer Corporation and Electric Boat Division of General Dynamics Corporation (Groton); an air transportation facility (Groton/New London Airport); four military installations: U.S. Naval Submarine Base (Groton), U.S.

Coast Guard Academy (New London), Connecticut National Guard Camp and Stone's Ranch Military Reservation (East Lyme); and the State of Connecticut maintained York Correctional Institute (East Lyme).

fu accordance with 10CFR50.82(a)(l)(i) and 10CFR50.82(a)(l)(ii), Millstone Unit 1 submitted certification to the NRC that as of July 1, 1998, power operations had permanently ceased and fuel had been permanently

  • removed from the reactor vessel.

1-1 Millstone Station Emergency Plan Revision 56 March2018

1.2 Interrelationships of State/Local/Licensee Emergency Plans

  • The objective of the Millstone Power Station Emergency Plan is to delineate assessment and protective actions to be taken to minimize the consequences of an incident to the health and safety of the public. Separate plans exist for the licensee, state and local communities within the plume exposure pathway EPZ and the host communities (Table 1-1) to which populations will evacuate. The plans encompass emergency preparedness actions taken by the licensee, the State (all applicable agencies) and the affected local communities. These plans are linked together by a broad overall concept of operations through mutual planning and common notification and assessment procedures.

Various federal agencies including the Nuclear Regulatory Commission (NRC), Federal Emergency Management Agency (FEMA), Department of Energy (DOE), and Environmental Protection Agency (EPA) also respond to an emergency in accordance with established federal plans. The licensee will maintain contact with the NRC, the Connecticut Department of Energy and Environmental Protection (DEEP), and the Connecticut Division of Emergency Management and Homeland Security (DEMHS). The DEMHS is responsible for coordinating emergency activities with state and federal agencies and notification of adjoining state governments.

Figure 1-1 illustrates general responsibilities of state, local and licensee emergency organizations. Implementing procedures have been developed to ensure planning effectiveness.

The licensee, state, and local emergency plans include responsibilities and functions and

  • 1.3 identify resources for each organization. Local radiological emergency response procedures are reviewed and approved by appropriate government officials. State and local emergency preparedness programs include training and periodic drills or exercises.

Actions Figure 1-1 outlines responsibilities and actions of the licensee, state, and local communities. Figure 1-2 outlines actions and responsibilities of state and local agencies.

Figure 1-3 outlines actions and responsibilities associated with each emergency response facility. The actions escalate through each successive emergency classification.

The licensee response to an incident includes: assessment of plant conditions, incident classification, notification of state and local officials, mitigation of plant system degradation, and assessment of accident consequences. The licensee will classify the incident in accordance with federal guidelines and the State of Connecticut Nuclear Incident Classification Scheme. The licensee will notify designated Connecticut and New York state and local officials and licensee personnel, as appropriate, within 15 minutes of an incident classification. In Connecticut, the state agencies notified are the DEMHS, the State Police and the DEEP, as well as officials in the local EPZ communities. In New Yotk, this notification is provided to Suffolk County and Fishers Island, while a courtesy notification is provided to the State of New York. NRC notification by the licensee is completed via telephone .

After initial classification, the licensee ensures that plant conditions are evaluated and

  • 1.4 updated information or event reclassification is completed as necessary .

Assistance State agencies will mobilize resources as necessary to support local communities in protective action implementation. The Director of DEMHS is authorized to request assistance from federal agencies as necessary.

The licensee emergency response facilities provide office space for federal agency responders.

1.5 Public Notification Public protective actions will be implemented by use of the Public Alerting System and the Emergency Alert System (EAS). The Public Alerting System consists of electronic sirens at various locations within the Plume EPZ. Procedures for providing prompt notification and information to the public are contained within the State Radiological Emergency Response Plan (RERP). Local agencies will initiate responses to implement and support the protective actions. In the event evacuation is necessary, reception centers that are greater than 15 miles from the station have been designated (Table 1-1).

1.6 Public Information Program A public information program has been developed to inform EPZ populations of actions to be taken during an emergency. This program, as described in Section 8.0, has been developed for the media and general population and provides general radiological and emergency response information .

Table 1-1

  • Off-Site Host Community and Reception Centers Local Community Host Community-Reception Facility East Lyme New Haven - Southern Connecticut State University Moore Fieldhouse Fishers Island, New York Windham - Windham High School Groton, City of Norwich- Norwich Technical High School Groton, Town Norwich - Norwich Technical High School Ledyard Storrs - University of Connecticut Fieldhouse Lyme New Haven - Southern Connecticut State University Moore Fieldhouse '

Montville East Hartford - East Hartford High School New London Windham - Windham High School Old Lyme New Haven - Southern Connecticut State University Moore Fieldhouse Waterford East Hartford - East Hartford High School

Figure 1-1

  • 1.

2.

Emergency Response Organizations Responsibilities A. Licensee Responsibilities Classification of event.

Activation of on-site TSC, OSC and EOF within 60 minutes of ALERT or higher level incident notification

3. Notification of licensee, State of Connecticut, State of New York (Suffolk County) and EPZ communities.
4. On-site mitigation actions.
5. On-site corrective actions.
6. Protective Action recommendations to the State of Connecticut, as required.
7. Off-site radiological monitoring.
8. Assist State of Connecticut environmental sampling program.

B. State of Connecticut Responsibilities

1. Activation of State EOC and Joint Media Center at SITE AREA EMERGENCY or higher level incident notification (standby at ALERT).
2. Notification of host communities.
3. Notification of Rhode Island and New York (50-mile EPZ states).
4. Protective action decision making after declaration of State of Emergency by the Governor.
5. Activation of Emergency Alert System (standby at ALERT, activate at SITE AREA EMERGENCY or higher level incident notification).
6. Off-site radiological monitoring team deployment and environmental sample collection.
7. Implementation of the Traffic Management Plan for affected areas, as required .

C. 10-Mile EPZ Communities

1. Activation of EOCs at SITE AREA EMERGENCY and higher level incident notification (standby at ALERT).
2. Protective action decision making prior to declaration of State of Emergency by Governor.
3. Activation of the Public Alert System (sirens) at SITE AREA EMERGENCY and higher level incident notification in coordination with Emergency Alert System activation.
4. Implementation of protective actions.

D. Host Communities

1. Standby at SITE AREA EMERGENCY (as directed)
2. At the direction of the State DEMHS, activate reception center and shelter areas at GENERAL EMERGENCY incident.

E. 50-mile JPZ States

1. Activate EOCs at SITE AREA EMERGENCY (Standby at ALERT) level.
2. Monitor food pathways.
3. Implement ingestion pathway protective actions .

Figure 1-2 Responsibilities of State and Local Agencies for the Various Incident Classifications UNUSUAL EVENT*

ALERT**

  • All agencies acknowledge SITE AREA EMERGENCY ** All agencies Standby GENERAL EMERGENCY I

I I I I I Department of Energy Division of and Environmental Emergency Local Chief Department of Public Governor Protection - Management and Executives Safety Division of Radiation Homeland Security Direct actions of all State Conduct independent Disseminate emergency data Execute and direct Serve as backup agencies. assessment of the incident to local, State, and Federal emergency protective communications link and/or respond with agencies. actions within their between the site and State Coordinate media releases. assistance. jurisdiction. EOG.

Maintain communications Declare a State of Recommend public with towns and respective Public Alert (siren) system Provide traffic and access Emergency as necessary protective actions, as DEMHS Area offices. activation. control.

and assume overall necessary.

command of State and Coordinate services, material Further duties as defined in Assist local police in local emergency response Deploy radiological support and manpower to the RERP. evacuation of residents in activities. monitoring teams to affected towns. affected areas.

areas, as necessary, for radiation measurements. Activate State EAS, as necessary.

Provide radiation monitoring support to the towns.

Notify and record the actions NOTE: In case of RADIOACTIVE MATERIALS of other State agencies.

INCIDENT OR GENERAL INTEREST EVENT only the Department of Energy and Environmental Activate host communities.

Protection will be notified per the State RERP.

1-6 Millstone Station Emergency Plan Revision 56 March 2018

Figure 1-3

  • Control Room Licensee Emergency Response Facility Responsibilities (ALERT'or higher event classifications)
  • hritial incident classification2
  • Implement mitigation actions
  • Implement corrective actions
  • Declare incident classification changes, as necessary
  • Perform notifications, develop and transmit incident reports 2
  • On-Shift Dose assessment
  • hritial NRC notification (may be done from EOF)

Emergency Operations Facility (EOF)

  • Overall Command and Control
  • Declare incident classification changes (Director of Station Emergency Operations)
  • Communications with NRC, SEOC, DEEP, and local communities
  • Notify state and local officials (notifications and incident reports)
  • Provide protective action recommendations (PARs) to State DEEP
  • Direct off-site radiological monitoring teams and dose assessment activities Co-located Technical Support Center/Operational Support Center (TSC/OSC)
  • Provide engineering and accident management support to Control Room and emergency response staff
  • Provide input on incident classification changes to Director of Station Emergency Operations
  • Prioritize TSC/OSC assessment and repair activities in coordination with Control Room
  • Direct on-site mitigation actions
  • Direct on-site corrective actions
  • Direct on-site protective actions Operational Support Center Assembly Area (OSC AA)
  • Assemble and brief/debrief emergency teams
  • Coordinate emergency team activities with the TSC/OSC and Control Room State Emergency Operations Center (SEOC)
  • Provides direct interface with state officials
  • Provides representative to the Joint Media Center Innsbrook Corporate Support Center (ICSC)
  • Provides technical support
  • Drafts news releases and obtains executive approval of news releases
  • Provides Corporate logistical assistance
  • Activated upon declaration of an ALERT or higher at Millstone.

2 Incident classifications of UNUSUAL EVENT require classification, notification and completion of incident

  • report only.

1-7 Millstone Station Emergency Plan Revision 56 March 2018

2. Applicability and Supporting Plans
  • This Plan applies to the Millstone Station Emergency Response Organization in the event of an incident at the Millstone Power Station. This Plan is in agreement with the affected state and local community plans. The supporting plans and their sources are listed in Table 2-1.

Table 2-1 Supporting Plans and Sources Plan Source

1. State of Connecticut Radiological Emergency State of Connecticut Division of Emergency Management Response Plan and Homeland Security, State Armory Hartford, Connecticut
2. State Agency Procedures State of Connecticut Di vision of Emergency Management and Homeland Security, State Armory Hartford, Connecticut
3. New York State Radiological Emergency New York State Disaster Preparedness Commission Preparedness Plan Albany, New York
4. State of Rhode Island Ingestion Exposure Rhode Island Emergency Management Agency Cranston, Pathway Emergency Response Plan RI
5. Local Community Procedures: Local Community Emergency Management Agencies
  • Town of East Lyme
  • City of Groton
  • Town of Groton
  • Hamlet of Fishers Island (NY)
  • Town of Ledyard
  • Town of Lyme 0 Town of Montville
  • City of New London
  • Town of Old Lyme
  • Town of Waterford
6. Host Community Procedures: Local Host Community Emergency Management
  • Town of East Hartford
  • UCONN I Storrs
  • City of New Haven
  • City of Norwich
  • Town of Windham
7. Lawrence and Memorial Hospital Master Lawrence and Memorial Hospital New London, Emergency Preparedness Manual,Section II, Part Connecticut K, Radiation Accident Plan
8. Treatment and Decontamination of Radioactively Middlesex Hospital Middletown, Connecticut Contaminated Patient(s) at Middlesex Hospital
9. Manual of Protective Action Guides and EPA-400-R-92-001 U.S. Environmental Protection Agency Protective Actions for Nuclear Incidents
3. Section Intentionally Left Blank (Reserved)
4. Classification System
  • An UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY is declared as required by the emergency assessment procedure. Each emergency classification has one or more corresponding state posture codes. Within each classification is a description of the conditions and parameter values which are applicable to classifying the incident. This classification approach is consistent with the NUMARC or NEI methods.

The State RERP requires that incidents be assigned a state posture code at the time of classification. The state plan also defines non-emergency "General Interest Events" and "Radioactive Materials Incidents," which require reporting. This scheme has been adopted by the state agencies and the local communities in the Millstone EPZ. Certain federal classifications and their corresponding posture codes include an associated public protection action recommendation. The station will report the incident classification and a state posture code during an event to local and state authorities.

The emergency classification description, posture codes, discussion, and corresponding licensee actions are also given in Table 4-1 (UNUSUAL EVENT), Table 4-2 (ALERT), Table 4-3 (SITE AREA EMERGENCY) and Table 4-4 (GENERAL EMERGENCY).

The nuclear incident classification description and associated posture code scheme is defined in the State RERP and described in emergency procedures.

Incident classifications are driven by unit specific Emergency Action Level (EAL) tables.

  • Example EAL tables are provided in Appendix I. The emergency classification and action level scheme meet I0CFR50.47(b)(4) requirements.

Once indications are available to plant operators that an emergency action level has been exceeded, the event is promptly assessed and classified, and the corresponding emergency classification level is declared. This declaration occurs as soon as possible and within 15 minutes of when these indications become available.

An analysis of the potential radiological impact of an accident at Unit 1 i_n the permanently defueled condition has been conducted. Based on this analysis, any potential release is not expected to exceed the EPA PAG exposure levels beyond the exclusion area boundary. For this reason, only the UNUSUAL EVENT or ALERT classifications apply at this unit.

Table 4-1

  • Class Description Unusual Event - Licensee Actions NOTIFICATION OF UNUSUAL EVENT (State Posture Code: DELTA-TWO [if radiation release] or DELTA-ONE): 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. j No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs.

Actions

1. Assessment of conditions and initiation of actual corrective responses, as appropriate.
2. Notification of the Innsbrook Corporate Security Control Center.
3. Notification of the appropriate Connecticut and New York state agencies and local communities (responsible local officials) within the plume exposure EPZ.
4. Notification of the appropriate licensee personnel and NRC.
5. Augmentation of on-shift resources, as appropriate.
6. Periodic event status updates are provided to off-site authorities.
7. Reassessment of conditions and a revised event classification, as appropriate.
8. A close-out report is provided with verbal summary to off-site authorities, followed by a written summary to the NRC as required by 10 CFR 50.73, as appropriate .

Table 4-2

  • Class Description Alert - Licensee Actions ALERT (State Posture Code: CHARLJE-ONE): 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 intentional malicious dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

Actions

1. Assessment of conditions and initiation of actual corrective responses, as necessary.
2. Notification of the hmsbrook Corporate Support Center (ICSC) via the Corporate Security Control Center.
3. Precautionary dismissal of nonessential station personnel.
4. Notification of the appropriate Connecticut and New York state agencies and local communities (responsible local officials) within the plume exposure EPZ.
5. Activation of the Station Emergency Response Organization (SERO) and appropriate emergency response facilities (ERFs)
6. Establish communications with the SEOC in Hartford, if activated.
7. Notification of the NRC.
8. Deployment of on-site and off-site radiological monitoring teams (RMTs).
9. Periodic event status updates are provided to off-site authorities.
10. Periodic meteorological data summaries and dose assessments are developed and provided to off-site authorities.
11. Reassessment of conditions and a revised event classification, as appropriate.
12. An event report by verbal summary is provided to off-site authorities followed by a written summary to the NRC as required by 10 CFR 50.73, as appropriate .

Table 4-3

  • Class Description Site Area Emergency - Licensee Actions SITE AREA EMERGENCY (State Posture Code: CHARLIE-TWO): Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or security events that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents 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 except near the site boundary.

Actions

1. Assessment of conditions and initiation of corrective responses, as necessary.
2. Notification of the Innsbrook Corporate Support Center (ICSC) via the Corporate Security Control Center.
3. Evacuation of nonessential personnel at the station.
4. Implement accountability of station personnel, as required.
5. Notification of the appropriate Connecticut and New York state agencies and local communities (responsible local official) within the plume exposure EPZ.
6. Activation of the Station Emergency Response Organization (SERO) and ERFs.
7. Establish communications with the SEOC in Hartford, when activated.
8. Notification of the NRC.
9. J?eployment of on-site and off-site RMTs.
10. Periodic event status updates are provided to off-site authorities.
11. Periodic meteorological data summaries and dose assessments are developed and provided to off-site authorities.
12. Reassessment of conditions and revised event classification, if appropriate.
13. An event report by verbal summary is provided to off-site authorities followed by a written summary to the NRC as required by 10 CFR 50.73, as appropriate .

Table 4-4

  • Class Description General Emergency - Licensee Actions GENERAL EMERGENCY (State Posture Code: ALPHA [significant radiation release] or BRAVO): Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or security events that result in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels off-site for more than the immediate site area.

Actions

1. Assessment of conditions and initiation of corrective responses, as necessary.
2. Notification of the Innsbrook Corporate Support Center (ICSC) via the Corporate Security Control Center. *
3. Evacuation of nonessential personnel at the station.
4. Implement accountability of station personnel, as required.
5. Notification of the appropriate Connecticut and New York state agencies and local communities (responsible local official) within the plume exposure EPZ.
6. Activation of the Station Emergency Response Organization (SERO) and ERFs.
7. Establish communications with the SEOC in Hartford, when activated.
8. Notification of the NRC.
9. Deployment of on-site and off-site RMTs.
10. Periodic event status updates are provided to off-site authorities.
11. Periodic meteorological data summaries and dose assessments are developed and provided to off-site authorities.
12. Provide protective action recommendations to the SEOC.
13. An event report by verbal summary is provided to off-site authorities followed by a written summary to the NRC as required by 10 CFR 50.73, as appropriate .
5. Emergency Response Organization
  • This section describes the Station Emergency Response Organization (SERO). The SERO (Figure 5-1) replaces and prevails over the normal station organization. Information regarding the structure of the normal operating organization is presented in Section 1.0 of the "Dominion Nuclear Facility Quality Assurance Program Description" (DOM-QA-1) and is incorporated in this document by reference.

A detailed analysis of on-shift personnel assigned emergency plan implementation functions was performed under provisions of 10 CPR 50 Appendix E Part IV.A.9. This analysis determined the staff complement listed in the on-shift column of Table 5-1 can adequately perform required emergency response actions in a timely manner until augmenting SERO staff is required to arrive. This analysis considered a spectrum of events, including FSAR Condition IV events requiring augmented SERO response, a probable aircraft threat, a design basis threat, a fire requiring Control Room evacuation and remote shutdown, a station black out, etc. This staffing analysis is incorporated by reference as a part of this emergency plan.

Personnel are assigned to the SERO based on their normal job qualifications and other specialized training. Personnel assigned receive Emergency Plan training based on their specific emergency functions. The Nuclear Training Department maintains a Training Procedure Description that specifies required training for each SERO function.

The SERO consists of on-shift staff, minimum staffing, and full staffing. The minimum SERO staffing necessary to activate the ERFs consists of the on-shift and minimum staffing positions

  • identified in Table 5-1. The DSEO has the discretion to relieve the CR-DSEO and authorize ERP activation with less than minimum staffing when the necessary functional areas are filled. The specified positions are in accordance with NUREG-0654, Planning Standard B, Table B-1. The SERO personnel identified as full staffing are additional personnel beyond the required minimum, used to enhance the emergency response. The full staffing emergency positions will report as soon as possible after acknowledging notification with a goal of filling these positions within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The SERO is activated upon declaration of an ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY. The on-shift SERO personnel are then supplemented by minimum and full staffing, reporting as indicated on Table 5-1. Additional personnel resources, outside the SERO staff, may be activated, as needed.

The SERO is described in Table 5-1 and Figure 5-1. Table 5-1 illustrates the relationship between emergency and normal positions, describes major tasks, functional areas, emergency locations, and indicates the emergency position type (i.e. on-shift, minimum staffing, or full staffing). The normal on-shift staff complement applies to operating modes. During shutdown, refueling or permanently defueled condition, the on-shift staff may be reduced to the minimum shift staff composition delineated in the administrative controls section of the unit Technical Specifications.

Procedures detailing responsibilities for the various SERO staff positions are listed in Appendix D, as applicable .

This section also includes brief descriptions of the state, local and other organizations that would

  • provide assistance upon request.

Appendix B contains copies of letters of agreement from these organizations.

The on-shift/on-site positions are part of the normal station organization, which includes:

  • Shift Manager/Certified Fuel Handler (CFH)
  • Shift Technical Advisor (Unit 2 and Unit 3)
  • Work Control Senior Reactor Operator (SRO)
  • Unit Supervisor (Unit 2 and Unit 3)
  • Control Operators (Unit 2 and Unit 3)
  • Plant Equipment Operators (Unit 2 and Unit 3)
  • Health Physics Technicians (same as Radiation Protection Technicians)
  • Chemistry Technician
  • Security Shift Operations Supervisor and Security Personnel
  • Station Duty Officer
  • Fire Brigade
  • First Aid Team
  • The minimum staffing management positions include the following:
  • Director of Station Emergency Operations
  • Assistant Director, Emergency Operations Facility
  • Assistant Director, Technical Support (Unit 2, 3)
  • Manager of Radiological Consequence Assessment
  • Manager of Radiological Dose Assessment
  • Manager of Communications (Unit 2, 3)
  • Manager of Operational Support Center (2 Positions)
  • Millstone Emergency Offsite Representative
  • Nuclear News Manager
  • Manager of Resources
  • Emergency Information Specialist
  • Corporate Support Director

The Millstone SERO positions are described below:

  • 5.1 On-Shift Positions 5.1.1 Shift Manager (SM)3 The Shift Manager initially assumes command of the SERO as the Control Room DSEO (CRDSEO) following UNUSUAL EVENT or higher classification. In this position, the Shift Manager has the authority and responsibilities of the DSEO.

Due to the numerous responsibilities assigned the Shift Manager at the onset of an emergency, actions shall be prioritized as follows:

(1) ensure safe operation of the plant, (2) ensure immediate notification requirements are met, (3) obtain operational and radiological assessment of the emergency, and (4) perform additional emergency actions as directed by procedures as time and conditions permit.

An SRO shall assume the responsibilities of the SM if the SM should become incapacitated or otherwise unable to fulfill the responsibilities of CRDSEO. If this is required, some delay in completing the prioritized actions is expected. However, assistance is available from the Station Duty Officer and the unit STA. After being relieved by another qualified DSEO, the Shift Manager becomes the Manager of Control Room Operations (MCRO). The following CRDSEO responsibilities cannot be delegated:

  • Event classification4
  • Initiation of station emergency response
  • Authorization of mitigation and repair activities.
  • Command and control of station emergency response.
  • Approval of off-site Protective Action Recommendations.
  • Approval of on-site evacuation.
  • Authorization of emergency exposures.
  • Authorization of off-site notifications.

For a Unit 1 event, the Unit 2 SM/CFH functions as the CRDSEO.

3 For Unit 2, the SM is also a qualified Certified Fuel Handler (SM/CFH).

4 The Unit 2 CR DSEO will also classify events specific to Unit I.

5-3 Millstone Station Emergency Plan Revision 56 March 2018

5.1.2 Shift Technical Advisor (STA)

  • The STA is responsible for the analysis of operational data5
  • 5.1.3 Manager Of Control Room Operations (MCRO)

The Manager of Control Room Operations responsibilities include control room operations, interface with ADTS concerning plant status and changing conditions and recommendations for classification changes and corrective actions. The MCRO is also responsible for determining entry conditions into the Severe Accident Management Control Room Initial Response Guidelines and implementation of the Severe Accident Management Guidelines as required.

For a Unit 1 event, the Unit 2 CRDSEO becomes the MCRO.

5.1.4 Emergency Communicator (EC)

The Emergency Communicator is responsible for conducting emergency notifications and activating ERDS.

5.1.5 On-shift Operators For an operating unit, the on-shift Unit Supervisor (US), Control Operators (CO) and Plant Equipment Operators (PEO) perform plant related functions in accordance with unit and Station procedures, and as directed by the SM/MCRO .

The PEOs provide basic on-shift mechanical and electrical maintenance functions, in addition to Radwaste-operations. 6 5.1.6 Health Physics Technicians (HP)

The Health Physics Technicians provide initial in-plant and on-site radiological support actions as RMT #1.

5.1.7 Chemistry Technician The Chemistry Technician provides on-shift dose assessment, chemistry support and is available to assist control room personnel in other actions as directed.

5.1.8 Security Shift Operations Supervisor and Security Personnel The Security Shift Operations Supervisor performs security related functions in accordance with unit and Station procedures, and as directed by the SM/MCRO.

The Security Shift Operations Supervisor is assisted by security personnel in providing site access control and accountability.

5 This position is not required for a permanently defueled unit.

6 For a permanently defueled unit, an on-shift Unit 2 operator (licensed or non-licensed) performs these functions .

5-4 Millstone Station Emergency Plan Revision 56 March 2018

5.1.9 Station Duty Officer (SDO)

  • The Station Duty Officer or available SRO notifies the NRC, assists with communications, precautionary dismissal, and evacuation or assembly of station personnel.

5.1.10 Fire Brigade The Fire Brigade provides immediate response to a fire on-site.

5.1.11 First Aid Team The First Aid Team provides emergency medical services for on-site personnel mJunes.

5.2 Minimum Staffing Positions 5.2.1 Director of Station Emergency Operations (DSEO)

After relieving the CRDSEO, the EOF DSEO assumes overall command and control of the SERO and the licensee emergency response. The DSEO is responsible for classification, notification, release of information to off-site authorities, recommending protective actions to the State of Connecticut, and approval of personnel appointed to fill SERO vacancies during an emergency. The DSEO will ensure that additional SERO staff positions, as determined necessary to effectively respond to the specific emergency, will be staffed within 90 minutes of facility activation. The following DSEO responsibilities cannot be delegated:

  • Command and control of station emergency response, including coordination of response by off-site agencies
  • Event classification
  • Approval of off-site Protective Action Recommendations
  • Authorization of emergency exposures greater than 25 rem TEDE for lifesaving activities
  • Authorization of off-site notifications
  • Requests for federal assistance to support station response 5.2.2 Assistant Director, Technical Support (ADTS)

The ADTS reports to the DSEO. The ADTS is responsible for providing command and control of the SERO technical, operational, assessment and repair staff. The MCRO, MRCA, MOSC, MTSC, and MOS report to the ADTS.'

The ADTS primary responsibilities include:

Ensuring actions are taken to mitigate degradation of plant systems Recommending changes in classification to the DSEO Approving accident management strategies and ensuring accident management plan is implemented

  • Ordering station assembly, evacuation, or sheltering
  • Approving on-site personal protective action decisions (PPADs)
  • Approving emergency exposure upgrades to 25 Rem TEDE for on-site staff and technical, operational support and security personnel
  • Approving the issue of Potassium Iodide (KI) to emergency personnel assigned to the ADTS, at the recommendation of the MRCA

The MTSC reports to the ADTS. The MTSC analyzes operating data and provides technical support to the ADTS, MCRO, and the MOSC. The TSC Engineering staff and Accident Management Team report to the MTSC and provide accident assessment functions. The MTSC is assisted by a mechanical engineer, reactor engineer, and an electrical engineer.

5.2.4 Manager of Operational Support Center (MOSC)

The MOSC reports to the ADTS. The MOSC assembles, briefs, equips, deploys, and coordinates Emergency Assessment, Repair, and Search/Rescue Teams. The MOSC assumes control of the Operational Support Center. Personnel assigned to assist in performing these functions report to the MOSC. The MOSC is assisted by OSC assistants, maintenance specialists, and other staff.

5.2.5 Assistant Director, Emergency Operations Facility (ADEOF)

The ADEOF reports to the DSEO in the EOF. The ADEOF is responsible for providing command and control of the offsite radiological assessment and radiological support activities. The MRDA, MOC, MOR, and EC report to the ADEOF. The ADEOF is also responsible for:

  • Providing recommendations for classification changes based on offsite radiological conditions
  • Approving Potassium Iodide (KI) issue to emergency personnel assigned to theADEOF Developing, recommending and updating off-site PARs to the DSEO .

Off-site radiological dose assessment Providing logistics support (personnel) from external response agencies

  • Managing the collection and communication of event data for news releases
  • Assuming responsibilities of DSEO, in the event the DSEO becomes incapacitated or otherwise unable to perform the assigned duties
  • Approving emergency exposure upgrades up to 25 Rem TEDE for SERO personnel who perform actions off-site
  • Authorizing contaminated personnel to leave the station 5.2.6 Manager of Radiological Consequence Assessment (MRCA)

The MRCA reports to the ADTS. The MRCA coordinates health physics activities including on-site radiological assessment, personnel exposure control, recommendations on the issuance of KI to on-site SERO personnel, and radiation protection programs. Personnel assigned to assist in on-site radiological assessment functions include the Assistant Radiation Protection Supervisor (ARPS) and Radiological Communicators (RADCOM) .

5.2.7 Manager of Radiological Dose Assessment (MRDA)

The MRDA reports to the ADEOF. The MRDA coordinates off-site radiological monitoring, environmental sampling, and dose assessment, and provides recommendations for exposure upgrades and KI issuance to offsite SERO responders. The personnel assigned to assist in performing these functions are the Assistant Managers of Radiological Dose Assessment (AMRDAs), Radiological Assessment Engineers (RAEs), Field Team Data Coordinator (FTDC), and the Meteorological Assistant.

5.2.8 Manager of Communications (MOC)

The MOC reports to the ADEOF. The MOC provides information concerning the operation and status of the plant and radiological conditions to the NRC Headquarters Emergency Operations Center, Bethesda, MD and the NRC Region 1 Emergency Response Center as requested.

5.2.9 Radiological Monitoring Team (RMT #2-NAP and SAP)

HP Technicians serve as RMT # 2 and provide radiological surveys, HP coverage, and monitoring and decontamination activities associated with site evacuation.

The RMT #2 reports to the MRCA.

5.2.10 Radiological Monitoring Team (RMT #3-#4-#5)

  • RMTs # 3, #4, and #5 are each composed of a driver and monitor and provide offsite radiological surveys in the event of a release. The EOF RMTs will also collect environmental samples as directed by the MRDA. The offsite RMTs report to the MRDA.

5.2.11 EOF HP Technician The EOF HP Technician provides HP functions for the EOF and supervises operation of the EOF decontamination facility and count-room. The EOF HP Technician reports to the MRDA.

5.2.12 EOF Emergency Communicator (EC)

The EC performs notifications of corporate, SERO, federal, state and local officials. The EOF EC reports to the ADEOF.

5.2.13 OSC - Assistant Radiation Protection Supervisor (ARPS)

The ARPS reports to the MRCA. The ARPS provides radiological controls for the TSC/OSC and OSC Assembly Area. The ARPS also provides radiological support for emergency teams dispatched from the OSC AA.

5.2.14 Emergency Information Specialist (EIS)

  • The EIS reports to the DSEO. The EIS assists the DSEO in documenting or logging activities and provides other administrative assistance to the DSEO as needed.

5.2.15 Millstone Emergency Offsite Representative (MEOR)

The MEOR reports to the DSEO and acts as the company spokesperson at the SEOC and Joint Media Center, providing face-to-face .communications with state officials and representing the licensee at news conferences. The MEOR may also provide background information concerning licensee P ARs provided to the State DEEP and supports the Corporate Executive Spokesperson if one is present.

5.2.16 Nuclear News Manager (NNM)

The NNM reports to the MEOR and supervises Millstone public information activities at the Joint Media Center. The NNM may issue news releases if the Corporate External Affairs Manager is not available.

5.2.17 Manager of Resources (MOR)

The MOR reports to the ADEOF. The MOR fills SERO vacancies and provides 24 hour/day planning for manpower, transportation, food, quarters, equipment and supplies at the site. He/she serves as the coordinator for corporate support.

5-8 Millstone Station Emergency Plan Revision 56 March 2018

_ _ _J

5.2.18 Technical Support Center-Reactor Engineer (TSCRE)

  • The TSCRE reports to the MTSC and provides expertise in reactivity transients, reactivity management and shutdown margin calculations. The TSCRE assists the AMT with thermal hydraulic calculations as necessary.

5.2.19 Technical Information Coordinator (TIC)

The TIC reports to the DSEO and is responsible for collecting and entering information and key plant parameter data onto the Critical Parameters status board. The TIC obtains this set of key plant parameters from the Off-Site Facilities Information System (OFIS). This system provides information to the EOF, TSC and the SEOC.

5.2.20 Technical Support Center -Electrical Engineer (TSCEE)

TSCEE reports to the MTSC. The TSCEE is responsible for providing the MTSC with electrical engineering and general support.

5.2.21 Technical Support Center - Mechanical Engineer (TSCME)

TSCME reports to the MTSC. The TSCME is responsible for providing the MTSC with mechanical engineering and general support.

5.2.22 Mechanic, Electrician, l&C Technician, COEL The mechanic, electrician, and l&C Technician report to the Manager, OSC and are responsible for assessment, repair, and corrective actions.

5.2.23 Corporate Support Director (CSD)

The Corporate Support Director provides direction to the Innsbrook Corporate Support Center (ICSC) staff. The Corporate Support Director is also responsible for monitoring and participating in the corporate conference network, authorizing augmentation of additional corporate resources, and approving releases of information to the public.

5.3 Full Staffing Positions 5.3.1 Control Room Data Coordinator (CRDC)

The CRDC reports to the MCRO and is responsible for communicating plant data and control room activities to the TSC and EOF.

5.3.2 Technical Assistant (TA)

The TA reports to the MEOR and provides the MEOR with technical information as required .

5.3.3 Meteorological Assistant

  • 5.3.4 The Meteorological Assistant reports to the MRDA and provides meteorological data interpretation, calculations and long term meteorological information to support dose assessment activities.

Technical Support Center- Shift Manager (TSCSM)

The SRO assigned to the Technical Support Center assists with communications with the control room and provides technical expertise in accident assessment activities. The TSCSM monitors Emergency Operating Procedure (BOP) progress and assists the ADTS in monitoring plant conditions for possible classification changes.

5.3.5 Operational Support Center (OSC) Assistant The OSC Assistant reports to the Manager, OSC, and provides operational support by coordinating on-site activities and personnel.

5.3.6 CBETS Operator The CBETS Operator provides computer based exposure tracking information and assists the MRCA with the administrative activities for exposure upgrades and KI issuance. The CBETS Operator reports to the MRCA.

  • 5.3.7 5.3.8 Radiological Assessment Engineer (RAE) {two positions}

The RAE reports to the MRDA and assists the radiological assessment team in dose calculations.

Radiological Communicators {two positions} (RADCOM)

The RADCOMs report to the MRCA and provide communications for on-site radiological activities. One RADCOM is located in the TSC/OSC and the other is in theEOF.

5.3.9 Assistant Manager, Radiological Dose Assessment (AMRDA) {two positions}

The AMRDAs report to the MRDA and assist in performance of radiological monitoring, environmental sampling, and dose assessment.

5.3.10 Field Team Data Coordinator (FTDC)

The FTDC reports to the MRDA and provides communications and information from field teams to the EOF. The FTDC also briefs and deploys field monitoring and environmental sampling teams .

5.3.11 Manager of Security (MOS)

  • The Manager of Security reports to the ADTS and is responsible for maintaining accountability and site security.

5.3.12 Accident Management Team (AMT)

An Accident Management Team consisting of an AMT-Leader and an AMT Thermal-Hydraulic Engineer report to the MTSC and assist the Technical Support Center in developing accident response strategies. The AMT is also responsible for evaluating conditions and implementing Severe Accident Management Guidelines. During severe accident management implementation, the AMT reports to the ADTS.

5.3.13 Regulatory Liaison (RL)

The RL reports to the ADEOF and is responsible for accommodating the NRC Site Team dispatched to the station, arranging site access for the NRC Team, providing adequate dosimetry, and responding to questions and comments.

5.3.14 Media Center Liaison (MCL)

The MCL reports to the NNM and is responsible for assisting with media response .

  • 5.3.15 Technical Briefer (TB)

The TB reports to the Media Center Liaison and is responsible for providing technical, plant specific information to the media between official news briefings.

5.3.16 Radiological Briefer (RB)

The RB reports to the Media Center Liaison and is responsible for providing technical radiological information to the media between official news briefings.

5.3.17 Offsite Monitoring Facility (OMF) Staff The OMF is co-located with the EOF in Norwich. If activated, the EOF team reports to the MRDA through the FTDC. This is a call in position. If needed, the EOF team sets up and operates the OMF to monitor and decontaminate station personnel and monitor station personnel vehicles.

5.3.18 Station Emergency Preparedness Representative (SEPR)

The SEPR reports to the ADEOF and is responsible for assisting the EOF staff in activating and operating the facility .

5.3.19 Station Emergency Planning Liaison (SEPL)

  • 5.4 The SEPL reports to the l\1EOR and is responsible for providing support to SERO and state personnel in the SEOC.

Corporate Support 5.4.1 Corporate Support Coordinator (CSC)

  • Maintains an Events Log
  • Notifies Corporate Risk Management of the event
  • Serves as the central point-of-contact for requests for corporate logistical assist
  • Interfaces with the Manager of Resources 5.4.2 Corporate Plant Information Coordinator (CPIC)
  • Monitors the Operations Network and OFIS
  • Provides the Innsbrook Corporate Support Center (ICSC) with technical perspective
  • 5.4.3
  • Interfaces with the Technical Information Coordinator Corporate External Affairs Manager (CEAM)
  • Develops news releases if needed for an Unusual Event or higher incident classification for purposes of public information releases
  • Drafts news released based on input from the Corporate Conference Network data from Millstone, the EIS, and the NNM
  • Through the NNM, coordinates releases of GE news releases with State of Connecticut news releases
  • Distributes news releases to the media 5.4.4 Corporate Emergency Plan Specialist (CEPS)
  • Provides assistance with facility operations and interpretation of the Millstone Emergency Plan

5.4.5 Corporate Executive Spokesperson (CES)

  • Assumes responsibility as spokesperson from the MEOR. If it is determined that a CES is necessary, the CES will be assigned to the State Emergency Operations Center/Joint Media Center at the Hartford State Armory.

5.5 Other Organizations Providing Assistance 5 .5 .1 State I Local Assistance During an emergency, assistance from state or local agencies may be required. The State RERP defines responsibilities of the state and local agencies. Details of provided assistance are contained in Letters of Agreement (Appendix B) with the agencies and the State RERP.

[Response agencies will use the Incident Command Systems (ICS), the Connecticut State Response Framework, and the Connecticut Radiological Emergency Response Plan as appropriate in managing large scale incidents. For an event such as a security or Hostile Action, the Waterford Police Department and the State of Connecticut will assist as appropriate and coordinate the response with other local, state, and federal agencies.]

These letters are updated annually or as necessary to reaffirm agreed-upon assistance and to verify appropriate communications channels.

5.5.2 Private Agency Assistance Assistance of private agencies may also be required during an accident.

Details of the type of services expected are contained in letters of agreement. The letters are updated annually or as necessary to reaffirm agreed-upon assistance and to verify appropriate communications channels. Appendix B contains a listing of operational letters of agreement.

5.5.3 Federal Assistance Request for off-site federal assistance will be made through the State DEMHS. The federal agencies contacted can inform the State DEMHS of their response times.

The licensee does not anticipate need for additional federal support in responding to an accident.

The licensee maintains work centers for both FEMA and the NRC at the Station EOF. Work space is also maintained for NRC personnel in the TSC. Dedicated federal telephone communications and access to licensee communications equipment are provided in this area.

Table 5-1

  • Major Functional Area Unit Operations and assess. of operational Major Tasks Responsible for safe operation of the unit including the Normal Position/Title(n)

Shift Manager (SM)/CFH Station Emergency Response Organization Emergency Position/Title Manager of Control Room Emergency Location Affected Unit CR On-Shift 1(d, i)

Minimum StaffinQ *

  • 30-60 Minutes 60 Minutes Full Staffing (bl Training Summary (Refer to App K) 1, 4, 6, 9, 14 Rad Worker YES Resp Qua!

YES Operations(q) aspects, assessment of implementation of normal &

off-normal operational emergency operating Shift Technical Advisor, 1(a) YES Station Duty Officer Affected Unit CR 1,4 YES aspects procedures Security Supervision Shift Technical Advisor (a, i)

Shift Technical Advisor Affected Unit CR 1 1,4 YES YES (STA)

Unit Supervi~or (US) us Affected Unit CR i (i) 1; 4, 6, 9, 14 YES YES co Affected Unit CR 2(i) i YES YES Control Operator (CO)

Plant Equipment 2(i)

PEO Affected Unit CR 1 YES YES Operator (PEO) (Unit 2,3)

Unit 2 Operator (Unit 1 responder and Unit 2 PEO Unit 2 CR 1(i) i YES YES

.. Appendix R responder)

Emergency Direction and Assume command and control Manager, Nuclear Director of Station Affected Unit Control 1tm1 1, 4, 6, 9, 14 YES YES Control, Support of of Station Emergency Operations, Shift Emergency Operations(qJ Room(m)

Operational Accident Operations. Event Managers/CFH Assessment classifications, notifications and .-

PARs.

  • Communications Management liaison to the SEOC. Coordinates station emergency response actions with that of the State.

Provide information to the Chief Directors, Managers Directors, Managers, Nuclear Specialist Licensing, Millstone Emergency Offsite Representative Technical Assistant EOF SEOC/Joint Media Center SEOC/Joint Media Center 1

1\0/

1 1, 4, 9, 14 1, 2, 9 Technical Spokesperson Engineers/Process Leadership, Maintenance

(

Table 5-1

  • Major Functional Area Public Information Major Tasks Supervise public information activities. Disseminate Normal Positionffitle(nJ Various Station Emergency Response Organization Emergency Position/Title Nuclear News Manager Emergency Location SEOC/Joint Media Center On-Shift Minimum StaffinQ *
  • 30-60 Minutes 60 Minutes 1ln)\O)

Full Staffing (bl Training Summary (Refer to App K) 1, 4, 9 Rad Worker Resp Qual information received from EOF, armory, and Corporate staff to appropriate corporate and government officials.

Coordinate with ICSC.

Develop and distribute news releases if the Corporate External Affairs Manager is not available.

Approve news releases. Senior Executive Corporate Support Director ICSC 1 (h) .. , 1, 4, 9 Support coordination with CT Various Media Center Liaison SEOC/Joint Media Center 1 r 1, 4, 9 Public Information Staff.

Support public information effort Various Technical Briefer SEOC/Joint Media Center 1 1, 4, 9 with technical information.

Support public information effort Various Radiological Briefer SEOC/Joint Media Center 1 1, 4, 9 with radioloqical information.

Radiological Calculations Assume command and control Managers, Supervisors Assistant Director EOF 1 1, 4, 7, 9, 14 and Event of. internal/external Emergency Operations Communications communications, radiological Facility ' ,

assessment, and management of the event. Ensures off-site radiological assessments are ' ..

provided to the State DEEP. *-.:

Recommends PARs to the ...

DSEO.

Decontamination and Provide HP controls for the HP Tech EOF HP Tech EOF 1 1 YES YES Radiation Controls EOF, supervise Decon Facility Notification and Notify licensee, corporate, Work Control SRO Emergency Communicator Unit CR 1lC)

  • 1,3,4,9 YES YES Communications federal, state and local officials.

STNSecurity SDO Unit CR 1 1, 4, 9 YES YES Supervision/Work Control SRO Work Control SRO Emergency Communicator EOF 1 1,3,4,9 YES YES Communicate with CR. SRO TSC-Shift Manager/CFH TSC/OSC 1(g) 1, 4 YES YES Activate ERDS Work Control SRO EmerQency Communicator Unit CR 1,3,4,9 YES YES Notification and Coordinate technical data Operator Training Staff Manager of EOF 1t9J 1 1, 2, 4, 9 Communications. communication between EOF, Communications (Technical) CR, TSC/OSC, and government aQencies.

Technical Information Obtain plant data for Unit Personnel, Operator Technical Information EOF 1l9) 1 1, 2, 4, 6 or 7, Communications Emergency Response Facilities Training Staff Coordinator ' 9 and Technical Assistant at SEOC as required .

Table 5-1

  • Station Emergency Response Organization On- Minim um Staffinq *
  • Training Major Functional Area Major Tasks Normal Position!Title(nl Emergency Position/Title Emergency Location Full Rad Resp Shift 30-60 60 Staffing (bl Summary Worker Qual Minutes Minutes (Refer to App K)

Administrative Support Provide administrative support Various Emergency Information EOF 1 .. 1, 4, 9 to the DSEO. Specialist Maintain log for the DSEO.

Facilitate information exchange with other emerqency facilities.

Technical Data Operator Training Staff Control Room Data Affected Unit CR 2l9) 1, 2, 4, 9 YES Ensure needs for plant data and Communications information are met. Coordinator On-Site Radiological Direct On-site RMTs, sampling Radiological Protection Manager of Radiological TSC/OSC 1 1 1, 4, 9 YES Accident Assessment program and radiation and Waste Services Consequence Assessment protection program. Perform HP Ops Support dose assessment calculations. HP Ops

.. HP Supervisors Radiological Surveys HP coverage and station HP Technician RMT#1 Affected Unit CR 1(d) 1 1, 4 YES YES surveys for repair, corrective actions, Search and Rescue, *.

and fire-fighting. Personnel monitoring, and dosimetry issue.

(d,I)

Radiological Protection Radio Chemistry Assessments I Chemistry Technicians Chemistry Technicians CR, OSCAA 2 1, 15 YES YES Initial Dose Assessment

  • Off-site Radiological Dose Assessment Access control Coordinate off-site sampling program, dose assessment and core damage assessment Dose Calculations

.. HP Technician Engineers/Manager-Chemistry Supervisors Engineers/Analysts/

Specialists RMT #2 (A,B,C,D)

Manager of Radiological Dose Assessment Radiological Assessment Enqineer NAP/SAP EOF EOF 4

1 2

1, 4 1, 4, 5, 7, 9, 11, 12, 13, 14 1, 4, 5, 9, 11, 12, 13 YES YES Dose Assessment, Radiological Chemistry Supervisors, Assistant Manager of EOF 2 .. 1, 4, 5, 7, 9, Calculations Chemistry Training Radiological Dose 11, 12, 13, 14 i

Assessment Engineers/Analysts/

' Specialists Radiological Control Within Provide radiological col)trols HP Assistant Radiological OSCAA 1 ..

1, 4 YES the OSC AA within the TSC/OSC, OSC AA Protection Supervisor and provides radiological ...

support for emergency teams dispatched from the OSG AA Radiological Radio Deploy RMTs, collect d1:1ta. Site Services, HP Services Field T earn Data EOF 1 1, 4, 5, 9 Communications ' Coordinator Radioloqical Surveys Off-site Surveys HPNarious RMT #3-4-5 and Drivers EOF 2 4 1, 4 YES YES Meteorological Services Provide meteorological data Environmental Specialists Meteorological Assistant EOF 1 1, 4, 10 interpretation, calculations, long term meteoroloqical information Environmental Services Plume and Ingestion Pathway Environmental/HP RMT #3-4-5 and Drivers EOF 2UJ YES and/or Health Physics Sampling I Personnel and/or HP REMP Tech

Table 5-1

  • Major Functional Area Contingency Offsite Contamination Monitoring Major Tasks Set up and operate Offsite Monitoring Facility Normal Position!Title(nl Radioactive Material Technician OMF Staff Station Emergency Response Organization Emergency Position!Title EOF Emergency Location On-Shift Minimum Staffinq *
  • 30-60 Minutes 60 Minutes Full Staffing (bl 6\PI Training Summary (Refer to App K) 4 Rad Worker YES Resp Qual for Station Staff ...

Accident Assessment Assume command and control Manager-Operations, Assistant Director, TSC/OSC 1\9) 1 1, 4, 6, 8, 9 YES Management and of the station operating, Supervisor Nuclear Shift Technical Support Consequence Mitigation technical assessment and Operations, Supervisor-repair staff. Recommends Operator Training chanQes to classifications Unit System Engineering Responsible for analysis of Manager-Engineering/ Manager of Technical TSC/OSC 1 1 I 1,4, 7,9 YES operations data, development of Supervisors, Engineers Support Center procedures, recommend repair, Manager-Site Services and corrective actions ..

Assist Manager of Technical Mechanical Engineer TSC-ME TSC/OSC 1 1 1, 2, 4 YES Support Electrical Engineer TSC-EE TSC/OSC 1 1 1, 2, 4 YES Reactor Enqineer TSC-RE TSC/OSC 1 1, 2, 4 YES Nuclear Instrument Control Operations OSCAA 1 1 YES Technician Electrical (GOEL) Specialist Plant System Engineer Assist Manager of Technical Safety Analysis, Nuclear Accident Management TSC/OSC 1 1, 2, 4, 8 YES Repair and Corrective Support. Provide accident Fuel Engineering Team- Leader Action analysis

  • Repair and Corrective Actions Evaluation, repair, and corrective actions Safety Analysis, Nuclear Fuel EnqineerinQ Manager-Maintenance Supervisor Mechanic AMT-Thermal-Hydraulic EnQineer (T-H)

Manager of Operational Support Center Mechanic TSC/OSC TSC/OSC, OSC AA OSCAA 1 1

1 1

1 1, 2, 4 1, 4, 9 1

YES YES YES YES Electrician Electrician OSCAA 1 1 1 YES YES l&C Technician l&C Technician OSCAA 1 1 1 YES YES Operational Support Coordinate on-site activities and Supervisor-Maintenance OSC Assistant TSC/OSC, OSC AA 2 1, 4, 9 YES personnel

... Supervisor-Maintenance OSC Assistant TSC/OSC, OSC AA 2 1, 4, 9 YES Resource Acquisition & . Coordinates requests for Various Manager of Resources EOF 1 1, 4, 9 Personnel Dispatching assistance, organizes station personnel for relief shift work, account SERO personnel.

Coordinate acquisition of personnel and equipment from corporate or outside sources.

Information Resources Maintain computer availability IT Personnel None Millstone Station (i)

l-Table 5-1 Station Emergency Response Organization Minimum Staffinq *

  • Training Major Functional Area Major Tasks Normal Positionffitle<n> Emergency Positionffitle Emergency Location On-Shift Full Rad Resp 30-60 60 Staffing Summary Qual (b) Worker

.. Minutes Minutes (Refer to App K)

Firefighting Firefighting and communicate Fire Brigade Fire Brigade As Required Per Local 1 YES YES and strategize with Control TRM<a> Comm '

Room and Support FPER<a>

Search and Rescue _Search and rescue operations Security Personnel / Security Personnel / Station As Required Per Sec. i 1 YES YES Operations Station Personnel, as Personnel Plan required External Response Provide logistics support for Licensing, Engineering Regulatory Liaison EOF 1 1, 4 Logistics external response personnel.

Liaison with NRG Site Response team. .

Backup SERO Communications with Security Personnel Security Person GAS/SAS 1 1 YES YES Notifications ADTS/DSEO. Backup SERO Notification Svstem Communications HP Communications *-. HP Staff RAD Communicator

  • EOF, TSC/OSC 2 1, 4 YES Exposure Control Exposure Monitorinq HP Staff CBETS Operator OSCAA 1 1, 4 YES First Aid Emergency Medical Services First Aid Team First Aid T earn As required 2 (a) Local 1 YES Comm

... Suooort Site Access Control and Establish EOF security. Directs Security Personnel Manager of Security TSC/OSC 1 1, 4, 7, 9 YES Personnel Accountability Security Personnel in support of ,;:

emergency operations (firefighting communications, -*.

personnel accountability) assist ,;*.

in personnel accountability **'i.

Establish station security. Security Personnel Security Personnel Per ¥*.*

1 YES YES Support emergency operations Security . -

and perform personnel _Plan accountability Supervise on-site security Security Shift Operations Security Shift Operations 1(a) 1, 7 YES I

operations Supervisor Supervisor Support Provide support to SEOC staff EP Narious State Emergency Planning SEOC/Joint Media Center 1 1,4,9 Liaison Provide support to EOF staff EP Staff Station Emergency EOF 1 1,4,9 Prepared11ess

.. Representative Totals Unit 1 10(k, I) 11 3o(e) 38 Unit 2/Unit 3 15(k, I) 11 3o(e) 38

Table 5-1 Notes:

a May be provided by shift personnel not assigned an Emergency Position (exception is First Aid Team) .

b Full staffing are beyond minimum required for facility activation which constitute a fully augmented SERO. Personnel respond as soon as possible upon notification with a goal of filling these positions within 4 hour~.

c Station position (Counted as affected unit resource).

d One for Unit I/Unit 2; one for Unit 3; (for Chemistry and Health Physics, two each per site) e Assigned, affected unit resources, additional SERO staff will respond from non-affected units.

f Overall station resource (accounts for additional personnel from the unaffected units).

g One needed for Unit 2 and one needed for Unit 3 (only 1 required for minimum staffing for activation).

h Carries out independent responses at time of incident notification.

Only one senior reactor operator, reactor operator and non-licensed operator are required on shift under non-operating conditions (shutdown and refueling). For a permanently defueled condition, only one certified fuel handler and one equipment operator are required on shift.

j Call-in specialized resource- (Non-SERO personnel).

k Total does not include Security staff or Fire Brigade personnel on-shift.

I On-Shift total reflects Shift Manager/ Affected Unit Control Room DSEO as one position.

m For a Unit 1 event the Unit 2 SM/CHI becomes the CRDSEO; after transferring responsibilities to the ADTS and EOF DSEO, the Unit 2 CRDSEO becomes the MCRO.-

n Higher level organization personnel may be used to fill these roles as necessary.

0 A 90-minute goal has been established for the Millstone Emergency Offsite Representative and Nuclear News Manager who report to the CT SEOC.

p. Position will be staffed as needed by called in personnel and only as required. Staff may be augmented by any available HP Technicians, ARPSs, and/or CBETS operators.
q. The Shift Manager (SM) becomes the Control Room Director of Station Emergency Operations (CR DSEO) until relieved by the EOF DSEO. The SM then becomes the Manager of Control Room Operations.
  • A 30 to 60-minute goal has been established for the identified individuals. It is expected that some of these individuals will report within about 30 minutes, with the remainder arriving at various times during the next 30-minute interval.
  • Indicated Staff response times are from the time of notification to report to emergency assignments.

Figure 5-1 Organization of Station Emergency Management Personnel (Page 1 of3)

Senior SERO Management Structure I

Corporate Support ADTS ADEOF MEOR Director (Onsite Response) (Offsite Response) . (Public Information)

(Corporate Support)

Q Public fuformation SERO Structure

' MEOR

  • Tech Assistant State EP Liaison II Indicates positions necessary for facility activation.

D Indicates fully augmented organization positions .

Figure 5-1 Organization of Station Emergency Management Personnel (Page 2 of3)

Onsite SERO Structure ADTS MTSC MOSC MTSC Reactor Eng Electrical Eng Mechanical Eng Electrical Eng Mechanical Eng Indicates on shift positions.

II Indicates positions necessary for facility activation.

D Indicates fully augmented organization positions.

5-21 Millstone Station Emergency Plan Revision 56 March 2018

Figure 5-1 Organization and Location of Station Emergency Management Personnel (Page 3 of3)

Offsite SERO Structure ADEOF I

MRDA MOR Station EP Rep Reg Liaison Rad Corn Met Assistant II Indicates positions necessary for facility activation.

D Indicates fully augmented organization positions.

5-22 Millstone Station Emergency Plan Revision 56 March 2018

6. Emergency Measures
  • Emergency measures begin with the identification and classification of an emergency and the activation of the appropriate emergency organizations. Emergency measures include assessment actions, corrective actions, and recommendation of protective actions. The Emergency Action Levels (EALs) have predetermined values or conditions which, when met or exceeded, require declaration of an emergency classification, notification of the licensee. emergency response organization, state and local officials, and corrective and/or protective actions. A general outline is presented as follows:

6.1 Notification and Activation of Emergency Organizations The authority and responsibility for initially classifying and declaring emergencies, initiating notification to emergency organization personnel, state and local officials and the NRC and initiating immediate actions necessary to limit the consequences of the emergency reside with the Shift Manager (SM), who is on site 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.

The SM initially assumes command and control of the SERO as the Control Room Director of Station Emergency Operations (CRDSEO). The SM will function as CRDSEO until relieved by the EOF DSEO, a shift relief occurs, or the event is terminated. After relief by the EOF DSEO, the SM assumes responsibility as Manager of Control Room Operations (MCRO).

The CRDSEO /DSEO is responsible for ensuring that timely and appr9priate notifications

  • are made .

SERO responsibilities may be transferred during a normal shift rotation when a qualified relief reports on site and is fully briefed on current and past conditions.

For emergencies that are not unit-specific, the Unit 3 Shift Manager assumes the position of DSEO until relieved, or the event is terminated.

The SERO is activated by a combination of public address (PA) system announcement, Station emergency alarm actuation and electronic message. The PA announcement can include the incident location, emergency classification and personnel information.

Initially, the emergency organization consists of normal on-shift personnel. Notification of the emergency organization and state and local officials is by the Emergency Notification and Response System (ENRS) which is initiated by Control Room personnel.

If a failure of either system should occur, notifications will be made using commercial telephone lines and/or satellite phones. The Connecticut State Police will assist with backup notifications to state and local officials, as necessary.

Following the declaration of a "State of Emergency" by the Governor, DEMHS may

  • direct the DSEO to discontinue use of the ENRS for further state and local notifications and directly communicate with the SEOC for classification changes or event updates. The State will then assume responsibilities for notification of the local town EOCs. The SEOC will coordinate activation of the Public Alerting System sirens with the local governments, as needed. The ENRS consists of computer based systems. When activated, messages are sent to phones and/or electronic devices. The ENRS is used for notification of emergency events and decreases the time necessary to notify off-site officials. The ENRS message satisfies the requirement to notify state and local officials of the emergency classification level within 15 minutes after declaration of an emergency. State and local officials acknowledge the notification. The ENRS records the time the call was completed and provides more detailed incident information. A goal of 15 minutes has been established for completing the initial SERO notification sequence.

Electronic messages include the following information:

  • Station and unit identification
  • Event classification (including State Posture Code) fucident report forms are sent to State and local officials by electronic means with the following additional information:
  • Date and time of event classification
  • Name and Title of communicator
  • Verbal summary of incident details (major and minor EAL headings)

Current release information Meteorological conditions (if available)

Classification change, update, termination Message updates which are provided as plant status and conditions change include forecast meteorological conditions, plant status, any offsite services requested, and whether or not access to the site has been restricted.

Details concerning release type, quantities and actual or projected dose rates will be developed, as appropriate, and provided to responsible officials, when requested.

The ENRS provides initial event notification to the emergency organizations. When emergency facilities are activated, various communications systems are used. These systems allow transmission of detailed technical information of the event in progress as well as direct voice communications between facilities and decision makers. Detailed radiological information will be relayed to the DEEP at the SEOC for analysis and decision making.

A representative from the State DEEP responds to the EOF and provides a liaison with the EOF and SEOC staff.

The Millstone Emergency Offsite Representative, Technical Assistant, and Nuclear News

  • Manager respond to the State EOC. They are supported by the Media Center Liaison, Technical Briefer, Radiological Briefer, and State EP Liaison.

Work space and communications for federal agencies and the Town of Waterford are located in the EOF. The TSC provides a work area and limited communications for the NRC.

The SEOC in Hartford uses various communication systems to provide information to the DEMHS Region Coordinators and the local community EOCs. The systems are used to transmit technical, radiological, administrative and resource data between the local community EOCs and the SEOC. Radio, telephone, and FAX devices are used to provide continuous contact with the affected areas. The SEOC coordinates the Public Alerting System siren activation to immediately precede Emergency Alert System (EAS) broadcast messages.

The primary notification (electronic and dedicated telephone lines) contacts and the continuing lines of communication between on-site emergency response facilities and off-site emergency response centers are indicated in Figures 7-1 a through 7-1 c.

6.2 Assessment Actions 6.2.1 Initial Assessment Event classification is based on EALs. The EAL tables provide an incident classification based on instrument readings available in the control room or other observations. The NRC incident classification and corresponding state posture codes are transmitted to state and local officials via the ENRS.

On-Shift dose calculations are conducted, when appropriate, and used to validate the incident classification and any PAR if applicable.

The Shift Technical Advisor (STA) provides independent assessment of emergency actions. When activated, the TSC assumes a more expanded role and responsibility beyond that of the STA.

Additional technical services and support are obtained as necessary from a combination of station personnel, corporate personnel, and off-site assistance companies/agencies. The State DEEP does an independent assessment of plant conditions and off-site dose. assessment.

6.2.2 Protective Action Recommendations (PARs)

The State RERP includes procedures for use by state and local community officials for public protective actions in the plume exposure pathway. Public PARs requiring evacuation are to be initiated only for GENERAL EMERGENCY events .

PARs beyond those associated with the event classification are developed using

  • dose assessment or plant conditions in accordance . with "NUREG-0654, Supplement 3" guidance for severe reactor accidents. The licensee will provide a PAR to state and local authorities.

If PARs are warranted from the Control Room before activation of the station response organization, the appropriate PARs will be transmitted directly to the State DEEP. Following activation of the station response organizations, PARs are developed and issued directly to the SEOC. The provided PAR will be revised if changing conditions warrant.

When authorized, protective actions are implemented by state and local officials using the Public Alerting System sirens in conjunction with the EAS. Route alerting provides backup alert and notification capability. The Governor of Connecticut is responsible for public protective actibn decisions after a state of emergency is declared. Before a state of emergency declaration, local chief executives are authorized to take the public protective actions associat~d with the GENERAL EMERGENCY posture codes.

When emergency response facilities are activated, the State DEEP will collect and process information to independently verify and recommend changes, if necessary, to the licensee provided PARs.

6.2.3 Dose Assessment

  • Radiological assessments by the SERO include determination of radiation exposure rates by both analytic and direct measurement methods. Direct measurements are performed by RMTs deployed to field monitoring locations.

The analytic methods use computerized dose calculation models. Projected dose estimates are calculated for different downwind directions and distances. The results may require reclassification of the emergency. Further assessments are performed as required and updates are provided to off-site authorities. On-site radiation protection activities are coordinated by the MRCA. Off-site RMT activities are coordinated by the FTDC under the direction of the MRDA. Field data and projected dose information are transmitted to the State DEEP, as necessary.

The emergency plan procedures contain methods for relating the various measured parameters to dose rates for the accident conditions.

Dose assessment is performed by licensee personnel assigned to the control room or EOF who perform the calculations. Information from dispatched field monitoring teams and plant conditions are then ' used to verify incident classification.

a. Use of Station Monitors
  • The station has an extensive system for monitoring radioactive materials released to the environment. As a general requirement, the various process monitors are capable of initiating appropriate alarms and/or actuating control equipment to provide containment of radioactive materials if pre-established limits are reached.

High range containment radiation monitors have been installed in the Unit 2 and Unit 3 containments to be used to determine containment atmosphere curie inventory. Procedures have been established for converting these monitor readings into potential dose assessment data.

For Unit 2 and Unit 3, high-range radiation monitors have been installed at the potential effluent points to determine effluent release rates if existing normal range stack monitors should go off-scale or become inoperative during an emergency. These high-range monitors cover the entire postulated range of releases and exceed the v~ues specified for a GENERAL EMERGENCY. These systems allow for monitoring releases during emergency conditions. Procedures have been established for converting these monitor readings into release rates. RMT surveys are taken to verify release rates.

Unit 1 gaseous effluent releases are continuously monitored for radioactive

  • gases by a Spent Fuel Pool Island (SFPI) radiation monitoring system.

Gaseous effluent is sampled for radioactive particulates by a continuous sampling system which collects samples for periodic analysis.

The site has a permanent meteorological installation that records wind speed, direction, and temperature differences continuously in the Unit 2 and Unit 3 Control Rooms and at 15-minute intervals via a computer system.

b. Use of Emergency Action Levels (EALs)

Unit 2 and Unit 3 EALs contain effluent monitor radiation levels which correspond to predetermined dose assessments and appropriate emergency classification levels.

Unit 1 EALs contain effluent monitor release limits established in the Radiation Effluent Monitoring Manual .

C* Dose Estimates for Radioactive Releases

  • Upon determination of an emergency or potential emergency condition that is anticipated to have off-site consequences, off-site doses are estimated. The critical exposure pathways for short-term emergency actions are the external dose due to noble gases and the internal thyroid dose due to inhalation of radioactive iodine. In these cases, estimated release rates are combined with meteorological dispersion estimates in order to predict off-site doses. Station emergency plan procedures include a method to calculate the distances at which the Environmental Protection Agency protective action guide (PAG) limits may occur.

When the station EOF is activated and radiological dose assessment personnel have arrived, estimates of off-site doses based on more sophisticated techniques and by analysis of actual RMT data can be provided.

6.2.4 Release Rate and Dose Estimate Methodology

a. Noble Gas Release Rate Estimates Gaseous effluent readings for Unit 2 and Unit 3 are obtained and converted to release rates by multiplying the readings by an appropriate factor. If the monitors are off-scale, the high-range radiation monitors are used to determine release rates. The high-range radiation monitor readings are converted to a release rate using a predetermined factor. Grab sample results, if available, may be more accurate than gross monitor readings.

Release rates based on actual samples, if available, will be used in lieu of monitor based calculations.

If no release estimates based on fixed monitors are available, the release rate will be estimated using field monitoring results.

Unit 1 noble gas release estimates for accidental releases out the SFPI vent will use an area monitor and conversion factors to determine the quantity of Kr-85 being released.

b. Radioactive Iodine Release Rate Estimates If radioactive iodine grab sample results are available, they may be used to calculate the total iodine release rate. If grab samples are not available, the total noble *gas release rate is multiplied by a predetermined iodine-to-noble gas ratio (depending on the plant conditions) to obtain the iodine release rate .

C* Core Damage Estimates

  • Core damage estimations serve several roles within the Millstone Emergency Preparedness Program. For planning purposes, core damage considerations are used as the bases for several of the Emergency Action Level (EAL) initiating conditions and as the threshold for the declaration of a General Emergency (the definition of a General Emergency specifies conditions which involve 'substantial' core degradation or melting as one of the bases for classification). From an implementation perspective, core damage estimations provide a means of realistically differentiating between the four core states (no damage, clad damage, overheat, and melt) to:
  • Evaluate the status of the fuel barriers and how their status relates to the risks and possible consequences of the accident.
  • Determine the potential quality (type) and/or quantity(%) of source term available for release in support of projected offsite doses and protective action recommendations.
  • Provide information which quantifies the severity of an accident in terms that can be readily understood and visualized.
  • Support the determination of radiological protection actions that
  • should be considered for long term recovery activities .

The assessment methodologies used by Millstone Station are intended to provide a rapid best estimate of core damage which, when evaluated together, help to develop an overall picture of the extent of core damage.

The methods used to estimate the amount or type of core damage occurring under accident conditions include the following:

  • Core Uncovery Time: An indirect method used to indicate the type of core damage (clad failure or fuel melt). Applicable for all types of accidents. Provides a relatively accurate estimate of the core state early in the event. Valid any time following an accident.
  • Core Temperatures: An indirect method used to indicate the type of core damage. Applicable for all types of accidents. Does not provide numerical estimations but is useful as a yes/no indicator or as confirmation of other methods. Valid any time following an accident.
  • method used to determine the amount of core damage. Applicable to LOCA type accidents. Based upon an end-of-life source term and static nuclide ratio assumptions yielding a limited accuracy.

Valid any time following an accident.

Containment Hydrogen Concentration: An indirect method used to establish the type of core damage. Applicable to LOCA type accidents where all the hydrogen generated by the metal-water reaction is released into containment. Valid any time following an accident.

  • Sample Analysis - Isotopic Ratio Comparison: A direct method used to establish the type of core damage. Compares expected isotopic ratios with a sample to determine a general core state.

Applicable under all types of accidents. Valid any time following an accident.

  • Sample Analysis - Presence of Abnormal Isotopes: A direct method used to indicate a degree of fuel melt by the presence of unusually high concentrations of the less volatile fission products.

Applicable under all types of accidents. Valid any time following an accident.

  • Sample Analysis - Concentration Evaluation: A direct method which yields the most accurate numerical estimations. Applicable for all types of accidents. Requires the sampled system(s) be in a steady state which usually prevents its use until the plant is in a stable condition.
d. Meteorological Data Input to the meteorological section of the procedures includes effective release height, temperature differential, wind speed, and wind direction based on actual or projected readings.

Meteorological data, acquisition and flow are described in Section 7.13.

e. Total Effective Dose Equivalent (TEDE)

The calculated TEDE contributions will include plume external exposure, ground external exposure and inhalation exposure. TEDE doses are calculated for various downwind distances using computerized methods .

f. Committed Dose Equivalent (CDE)-Thyroid
  • g.

The radioactive iodine release rate and meteorological data are used in computerized methods to obtain the projected maximum off-site CDE thyroid dose at various downwind distances.

Verification When appropriate, dose rates are verified by on-site and off-site RMTs which have been deployed with portable emergency radiological instrumentation and communication equipment.

h. RMT Mobilization and Monitoring
1) Notification/Coordination Methods - When notified by the station public address system, the RMT members report to the EOF, Control Room, North Access Point (NAP), South Access Point (SAP), or other areas as assigned. The teams are then dispatched by the appropriate SERO managers.
2) Composition - Each of the off-site RMTs consists of two persons, at least one is a health physics technician. The on-site RMTs are health physics technicians.
3) Transportation - Three dedicated company vehicles are used for transporting off-site RMTs.
4) Monitoring and Equipment - A general list of radiological monitoring kit equipment is included in Appendix E. Complete inventories are provided in station procedures. The kits are provided with appropriate radiological monitoring equipment to measure radioiodine concentrations in air as low as 10-7 µCi/cc.
5) Environmental Dosimeters of Legal Record (DLRs) and air particulate samples, air sample cartridges, goat milk, cow milk, soil, vegetation, and water are collected by Environmental Services (ES), Health Physics personnel, or HP REMP Tech.
6) Deployment Time- The off-site RMTs can be deployed in approximately one hour. The on-site RMTs can be deployed immediately after equipment checks.
7) RMT Communication- The RMTs report information via radio communications or telephone.
i. Off-site Monitoring by DEEP The State DEEP dispatches off-site monitoring teams of state personnel.
j. Plume Monitoring Over Water
  • Millstone Environmental Lab vessels may be used to provide transportation for plume monitoring over water. RMT personnel will be assigned to perform over water monitoring as necessary.

6.2.5

  • Secondary Dose Assessment Long-term off-site radiological dose assessment (secondary assessment) is
  • provided by the State DEEP. The State DEEP is assisted, as necessary, by Millstone and other agencies. After the assessment has been completed, the State DEEP recommends protective actions to the Governor for approval.

6.3 Corrective Actions Corrective actions are implemented by the use of detailed station procedures. These procedures prioritize actions to prevent or mitigate the consequences of an accident.

The instrumentation, control systems monitors, and radiation monitoring systems provide indications of the safe and orderly operation of the unit. These systems provide the operator with the information and controls needed to start up, operate at power, and shut down the plant. They further provide the means to cope with an abnormal operating condition should it occur. Control of plant systems and information displays are centralized in the control room. This instrumentation provides the basis for initiation of corrective actions .

The following additional corrective actions are implemented during emergency situations as necessary.

6.3. l Fire Fighting Procedures for responding to fire emergency situations are in place. Firefighting strategies for plant areas are available for use by responding personnel. The Shift Fire Brigade is in charge of extinguishing the fire.

Applicable health physics, security, and safeguards procedures apply. If outside assistance is needed, the Waterford Fire Service is called.

6.3.2 Damage Control, Repair and Decontamination Station personnel normally provide decontamination, repair and damage control services. For ALERT, SITE AREA EMERGENCY and GENERAL EMERGENCY operations, the support of specialized outside contractors is obtained, as required. Decontamination of personnel and equipment is conducted in accordance with approved procedures .

6.4 Protective Actions

  • Protective actions are taken when an incident has occurred, or may occur, that could result in concentrations of airborne radioactivity or radiation levels that exceed normal limits for a specific area or areas and cannot be readily controlled, or personnel safety from other causes is threatened. Emergency procedures provide guidance for protective actions, such as evacuation, assembly or sheltering.

6.4.1 On-site Protective Actions Persons in the owner-controlled area of the site, but outside the protected area, are considered members of the general public. Persons within the protected area are either station personnel, contractor personnel, or visitors. If the protected area has been evacuated, Security will inspect locations outside the protected area to ensure all personnel have evacuated.

The radiological protective actions specified in this section and in Emergency Plan Procedures are augmented by the normal health physics procedures and are used during an emergency unless different actions are identified and authorized by the ADTS. The MRCA establishes radiological control areas (RCAs) in response to the incident. Access to the RCA is controlled by the emergency team briefing process unless immediate access is authorized by the ADTS to facilitate emergency repairs.

a. Notification The actuation of radiation monitoring alarms, the station emergency alarm, fire alarms, and public address announcements alerts personnel to hazardous conditions and response actions. Station procedures provide for a range of protective actions to protect onsite personnel during hostile action.
b. Security and Site Access Control If station access has been restricted, traffic is diverted through a security checkpoint in the Simulator Training Building parking lot. Site access roads will be manned and barricaded as necessary. Station access controls will be supported by the Waterford Police Department and the Connecticut State Police, as necessary. Personnel accessing the protected area must be authorized. Station security procedures provide detailed guidance for responding to an emergency.

C. Precautionary Dismissal of Non-Essential Personnel A precautionary dismissal of non-SERO personnel occurs at the Alert level declaration and can be initiated from the Control Room or TSC. The CR DSEO or ADTS can elect NOT to conduct the precautionary dismissal if the nature of the event warrants such judgment.

6-11 Millstone Station Emergency Plan Revision 56 March 2018

A precautionary dismissal directs all non-essential Millstone employees,

  • d.

contractors, and visitors to leave the site.

Evacuation A site evacuation is initiated at the SITE AREA EMERGENCY or GENERAL EMERGENCY classification levels. Site evacuation may be called for at the ALERT level classification depending on the environmental conditions at the time of the event. All non-essential personnel are instructed to leave the Owner Controlled Area. Personnel can be evacuated in about 30 minutes. Evacuation may be suspended or deferred during certain situations (e.g., Security-related, toxic gas), until the threat is resolved. Evacuation will be implemented as quickly as possible thereafter, given the specific situation.

Evacuation can involve the movement of large numbers of personnel out of the Protected Area through the turnstiles at the NAP or SAP. An evacuation alarm actuator is located in the Unit 2 and Unit 3 control rooms. A public alert system is in place in the protected area to communicate evacuation messages in the event of a station emergency.

Evacuation may warrant station egress control by Security. Following discussion with the Connecticut State Police and the Waterford Police Departments, Security will provide specific instructions to exiting

  • personnel as requested by off-site authorities. As part of evacuation, station personnel may be directed to a specific location for monitoring and decontamination.

Other situations which involve the evacuation of personnel from occupied localized areas onsite must be controlled on a case-by-case basis.

e. Local Area Evacuation Local area evacuation is an evacuation of a building, area, unit, or multi-units for the immediate protection of station personnel from a hazard with limited exposure potential. It is a standard response immediately taken by control room personnel upon acknowledging the hazard.
f. Sheltering Sheltering is a short-term action taken in specific situations where there is insufficient time available to conduct an evacuation due to the hazard being short lived or threatening the safety of the evacuating population. If a release or hazard is projected to occur within 30-60 minutes, sheltering in place with subsequent staggered movement of personnel may be considered.
g. Assembly
  • Assembly occurs upon declaration of an ALERT or higher emergency classification level. Minimum staffing and full staffing SERO positions report to their emergency response facilities (control room, EOF, TSC/OSC, OSC AA). SERO personnel assigned to the SEOC report to Hartford. Non-essential personnel are not involved in assembly activities.

The Assembly Areas are used to retain SERO personnel who may be needed in the near term to support the event.

h. Accountability Accountability is conducted at a SITE AREA or GENERAL EMERGENCY and may be conducted at the Alert level following SERO activation and the completion of the precautionary dismissal.

Accountability is the process of verifying the location of personnel who are inside the Protected Area. That is, any unaccounted for person that has keyed into the Protected Area (NAP/SAP) and is not keyed into a vital area, the TSC/OSC, or the OSC Assembly Area (cafeteria) will be identified as missing. Accountability is required to be completed within 45 minutes of its initiation (the names of any missing persons identified to the DSEO or ADTS and announced over the PA).

If precautionary dismissal or evacuation could endanger plant personnel, these actions may be deferred until the condition has been resolved. When conditions warrant, dismissal, evacuation and accountability will be performed, as appropriate.

i. Personnel Monitoring All personnel within the Protected Area are monitored for radioactive contamination before leaving the Owner-Controlled Area. Portal monitors and RMTs will be used for monitoring personnel. An off-site monitoring location will be established if radiological conditions on site prohibit adequate monitoring.

Each ERF has radiation detection equipment.

The. MRCA will establish decontamination areas as necessary.

Decontamination facilities are available at various areas within the station.

The EOF may be used for monitoring and decontamination if conditions prohibit on- site monitoring. Transportation to an off-site facility will be provided, as necessary. Monitoring and decontamination procedures are detailed in the Radiation Protection Manual (RPM) .

Documentation of personnel contamination surveys will be maintained.

  • Any person suspected or known to have ingested radioactive material will receive bioassay examinations as specified by the RPM.

6.4.2 Use of On-site.Protective Equipment and Supplies Protective equipment and supplies are used to minimize external and internal radiological exposure and contamination of personnel entering the station.

Detailed procedures on the use of protective equipment and supplies are referenced in Appendix D.

6.4.3 Contamination Control Measures

a. Detailed guidance for controlling radioactive contamination of personnel and equipment is provided in the RPM.
b. During accident conditions, the MRCA may approve conditional release of items from the RCA, in excess of RPM release limits. Special controls for release of this equipment will be instituted.
c. Personnel are advised not to consume on-site drinking water and food supplies during an accident, until sampling and analysis are completed.
d. For areas outside the station protected area, RMTs will be used to identify radiation control areas and security will be used to control access. Public access areas of the site will be controlled to off-site radiological criteria.
e. Radiological waste material will be controlled, stored and shipped in accordance with the RPM.
f. Off-site surface contamination and other radiological control criteria are detailed in the state and local RERP.

6.4.4 Personnel Radiation Dose Determination Health Physics (HP) coverage is provided 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to support normal Station operations. During accident conditions, HP technicians may accompany emergency workers, as needed, during RCA entries.

Emergency dosimetry (i.e., self-reading Pocket Ion Chamber dosimeters (PICs) or alarming dosimeters (also called Self Reading Dosimeters (SRDs)) and Dosimeters of Legal Record (DLRs) are used by the initial SERO responders, as necessary. Additional dosimetry is distributed by HP personnel and is issued to individuals, including off-site individuals arriving at the EOF.

DLRs are available from and analyzed by the Dosimetry Laboratory. The

  • individual integrated dose records are maintained by the HP Department.

Exposure information is recorded from* self-reading dosimeters and provides personnel exposure tracking until DLRs results become available. The DLRs results will be used as a permanent exposure record.

Permanent dosimetry will usually be read when it is determined that the emergency workers have received an exposure near their administrative limit or if an overexposure is suspected. All other dosimetry is read on a schedule established by the MRCA.

6.5 Aid to Affected Personnel Provisions are made to assist personnel who are injured and/or have received high radiation exposures. First Aid qualified personnel provide on-site emergency medical services. First aid and decontamination facilities are available on-site and off-site. The following subsections describe measures to be used to provide necessary assistance.

6.5.1 Exposure Control Guidelines In the event of an ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY, emergency worker exposure limits are automatically increased in accordance with EPA 400. This limit remains in effect until mission-specific limit upgrades are required and authorized by the appropriate emergency manager (refer to Table 6-1). The use of radioprotective Potassium Iodide (KI) will be evaluated for administration to on-site and off-site SERO personnel in accordance with emergency procedures. Exposures are commensurate with the significance of the objective and are held to the lowest levels that the emergency permits. In all situations, every reasonable effort is made to minimize exposure to emergency personnel.

Planned actions are carefully examined by weighing the risks and consequences of potential exposure and injury against the probability of success and the benefits to be gained from these actions.

Emergency worker exposure limits and KI issuance for State and local agency responders (i.e., National Guard, police) onsite are controlled by the State of CT or applicable agency.

6.5.2 Emergency Exposure Control Guidelines for Off-Site Personnel If off-site emergency personnel are required during a nuclear incident to support combating fires, provide emergency first aid, .or transport injured and/or contaminated injured to off-site medical treatment facilities, exposure limits as specified in Table 6-1 are applied. Appropriate dosimetry will be issued to all off-site responders in accordance with the RPM .

Off-site medical facility staff personnel performing medical treatment on injured

  • and/or contaminated injured persons shall control exposure in accordance with facility emergency procedures. Medical staff shall be issued appropriate dosimetry (i.e., DLR and SRD).

All dosimetry will be evaluated to determine and document the actual exposure received responding to the emergency.

For security-related events, offsite emergency responders such as the National Guard and State Police will report to the site with their own dosimetry. Dosimetry will be processed by a State contractor. Exposures received will be reported to the individuals and the station, as requested. Exposure control will be through the State of CT or local agency.

6.5 .3 Decontamination Radiological decontamination of personnel, supplies and equipment and waste disposal is conducted in accordance with the RPM, under direction of HP personnel.

Unit 2 and Unit 3 have decontamination facilities which may be used to decontaminate emergency response personnel.

The EOF is the principal decontamination facility during emergencies. A shower with holding tank and supplies for personnel decontan:iination are provided. IT on-site areas are not usable because of inclement weather or continuing releases, the EOF may be used.

6.5.4 First Aid First Aid qualified personnel are available to assist ill or injured personnel on-site 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. IT necessary, a physician may be reguested to provide medical assistance on-site.

6.5.5 Medical Transportation Injured or radioactively contaminated injured personnel requiring hospitalization are transported using local community ambulance services. The ambulance may be requested via dedicated or commercial telephone. The ambulance crews are trained to respond to radiological incidents. Personnel qualified in radiation protection are directed to report. to the receiving hospital or accompany the injured, contaminated patients to the hospital. IT necessary, the receiving hospital will be provided details of patients being transported. Station procedures provide detailed instructions for personnel responding to personnel injuries or contamination .

6.5.6 Medical Treatment

  • Arrangements for the primary care of injured, or radioactively contaminated injured personnel are made with Lawrence and Memorial Hospital in New London and Middlesex Hospital in Middletown. Communications will be by commercial telephone lines. The hospital staff is trained annually and the facility is equipped to treat contaminated injured patients. Contaminated wounds are treated and decontaminated as necessary by the hospital staff.

6.6 Public Information At an Unusual Event Corporate Communications will determine the actions to take regarding notification of media in coordination with corporate management.

In an ALERT or higher public information emergency response personnel consist of the Nuclear News Manager (NNM), Corporate Support Director, Corporate External Affairs Manager, the Millstone Emergency Offsite Representative (MEOR), Corporate Executive Spokesperson (CES), and supporting staff. Public information will be coordinated between the station, the Hartford Armory, and Innsbrook. A variety of methods may be used to share information, including conference lines, Incident Report Forms, electronic or FAXed logs from the DSEO/EIS, and plant monitoring systems (OFIS).

The NNM reports to the MEOR at the Hartford Armory. The NNM interacts with the State and Federal media staff at the Joint Media Center and provides feedback including identified rumor trends to the ICSC. The Corporate External Affairs Manager reports to the Corporate Support Director at the ICSC. The Corporate External Affairs Manager develops and distributes news releases. The NNM may develop and distribute news releases if the Corporate External Affairs Manager is not available. The Corporate Support Director approves news releases. The Millstone Emergency Offsite Representative represents the licensee in communications with state decision makers at the SEOC and represents Dominion Energy in media briefs. The MEOR may be relieved by a CES at which time the MEOR assists the CES in an advisory role and manages the Dominion Energy staff at the Hartford Armory.

Table 6-1

  • Category Emergency Exposure Limits TEDE Annual Part 20 5.0 Rem(I)

Mission to protect valuable property 10.0 Rem(Z)

Mission to save a life or prevent/mitigate a *severe accident 25.0 RemC3)

Voluntary mission to save a life or prevent/mitigate a severe accident >25.0 RemC4)

NOTES:

(1) Automatic exposure up to 5 Rem is allowed in a declared emergency. Members of the SERO responding to on-site emergency response facilities are designated emergency workers subject to NRC 10 CPR 50.47(b).ll radiation exposure controls which are the EPA guidelines for on-site emergency workers.

(2) In accordance with EPA 400, emergency workers can be authorized for an exposure up to 10 Rem TEDE for operations necessary to protect valuable property.

  • (3)

(4)

Depending on station radiological conditions, authorized emergency workers may receive exposures up to a job/mission-specific designated limit, not to exceed 25 Rem TEDE.

Exposures above 25 Rem may be received for life saving activities on a volunteer basis and with full awareness of the risk involved.

  • It is recognized by NRC and EPA that an accident involving significant radiation exposure is a low probability occurrence. An exposure level below 25 Rem is not considered to be life-threatening and will occur once in a lifetime. ALARA principles will be applied when possible.
  • Dose received during an emergency is administratively tracked/controlled in accordance with 10 CPR 20 requirements following termination of the event.
  • Total Effective Dose Equivalent is defined as part of the station health physics program.

1

7. Emergency Facilities and Equipment
  • This section identifies, describes, and gives the locations of emergency operation centers, support centers, communication systems, and first aid and medical facilities. Diagrams of the station emergency response facilities (ERFs) are provided in Appendix F. Locations of the on-site emergency response facilities (ERFs) are indicated in Table 7-1. The various facilities and equipment are controlled and surveilled, using MP-26-EPA-FAPOS, "Emergency Planning Facility Manual," and MP-26-EPA-FAPOl, "Management Program for Maintaining Emergency Preparedness." These documents provide detailed lists of equipment and schedules for conduct of facility/equipment surveillance. Equipment inspection and inventories are conducted quarterly or after known or suspected use of equipment occurs in accordance with this procedure.

Operational checks of emergency equipment are completed at specified intervals and during activation of the emergency response organization.

7 .1 Control Room The Control Room is the primary facility where conditions of the plant are monitored, controlled and corrective actions are taken to mitigate any abnormal conditions. The Unit 1 Central Monitoring Station (CMS) houses one control station in "monitor mode" only (can be reconfigured to the control mode). No control functions are available in the "monitor mode." The Unit 2 control room contains a Programmable Logic Controller (PLC} and one control station (SM' s work station) and two monitors which provide all control and monitoring functions remotely. Both locations provide indications and alarms for Unit 1.

The Control Room provides the main communications link between the Station and the other ERFs concerning system problems as well as long-term and short-term corrective actions. The Control Room is the primary operations center during events classified as UNUSUAL EVENT, and prior to the activation of the other ERFs for ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY classifications. The SM/CRDSEO can initiate and coordinate appropriate procedures from the Control Room until additional assistance is .available.

Emergency lighting, power, ventilation systems, and shielding enable operators to remain in the Control Room to ensure the station can be maintained in a safe condition. In

. addition, the operators are able to evaluate station conditions and relay pertinent information and data to appropriate emergency .facilities, personnel, and agencies during all emergencies. To ensure that operating shift and other personnel can remain self-sufficient, portable radiation monitors, respiratory equipment, portable lighting, and alternate communication systems are maintained in the Control Room.

The Unit 2 and Unit 3 control rooms use the Off-site Facilities Information System (OFIS) as the primary data communications link to the ERFs. In addition, the Unit 2 and Unit 3 Control Rooms have Safety Parameter Display System (SPDS) terminals .

The Unit 2 control room contains one SM's work station and two monitors which provide

  • indications and alarms for various parameters applicable to Unit l's decommissioned condition, including the Spent Fuel Pool Island.

7 .1.1 Normal Operations The Control Room is the on-site location from which the nuclear power plant is

'operated. For Unit 2 and Unit 3, the control room contains the instrumentation, controls, and displays, as applicable to the unit, for:

  • Balance of Plant and Nuclear Steam Supply systems
  • Electrical systems
  • Safety systems (including engineered safety features), and
  • Accident monitoring systems The Unit 2 control room is the on-site location from which the defueled plant is monitored and controlled. It contains instrumentation or displays for the Spent Fuel Pool, Balance of Plant, and Accident Monitoring Systems. If the Unit 2 control station console should become inoperable, the Unit 1 CMS may be used for control and monitoring .

7.1.2 Alert and Notification The Unit 2 and Unit 3 control rooms are equipped with an ENRS terminal from which personnel transmit notification messages. State and local emergency response personnel acknowledge the notification.

7.1.3 Communications In addition to regular direct-dial telephone lines and on-site extensions, the Unit 2 and Unit 3 Control Rooms are equipped with reliable emergency communication systems (dedicated telephone lines, satellite phones, and radios) necessary to alert station and other essential licensee, state, and local community personnel and maintain communications with the station ERFs throughout an emergency. The Unit 2 and Unit 3 Control Rooms, the TSC, and the EOF have a dedicated telephone system to communicate with the NRC .

7.2 Emergency Operations Facility

  • 7 .2.1 Function The EOF serves as a support facility for the management of the overall site emergency response, the coordination of radiological and environmental assessments, and determination of recommended public protective actions. It is the primary communication center and contains appropriate communication links to on-site data sources and off-site organizations.

Emergency radiological monitoring and decontamination equipment and supplies, protective clothing, and respiratory protective devices are also located in the EOF.

In addition, the EOF contains a facility for limited analyses of radiological data.

The EOF is activated during events classified as ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY and is the primary interface between the SERO and.off-site agencies.

  • If an event occurs which prohibits access to the station per NRC Letter A15638, commitment number B18617-10, designated locations are available for EOF SERO response. Full activation may not be possible until the threat conditions have been resolved.

7 .2.2 Location

  • The EOF is located approximately 15 miles north of the station protected area (refer to Appendix F, Figure F-2).

An alternate EOF is located in the Unit 3 Control Room (office area in the back of the Control Room) for key positions.

7 .2.3 Structure and Habitability The EOF is designed for continuous operation during an emergency. It is a rectangular, one-level, above-ground structure. It provides approximately 16,000 ft2 of working space. The EOF is a fenced in facility with a key card security system for entry. It has an Emergency Generator to provide backup AC power.

7 .2.4 Layout The EOF functional areas are indicated in Appendix F, Figure F-2.

  • 7-3

7.2.5 Communications

  • The EOF is the primary communications center at the station during an emergency. The EOF is provided with communications to the control rooms, TSC/OSC, SEOC, Joint Media Center, Innsbrook Corporate Support Center (ICSC), and NRC.

An ENRS terminal is available as well as radios, dedicated telephones, satellite phones, and facsimile machines.

7.2.6 Power Supplies Normal power is provided to the EOF from the power grid. Emergency power is provided automatically by an emergency generator, capable of meeting all EOF power requirements.

7 .2.7 Technical Data and Data Systems The EOF receives plant operational data via the Offsite Facility Information System (OFIS) and direct voice communications with other ERFs. Facsimile machines provide hardcopy communications between ERFs.

7 .2.8 Records Availability and Management An administratively controlled library of station and plant specific drawings and

  • 7.3 procedures is maintained in the EOF. This information is stored at the EOF in hard copy or electronic form.

Technical Support Center/Operational Support Center 7.3.1 Function The TSC provides technical support to plant operations personnel in the Control Room, OSC (co-located with the TSC) and EOF during an emergency. The TSC is activated within 60 minutes of notification of an ALERT or higher event.

TSC personnel are under the direction of the ADTS. The MTSC will use communication networks, data system networks, and available documents to analyze the plant behavior throughout the incident. TSC personnel will also research, collect, and interpret plant parameter data, perform detailed calculations, trend data, determine probable consequences of proposed plant corrective actions and provide engineering recommendations to mitigate plant system degradation.

The MTSC communicates with the MCRO to evaluate plant conditions, and recommends corrective action via the ADTS.

If an event occurs which prohibits staffing the TSC (i.e., Security threat),

designated locations are available for TSC SERO response. Full TSC activation may not be possible until the threat conditions have been resolved.

The ADTS, located in the TSC, provides guidance and direction to the control

  • room operating personnel. The MTSC coordinates with the MOSC to brief emergency repair teams.

The NRC dispatches representatives to the TSC to monitor plant conditions and station emergency technical support activities, and to maintain communications with the NRC senior representative on site.

7.3.2 Location The TSC is located inside the protected area, adjacent to the west side of the Unit 3 control building. An alternate TSC is located in the Emergency Operations Facility.

7.3.3 Structure and Habitability The TSC/OSC is a 2000-ft2 below-ground facility with one-foot thick (minimum) exterior walls and ceiling. It was designed and built in accordance with the Connecticut State Building Code. It is able to withstand the most adverse conditions reasonably expected during the design life of the station.

A dose 'consequence study for the TSC/OSC revealed that the calculated 30-day integrated doses to personnel in the TSC/OSC following a design basis accident at any of the three units are within 10CFRSO Appendix A, General Design Criteria 19 guidelines and the NRC Standard Review Plan for Control Room Habitability:

Limit Thyroid 30Rem Whole body gamma 5Rem Beta skin dose 30Rem The HVAC system is rated for 2,000 CFM and located in the TSC/OSC penthouse, which is above ground level. The facility receives an isolation signal initiating HVAC operation from the Unit 3 control building isolation (CBI) signal.

This system is designed to maintain habitability for facility occupants. Specific occupancy criteria is included in Section 9.4.13 of the Unit 3 Final Safety Analysis Report (FSAR).

7 .3 .4 Layout Work centers exist to enable OSC and TSC personnel to monitor plant data on the OFIS, SPDS terminals, and provide technical assistance. The critical safety functions may be continuously monitored on provided SPDS displays.

The NRC work area provides a space for the NRC to establish local area network communications and monitor OSC and TSC activities. NRC dedicated telephone system connections are provided in addition to site telephone access .

7.3.5 Communications

  • 7.3.6 The OSC and TSC are provided with reliable communications to the control rooms and EOF. A facsimile machine is provided for hard copy data transmission.

Power Supplies The TSC/OSC is powered from the Unit 3 normal power bus. The Security system emergency diesel generator provides reliable backup power to meet all TSC requirements.

7.3.7 Technical Data and Data Systems The TSC will initially receive plant operational data via the Unit 2 or Unit 3 SPDS and/or OFIS system and telephone communications between the TSC and the control room. OFIS automatically records plant system variables and provides history, data trending and graphic print capability to the ERFs.

7.3.8 Records Availability An administratively controlled library of station and plant specific drawings and procedures is maintained in the TSC. This information is stored in hard copy or electronic form.

7.4 Operational Support Center (OSC) and OSC Assembly Area 7.4.1 Function The OSC is a protected area facility, co-located within the same structure as the TSC. Emergency response personnel will assemble in the OSC during an emergency to provide support to the affected control room.

1 The OSC Assembly Area provides a staging area for emergency teams being dispatched during accident conditions, as well as space for additional SERO personnel outside the TSC/OSC.

7.4.2 Location and Size The OSC is located within the TSC/OSC facility adjacent to the west side of the Unit 3 control building. The OSC is approximately 23 feet by 26 feet.

The OSC Assembly Area accommodates support personnel not located in the TSC/OSC facility.

The OSC Assembly Area is located in the Technical Support Building (B475),

Conference Room C-102, which is approximately 50 yards west of the TSC/OSC (see Figure F-3) .

7.4.3 Structure and Habitability

  • 7.4.4 The OSC has the same habitability as the TSC.

The OSC Assembly Area has no specific habitability criteria.

Communications The MOSC will maintain communications with the OSC Assembly Area using normal or dedicated telephones in the OSC. The MOSC will directly communicate with the ADTS.

7.4.5 Emergency Equipment In order to support the OSC function, the following emergency equipment is located in OSC storage locations:

  • Radiation Monitoring Team Kit
  • Portable Radios
  • Protective Clothing
  • Respiratory Protection
  • Access to additional HP and maintenance equipment is readily available to obtain specific materials required to perform OSC functions.

The OSC AA contains the following equipment:

  • Dosimetry issue equipment
  • Portable radios
  • Hotlines and fax machines

7 .5 State Emergency Operations Center

  • 7.5.1 Function The State Emergency Operations Center (SEOC) is activated by the State of Connecticut. Overall direction for response to major emergencies in Connecticut is coordinated by Unified Command (UC) in the SEOC. Participants in the UC include the Governor, various state department leads, federal agencies, and for Millstone emergencies, Millstone/Dominion Energy SERO staff. In this facility, SERO staff advises state officials regarding plant conditions, plant response activities, protective actions, public information messaging and state resources needed to support the response. SEOC SERO staff participates in communications with local town EOCs to provide plant information. SERO staff work with CT DEEP staff in the SEOC supporting independent plant condition analysis and dose assessment activities.

The Joint Media Center is located within this facility. It is activated by the DEMHS and Governor's press staff as the principal media contact point for the licensee, the state and local communities during a Site Area Emergency, General Emergency, or other incidents that may generate high media interest. State and licensee plans do not include use of station facilities for a media center; however space is available for media briefings or conferences at the site.

7.5.2 Location

7.5.3 Structure and Habitability The State of Connecticut, DEMHS maintains this facility available 24/7 as an all hazards emergency response facility.

7 .5 .4 Layout Space in the SEOC includes the UC center, work spaces for various agencies and non-governmental organizations including Millstone SERO staff, meeting areas, kitchen facilities, restrooms, and the Joint Media Center. Space is provided to allow SERO staff to maintain contact with other ERFs.

7.5 .5 Communications SERO staff at the SEOC communicates with the EOF and the ICSC using commercial telephone lines, email and/or FAX. OFIS monitoring capability is provided for SERO and DEEP staff. Millstone maintains a direct line for the DEEP to receive Protective Action Recommendations (PARs) from the DSEO, and a direct line for the DEEP to contact the DEEP representative in the EOF .

7.5.6 Technical Data and Data Systems

  • 7.5. 7 The SEOC receives plant operational data via the Offsite Facility Information System (OFIS) and direct communication with other ERFs.

Records Availability and Management Procedures, job aids and presentation materials are stored at the SEOC for use by Millstone SERO staff.

_7.6 Emergency Equipment Emergency equipment is stored at various on-site locations, including the control rooms, TSC/OSC, access points and the EOF.

For a representative list of emergency equipment, see Appendix E. Emergency equipment is maintained in accordance with station procedures including MP-26-EPA-FAPOl and MP-26-EPA-FAPOS.

7 .6.1 Emergency Response Data System (ERDS)

The ERDS, established in accordance with regulatory guidance, is provided via electronic data transfer. An ERDS link is initiated within an hour of an ALERT or higher emergency classification. An ERDS link is not provided for Unit 1.

  • 7.7 Security Posts The security posts that are established and used during an emergency. are addressed in general terms to avoid disclosing safeguards information. More specific information is contained in the proprietary Security Plan and procedures.

The Station Security Department primary objectives during an emergency are to maintain adequate station security, facilitate the precautionary dismissal and evacuation of the protected area and outlying areas, and assist . with emergency communications, as necessary.

Either the Central or Secondary Alarm Station will become the Security Command Console if an emergency occurs and will function as an on-site emergency communications center during the first 60 minutes while the SERO is being activated.

Security computer proximity card reader units are used to perform accountability for the protected area. Accountability can be performed via alternate method if proximity card reader units are inoperable.

7.8 Alternate Locations

  • 7 .8.1 An alternate location is designated for off-site officials who are unable to reach the EOF due to radiological or environmental conditions near the EOF. The Alternate Location is physically located at the SEOC (Armory) in Hartford, Connecticut. The alternate location has communications capability with the site emergency response facilities (i.e., EOF, TSC, control room). There is enough space to accommodate off-site officials requiring access to site emergency managers.

7.8.2 The EOF in Norwich, CT, functions as a staging area for augmentation of emergency response staff if the site is under threat of, or experiencing, hostile action. This location has the capability to communicate with the control rooms and plant security.

7.9 Communication Systems The communication links between emergency response centers and off-site agencies are shown in Figures 7-1 a through 7-1 c. These systems provide reliable communications and consist of a combination of the station PA system, emergency alarm, intraplant telephones, computer terminals, dedicated hotlines, commercial and utility (tie-line) telephones, satellite phones, facsimile machines, and two-way radios including utility, State Police, Waterford Police, and ISO New England radio communications. In addition, the Station has NRC dedicated telephone system lines installed in the Unit 2 and Unit 3 control rooms, EOF and TSC .

Two-way radio communications are used to maintain communication between the EOF and RMTs. Police and utility radio communication are used by the Control Room in the event of the failure of the telephone system for off-site communications. Backup power is maintained for selected communication links in the protected area and the EOF.

Ambulances are equipped with radios and can communicate with the hospital. Normal communication between the station and off-site medical facilities will be over commercial telephone. There are also hotline telephones between the Central Alarm Station and TSC/OSC to the State Police, Waterford Police I Waterford Emergency Communications Center.

The states of New York and Rhode Island are within the 50-mile ingestion pathway EPZ and are contacted through the Connecticut DEMHS and State Police as described in the State RERP. Fishers Island and Plum Island, New York, are within the plume exposure EPZ and are notified of emergency events via ENRS .

7.10 Assessment Facilities

  • Appropriate on-site and off-site monitoring instruments and laboratory facilities needed to analyze an accident are available 24-hours per day and are listed in Appendix H, Tables H-1 and H-2. The MRDA and MRCA will coordinate the collection of sample media by the Radiological Monitoring Teams (RMTs). The RMTs will return samples to the EOF for analysis when directed. Appendix B provides letters of agreement with private laboratory facilities specified in Table H-2. Post-accident environmental samples are collected by responsible state agencies and analyzed by the State Health Department laboratory. The licensee will assist the State of Connecticut in the collection of environmental samples under direction and control of DEEP, as requested.

7.11 First Aid and Medical Facilities 24-hour per day first aid services are provided by first aid qualified personnel, as a minimum, with multi-media first aid training. First aid supplies and equipment are stored in various locations throughout the station. The Site Medical Facility is also available during selected hours, which may provide equipment and personnel to assist in medical emergencies.

7.12 Damage Control Equipment Damage control equipment cons1stmg of fire hydrants, fire hose stations, fire extinguishers, and portable lanterns are provided throughout the station for fire fighting.

Self-contained breathing apparatus is located strategically throughout the station for fire fighting and entry into airborne radioactivity or toxic gas areas. Selected equipment spare parts are stored in the warehouse for emergency repairs. Tools and equipment required for equipment maintenance are available in the maintenance shops.

7.13 Meteorological Data Acquisition The Millstone site has a primary meteorological installation consisting of a 450-foot instrumented tower, a climate-controlled shelter, and a computerized data acquisition system. Wind speed and direction are measured at four different levels: 33, 142, 374, and 447 feet. Vertical temperature difference is measured at 142, 374, and 447 foot levels: the vertical interval in all three cases is measured from a baseline height of 33 feet. The critical parameters of wind speed, wind direction, and a measure of atmospheric stability are continuously available in the Unit 2 and Unit 3 Control Rooms and at the base of the meteorological tower. Other non-critical meteorological parameters are also measured.

The site has a backup meteorological monitoring system located near the training facility.

The system consists of a IO-meter instrumented mast, a climate-controlled shelter, and a backup computerized data acquisition system. Additional information may be obtained from a weather service organization, listed in Appendix B.

The primary source of meteorological data used by the meteorological team is the EDAN

  • system, an electronic dafa acquisition network. If EDAN is inoperative, the critical data may be obtained over the telephone from operators reading Unit 3 Plant Process Computer data. If the primary meteorological tower instruments are not operating properly, the backup meteorological installation located near the training building may be used. If both on-site systems are inoperative, arrangements have been made to obtaip information from the assisting weather service organization.

7.14 Innsbrook Corporate Support Center (ICSC)

The ICSC located near Richmond, VA, is required to be activated to provide support during an ALERT or higher event at Millstone Power Station. When activated, the function of the ICSC includes public information and may include logistical support in the event of an emergency at Millstone .

Table 7-1

  • On-site
1. Control Room Locations Of Emergency Response Centers Location Unit 2 and 3 Control Room
2. OSC Assembly Area (OSC AA) Cafeteria, Bldg 475
3. Technical Support Center/Operational Adjacent to and below Unit 3 Control Bldg.

Support Center (TSC/OSC)

4. Alternate TSC EOF
5. Alternate EOF Unit 3 Control Room (office area in the back of the Control Room)

Off-site Location

1. Emergency Operations Facility 18 Stott Avenue, Norwich, CT
2. Assembly Area Simulator Foyer in the Training Building
3. Joint Media Center Connecticut State Armory (Hartford)
  • 4. State Emergency Operations Center
5. Local Community Emergency Operations Centers
6. Alternate Location Connecticut State Armory (Hartford)

Refer to the Local Community Radiological Emergency Response Procedures State EOC (Armory) Hartford, CT

7. Remote Mustering Area EOF, Norwich, CT
8. Offsite Monitoring Location EOF, Norwich, CT Corporate Location
1. Innsbrook Corporate Support Center Richmond, VA (Innsbrook)

(ICSC)

Figure 7-la Notification of Emergency Response Organizations ON-SITE STATE & LOCAL COMMUNITY RESPONSE CENTERS EMERGENCY RESPONSE CENTERS T

T CONTIGUOUS T CONTROL ROOM STATES OEM UNITS2AND3 (RI) (NY)

EN T

T STATE DEEP*

EN EOF*

EN EN STATE POLICE TROOPEANDF T STATE DEPT OF PUBLIC T

SAFETY COMM CENTER TSC/OSC/OSC AA Legend:

EN EN - T Commercial Telephone Lines I STATEDEMHS T EN Electronic Notification T

STATION ON-CALL T AFFECTED COMMUNITY RESPONSIBLE OFFICIAL EMERGENCY RESPONSE EN 1. East Lyme 7. Montville ORGANIZATION 2. Fishers Island (NY) 8. New London EN

3. GrotonCity 9. Old Lyme

~

4. Groton Town 10. Plum Island (NY)
5. Ledyard 11. - Waterford
6. Lyme 12. Suffolk County (NY)
  • Located offsite 7-14 Millstone Station Emergency Plan Revision 56 March2018

Figure 7-lb NRC Emergency Notification System (ENS) and Health Physics Network (HPN) Millstone Station ON-SITE EMERGENCY FEDERAL GOVERNMENT RESPONSE CENTERS EMERGENCY RESPONSE CENTERS Control Room I Units 2 and 3 E

~ ..--D_e_d_ic_at_e_d_li_ne-,s are bridged between NRG and Utilityfacilitie NRG NRG E I .... Emergency .... E

  • Region 1 Emergency Operations ...,,,,,.._ _ _ H __ ......._ Emergency Operations Facility*

H -;- ~ Center ~ ,,,,,...-- Response Center I ,' H I

Technical Support Center

.... I I I

. I I

. I NRG EOF H -+- . - - J Legend:

-E ENS - Emergency Notification Command Post E System, dedicated hotlines.

.I HPN - Health Physics Network

- - H-

.I normal long distance .

NRG Resident's ~

I

~ E Office MPEA...AN6.PPT

  • Located offsite 7-15 Millstone Station Emergency Plan Revision 56 March2018

Figure 7-lc Lines of Communications Between Emergency Response Centers Millstone Station On-Site Emergency Response Centers . State and Local Community Emergency Response Centers Dominion Energy Corporate Executive I

.I

.I Contiguous States (RI) (NY) - -T-

~

(£) -T-Control Room

.I

-R- I Unit 2 and 3 I

I

~

- -R-1

.I

-- Affected Community EOG (Waterford) --T- -T-

-R-Affected Community EOG I

I I I

-- State DEEP Desk -T- -R-I State EOG

-R- I -T- TSC/OSCQ)

I I

I .

I I

T- OSCAA

-- I I Innsbrook .I -- State Armory

(£)

~

Dominion Energy I

I Corporate Support Center I

I State EOG Joint Media Ctr.

~

-T-Corporate Nuclear Public I I

- . I Information

~

---,,,.. -- I I State Police -T-

-- Operations Emergenc~ -I- . I Troop "F"

~

to-

-- - - - - I -R-Facility/Center* -,..

I -R- State Police Troop "E" d:

---~.

Legend:

Radiological - T - Commercial ....,.. ~ Dedicated Telephone Telephones Dept of Public Safety

-R- ~ Monitoring .:I:

Teams - R - Radio (U2/3 only) Comm. Center 0 FAX Machine - - Data Line

- Information Line to Dominion Energy

  • Located offsite 7-16 Millstone Station Emergency Plan Revision 56 March 2018
8. Maintaining Emergency Preparedness
  • Station management is responsible for the staffing of the SERO and approval of station emergency plan procedures.

The Manager, Emergency Preparedness is responsible for the following:

  • Maintenance and readiness of the on-site emergency response facilities and equipment.
  • Maintenance and development of the Station Emergency Plan and implementing procedures (Appendix D).
  • Training off-site emergency response personnel.
  • Conducting and providing input to SERO training.
  • Scheduling, coordinating, and conducting SERO training using EP Personnel.
  • Assisting station management to ensure effective emergency plan implementation.
  • Collecting and reviewing additional BP-related information such as severe accident management research, and NRC regulations and industry research, for incorporation into the EP Program.

The Manager, Emergency Preparedness is assisted by the EPD staff. Appropriate EPD staff training is ensured by attendance at NRC/FEMA seminars/meetings, academic institutions, industry conferences/meetings, on-the-job training, and supervised work assignments.

Administration and management of emergency preparedness programs is detailed in Emergency Preparedness implementing and administrative procedure.

The Manager, Nuclear Training, is responsible for scheduling, coordinating, and conducting SERO training using Nuclear Training Department personnel. The Manager, Nuclear Training, will obtain assistance as necessary from discipline managers in the conduct of discipline-specific training. In addition, the Manager, Nuclear Training, is responsible for supporting chemistry drills and health physics drills. The Supervisor Nuclear Training is responsible for conducting required fire drills.

8.1 Training 8.1.1 SERO Training The goal of the Emergency Plan Training Program is to provide SERO personnel with the additional skills and knowledge necessary for them to effectively respond to an emergency at the station. The SERO Training Program provides both initial and requalification training on an annual, calendar year basis .

Appendix K provides a summary listing of training topics for SERO personnel.

  • 8.1.2 Section 5, Table 5-1 lists the topics for personnel by SERO position. Detailed training lesson plans and administrative requirements for SERO personnel are contained in TR-AA-TPG-2400 and MP-26-EPA-FAPOl.

Off-Site Emergency Response Training Training for local off-site emergency response personnel, such as local fire, police, mutual aid responders and emergency management officials is offered annually. Training for off-site agencies consists of radiation protection, emergency classification, notification, emergency plan overview and general plant access information. Local ambulance staff are trained annually in plant access and the medical treatment of contaminated, injured patients. Hospital emergency room staff are trained annually in medical treatment of contaminated patients.

State personnel, representing agencies at the State EOC, are trained in specific procedures through participation in periodic drills. fu addition, responsible state agencies are trained in emergency classification. Field monitoring and sampling team personnel are trained annually in radiation protection, monitoring and ingestion sampling procedures.

Host community emergency organizations are trained in radiation monitoring and protection, activation and operation of evacuee reception centers.

a. Plant Access Training (PAT)

Employees obtaining unescorted access to the station for the first time receive general instruction on the Emergency Plan as part of their plant access training. This includes a review of the purpose of emergency planning, the emergency classification system, and the precautionary dismissal, and evacuation. This information is reviewed annually as part of the employee's Plant Access Training Program. Company and contractor personnel obtaining unescorted access to the station receive general instruction on the Emergency Plan as part of their plant access training.

b. Fire Brigade Training The Fire Brigade is composed of designated station firefighting personnel.

fuitial and annual refresher training is provided to Fire Brigade Members in accordance with training department procedures.

c. First Aid Teams First Aid Teams are provided Medic First Aid training program: "Basic Plus - CPR, AED and First Aid for Adults" or equivalent at a minimum.

8.2 Tests, Drills, and Exercises

  • Drills and exercises are conducted to ensure that the participants are familiar with their emergency duties and responsibilities; to verify the adequacy of and methods used in station emergency plan procedures and other emergency procedures; and to verify emergency equipment function.

Drills are conducted for SERO personnel at intervals throughout the year. The drills may be combined with classroom refresher training for each SERO position. Drills may be conducted as an evaluated event or a training drill, where controllers provide immediate correction of erroneous pe1formance. Guidance for the conduct of drills and exercises is provided in regulatory guides published by NRC and FEMA. Detailed methodology for the structure, administration and conduct of drills is contained in EP-AA-400, "Drill and Exercise Program." Drill comments are also tracked and dispositioned using the station Corrective Action process.

8.2.1 Off-Site and On-Site Testing of the Notification, Communication, and Alerting Systems

a. Communication Tests Communication tests shall include an aspect of understanding message content as well as testing the equipment.
  • The site emergency alarms and emergency responder notification systems tests are conducted monthly.
  • Communications with specific state and local officials within the plume exposure pathway EPZ are tested at least monthly.
  • Telephone numbers in emergency plan procedures are reviewed quarterly and corrected as necessary.
  • The NRC dedicated telephone systems are tested monthly.
  • Communications capability between the RMTs and emergency centers are tested quarterly and during drills or exercises.
  • Communications with federal emergency response organizations and states within the ingestion pathway EPZ are tested quarterly by the State DEMHS.
  • The ERDS system for Unit-2 and Unit-3 is tested quarterly .
b. Off-site Public Alerting System Testing
  • The testing of the Public Alerting System (sirens) and communications is detailed in the State and local RERPs. Silent tests may be performed during the full or partial-participation exercise. Silent tests, system polling, individual siren growls, and full load checks are described in MP-26-EPA-FAP09, "Alert Notification System Test and Maintenance," and are performed at varying frequencies. Records on siren availability are kept by the Emergency Preparedness Department and summaries are forwarded to the State DEMHS on an annual basis.

8.2.2 Additional Tests, Drills, and Exercises The schedule for conducting drills and exercises is as follows:

a. Fire Drills Fire drills will be conducted in accordance with CM-AA-FPA-100 (Fire Protection/Appendix R (Fire Safe Shutdown) Program). The Training Department is responsible for the review and approval of fire drill scenarios. Fire drill discrepancies shall be entered into the Corrective Action Program (CAP) and will be assigned to the appropriate department to evaluate and to take corrective actions. The Site Fire Marshall shall also review and disposition, as necessary, comments from fire drill critiques .
  • b. Medical Emergency Drills The Manager, Emergency Preparedness is responsible for conducting annual medical drills. Arrangements for training and drills are made through the Lawrence and Memorial Hospital or Middlesex Hospital Emergency Departments, as applicable. A medical exercise, involving simulated contaminated and injured worker(s), local ambulance service personnel, station security, health physics and hospital emergency staff is conducted annually.

C. Radiological Monitoring Drills Environmental radiological monitoring drills (on-site and off-site) are conducted annually and can be conducted as part of the annual exercise.

These drills include collecting and analyzing environmental samples.

Communications and record-keeping procedures are also checked during these drills.

d. Health Physics Drills Health physics drills are conducted semi-annually and involve response to and analyses of simulated elevated airborne and liquid samples and direct radiation measurements .

8-4 Millstone Station Emergency Plan Revision 56 March2018

e. Emergency Plan Training Drills
  • The Emergency Preparedness Department is responsible for scheduling two emergency plan training drills annually for Unit 2 and Unit 3, and one for Unit 1. These drills generally include functional areas identified in Table 5-1. (These include the annual rehearsal and exercise.) The Emergency Preparedness Department will also conduct drills involving severe accident management implementation and terrorist based events at intervals established by the 8-year schedule.
f. Exercises Emergency Preparedness exercises are conducted in accordance with 10 CFR 50.47(b) and 10 CFR 50 Appendix E requirements.

The Emergency Preparedness Department is responsible for coordinating exercises to test station, state(s), and local emergency plans. Station procedures ensure 8-year exercise cycle objectives are met.

Millstone Power Station shall exercise the emergency plan annually.

Millstone Power Station shall exercise the emergency plan with off-site authorities (state and local government) every two (2) years, with full or partial-participation by state and local governments within the pluine exposure pathway EPZ. The level of participation shall be as follows:

  • The State of Connecticut shall at least partially participate in each off-site exercise at Millstone Power Station.
  • The State of Connecticut shall fully participate in at least one off-site exercise every two (2) years.
  • Partial participation by a local government is acceptable, with FEMA approval, when the local government is fully participating in a biennial exercise at another site, or a combination of the following enable demonstration of all exercise objectives:
1) FEMA credits actual incident* response for required objectives.
2) The local government cannot demonstrate exercise objectives due* to conflicting schedules and required objectives can be demonstrated out-of-sequence with the main exercise.
3) Compensatory measures can be demonstrated by another
  • entity.
  • The states of Rhode Island, Connecticut and New York, which are responsible for emergency responses within the 50 mile ingestion exposure pathway EPZ, shall exercise their plans and preparedness related to ingestion exposure pathway measures at least once every 8 years.
  • The licensee shall enable any state or local government located within the plume exposure pathway EPZ to participate in an annual exercise when requested by such state or local governments.
  • The licensee shall make provisions to conduct an off-hours exercise between the hours of 6:00 p.m.

and 4:00 a.m. every 8 years.

Remedial exercises will be required if the plan is not satisfactorily tested during the biennial exercise, such that NRC, in consultation with FEMA, cannot find reasonable assurance that adequate protective measures can be taken in the event of a radiological emergency. The extent of state and local participation in remedial exercises must be sufficient to show that appropriate corrective measures have been taken regarding planning

  • g.

elements not properly demonstrated during the previous exercise.

Post-Exercise Critique An in-house, post-exercise critique will be conducted.

  • Exercise evaluators will discuss emergency response observations during the critique. The exercise observations and comments shall be compiled into a formal exercise evaluation report by the Emergency Preparedness Department.
  • The Emergency Preparedness Department is responsible for tracking corrective actions for exercise critique comments.
  • The Emergency Preparedness Department will evaluate comments, assign responsibilities and track the resolution process. Station management will ensure corrective actions are completed as necessary .

An off-site post-exercise critique will be scheduled at the conclusion of

  • each exercise by FEMA to allow official observers and evaluators from federal agencies and state and local communities to evaluate the performance of the various emergency response organizations. The critique will be chaired by FEMA. Additionally, the critique is open to the public and news media.

8.3 Administration of Station Emergency.Plan and Procedures The Station Emergency Plan contains elements of planning that involve assistance and coordination of governmental agencies and intra-company groups. In order to achieve and maintain the most efficient course of emergency action, liaison is continuously maintained with state and local agencies responsible for public safety.

The Station Emergency Plan and letters of agreement are reviewed on an annual basis and updated as appropriate. Changes to the Emergency Preparedness Program are evaluated in accordance with EP-AA-101, 10 CFR 50.54(Q) Change Evaluation, for 10 CFR 50.54(q) prior to implementation. Changes to the Station Emergency Plan and implementing procedures are undertaken in accordance with station administrative procedures and subject to evaluation under 10 CFR 50.54(q).

Evacuation time estimates (ETEs) are developed within 365 days of when U.S. Census Bureau decennial data becomes available. ETEs are reviewed against estimated EPZ permanent resident population changes at least once a year and within 365 days of the

  • date of the previous ETE or its most recent review. Increases of ETEs greater than the limits detailed in 10 CFR 50 Appendix E require the ETE analysis be updated. The decennial ETE and its updates are submitted to NRC as required by 10 CFR 50 AppendixE.

10 CFR 50.54(t) reviews of the Emergency Preparedness Program are performed at the frequency required by 10 CFR 50.54(t)(l) by the licensee oversight group or an industry peer evaluation team. The reviews include the Emergency Plan, implementing procedures and practices, training, readiness testing, equipment, an evaluation of the adequacy of interfaces with state and local government and the conduct of drills and exercises. The reviewer completes a written report that details the items reviewed and corrective actions to be taken. The report is sent to the Manager, Emergency Preparedness and to corporate and station management. The Manager, Emergency Preparedness is responsible for evaluating and correcting report findings. Documentation of report findings and corrective actions shall be maintained for a period of no less than five years. Applicable portions of the report will also be made available to federal, state, and local organizations.

The Chairperson of the Management Safety Review Committee (MSRC) receives the report. Unresolved findings from the review are identified to the oversight group management in writing. Review items are not closed until final corrective actions are taken .

8.4 Public Information Programs

  • Specific emergency instructions are provided primarily via a booklet mailed annually to residences, commercial establishments and emergency management officials within the plume EPZ. The emergency information booklet includes a description of the Public Alerting System, a list of Emergency Alert System stations, sheltering and evacuation checklists, a map of evacuation routes to Host Community Reception Centers, and detailed information about radiation and its effects. The booklet also includes contact points and references to various emergency planning websites. This booklet is made available to the general public on the State's DEMHS website.

A brochure for annual distribution and posting at State designated public areas within the EPZ serves the transient population, in addition to selected telephone directories that contain abbreviated emergency public information. Special needs mailers with a pre-posted return form are sent directly to EPZ residents for voluntary registration with their local emergency officials.

The State of Connecticut DEMHS is provided with information for posting or distribution, as appropriate, at selected public areas within the EPZ.

Other on-going elements of the Public Information program include:

1) Educational Outreach Programs. These programs are conducted out of the Nuclear Training Center. The Outreach Program provides public informational and educational activities throughout the EPZ.
2) Speakers comprising a variety of company employees from many disciplines and operational functions, provides information on nuclear power to numerous institutions, civic and professional groups, and other organizations.

8.5 Media Information Program A media information program is offered annually to acquaint the news m~dia with emergency plans, information concerning radiation, and points of contact for release of public information in an emergency.

A media manual, developed to meet the needs of the news media, contains plant specific information and general information concerning emergency planning, nuclear power and radiation. The manual is distributed to the local media and is available for issue at the Joint Media Center at the time of an emergency.

9. Recovery
  • 9.1 Recovery Phase The Organization for Recovery Operations (ORO) is activated by the DSEO.

The recovery phase occurs after the plant is brought to a long-term stable state. When this occurs the emergency organization will no longer be required to take corrective or mitigating actions to respond to the accident.

If normal resources are adequate to recover the plant to normal operations, the emergency organization is disbanded and the event is terminated. If the unit is damaged and the recovery actions require extensive resources and/or will last from months to years, the ORO will replace the SERO. A Director of Recovery Operations will be designated to convene an event review meeting and investigate the cause.

9 .2 Recovery Organization The ORO is illustrated in Figure 9-1.

9.2.1 Site Vice President - Millstone The Site Vice President - Millstone is responsible for coordinating the station recovery operations.

9.2.2 Director of Recovery Operations (DRO)

.The Director of Recovery Operations (DRO) is responsible for overall direction of

  • recovery operations and reports to the Site Vice President - Millstone.

The Director of Recovery Operations (DRO), as well as those managers reporting directly to him, are chosen by station management. They possess competent managerial skills and are experienced in their areas of responsibility.

9 .2.3 Manager of Technical Support The Manager of Technical Support is responsible for the following:

  • Providing necessary technical support services.
  • Analyzing core parameters and other technical information.
  • Performing reactor systems analysis.
  • Providing a central facility for collecting, retaimng, and retrieving data.
  • Providing post accident data analysis timeline for the accident.

9-1 Millstone Station Emergency Plan Revision 56 March2018

  • Developing recovery procedures .

Developing and approving proposed modifications to procedures, systems and equipment.

Determining recovery activities needed to be documented in accordance with the Quality Assurance (QA) program.

9.2.4 Manager of Plant Operations Manager of Plant Operations is responsible for the following:

  • Supervising and maintaining a station support staff during the recovery operation.
  • Maintaining an effective station security program.
  • Implementing maintenance and repair operations with station staff.
  • Coordinating Facility Safety Review Committee (FSRC) activities as necessary.

9.2.5 Manager of Radiation Control/Radwaste Manager of Radiation Control/Radwaste is responsible for the following:

  • Assisting the State DEEP as necessary in off-site recovery phase sampling, survey measurements and data analysis to determine re-entry and recovery actions for off-site areas.
  • Developing and performing evaluations of health physics equipment and procedures for recovery operations.
  • Performing special dosimetry evaluations or providing specialized dosimeters.
  • Developing plans and procedures to sample, process, and control liquid,_

gaseous, and solid radioactive waste, and coordinating waste disposal activities.

  • Maintaining an ALARA program.
  • Developing decontamination plans.
  • Assisting the State DEEP in determining total integrated population doses by using various inputs .

9.2.6 Manager of Engineering Systems

  • Manager of Engineering Systems is responsible for the following:

Providing required engineering support services.

Interface and consultation with engineering and technical experts, as needed.

  • Acquisition and coordination of manpower and equipment to support repair activities.
  • Acquisition of housing, office, and construction equipment to support recovery operations.
  • Arranging for the purchase of legal and insurance assistance.
  • Providing general administrative support.
  • *Scheduling and expediting recovery operations.
  • Assisting the DRO in planning activities.
  • Coordination of recovery staff meetings .

Tabulating, expediting and closing out commitment lists in support of recovery operations.

Establishing cost control procedures.

9.2.7 Advisory Support Staff Advisory support staff personnel provide support to the DRO in various areas. .

9.2.8 Corporate External Affairs Manager The Corporate External Affairs Manager provides liaison with the media.

9.2.9 Licensing Department The Licensing Department interfaces with the NRC and other regulatory agencies on licensing issues.

9.2.10 Millstone Representative in the SEOC and Joint Media Center The Millstone Representative in the SEOC and Joint Media Center provides advisory support to state and local communities .

Figure 9-1 Recovery Organization Site Vice President - Millstone I

Director of Advisory Recovery - Support Operations I

I I I I I Manager, Millstone Station Manager, Manager, Radiation Manager, Representatives in Technical Plant Control and Engineering the State EOG and Support Operations Radwaste Joint Media Center

  • System Analysis *Affected unit staff *Waste Treatment *INPO *Millstone Liaison
  • Core Physics plus other station Design *Engineering with the State EOC
  • Data Reductions staff as applicable *ALARA Evaluations and official media
  • Vendors spokesperson.

(Post-Accident *Waste Disposal *NE Analysis Data) *Support State

  • Personnel Exposure *NSSS response to FEMA Evaluations I Licensing I *Specialized Dosimetry
  • Resources
  • Construction questions.
  • Support local
  • Purchasing responses to
  • NRG/State *Field Survey and questions and Environmental *Legal licensing evaluate needs.

Sample Teams *Insurance

  • Off-site and On-site *Project Management surveys, sampling for *Schedules recovery/reentry *Cost Control decision making 9-4 Millstone Station Emergency Plan Revision 56 March2018

Appendix A APPENDIX A DEFINITIONS, ABBREVIATIONS AND ACRONYMS

Appendix A This section provides definitions of commonly used terms that are applicable to this Emergency

  • Plan .

DEFINITIONS Absorbed Dose The quantity of energy imparted from ionizing radiation per unit mass of tissue.

Alternate Location A designated facility (SEOC [Armory]) where off-site officials can communicate with company officials if access to the EOF is impaired.

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

Corrective Actions Those emergency measures taken to improve or terminate an emergency situation.

  • Emergency Actions Actions taken as a result of reaching an Emergency Action Level.

Protective Actions An action taken to avoid or reduce a projected dose.

Recovery Actions Actions taken after an emergency to. restore the station to pre-emergency condition and decide on re-entry of the public affected areas.

Airborne Radioactivity Any radioactive material dispersed in the air in the form of dusts, vapors, gases, etc.

Clean Area An area free of contamination or with levels of contamination below the specified limits .

Appendix A Owner Controlled Area

  • The area within the site boundary including the protected area.

Protected Area The area within the Millstone Power Station security fence.

Radiological Control Area An area within the restricted area in which radioactive material is present and the potential exists for the spread of radioactive contamination. The area will be posted for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials.

Background Radiation Radiation arising from material other than the one directly under consideration such as from cosmic rays, the ground, the air, building materials, etc.

Barrier One of the three fission product barriers: fuel clad, RCS pressure boundary and containment.

Barrier Based EALs

  • A table of symptoms defining the loss or potential loss of a barrier, e.g., the Barrier Reference Table. A combination of barrier losses defines an emergency classification level.

Central Monitoring Station {CMS)

The Unit 1 facility from which indications and alarms are monitored and control functions performed, if necessary.

Certified Fuel Handler An individual who has qualified in accordance with an approved fuel handler training program.

Condition (also called initiating condition)

A description of a nuclear power plant event where either the potential exists for a radiological emergency, or such an emergency has occurred; e.g., loss of both batteries for greater than 15 minutes is a condition with a category of events titled Loss of Power.

Confinement Boundary The sealed dry cask storage canister that provides the spent fuel cladding protection. The barrier between areas containing radioactive substances and the environment.

Appendix A Contamination (Radioactive)

  • The deposition of radioactive material in any place where it is unwanted (e.g., on persons, products or equipment).

Control Room The Control Room is the primary location where conditions of the unit are monitored, controlled and where corrective actions are directed to mitigate any emergency.

Curie The unit of radioactivity which is equivalent to 3.7 x 1010 disintegrations per second; millicurie (mCi) = one-thousandth curie; microcurie (µCi) = one-millionth curie; picocurie (pCi) = one-millionth microcurie.

Decontamination The reduction or removal of contaminating radioactive material from a person, area or object by cleaning or washing.

Dosimeter A device that records radiation exposure.

  • Emergency Any abnormal condition that could affect the health and safety of people or safe operation of equipment.

Emergency Action Levels (EALs)

Thresholds for initiating emergency actions such as designating a particular class of emergency, initiating a notification procedure, or initiating a particular protective action.

Emergency Classification System A system that arranges abnormal conditions in order of severity. They are listed as follows in order of increasing severity:

  • UNUSUAL EVENT (State Posture Code, DELTA ONE/DELTA TWO)
  • ALERT (State Posture Code, CHARLIE-ONE)
  • SITE AREA EMERGENCY (State Posture Code, CHARLIE-TWO)
  • GENERAL EMERGENCY (State Posture Code, BRAVO/ALPHA)

( (

Appendix A Emergency Operations Facility (EOF)

  • A facility located 15 miles north of Millstone from which station act1v1t1es related to an emergency will be carried out and from which information will be provided to the corporate, federal, state officials and local community chief executive officers.

Emergency Planning Zone (EPZ)

An area surrounding the Millstone Power Station for which planning is conducted to ensure that prompt and effective actions can be taken to protect the public in the event of an accident. For the plume exposure pathway, the EPZ has a corresponding radius of about 10 miles; and for the ingestion exposure pathway, the EPZ has a corresponding radius of about 50 miles.

Event Based EAL A listing of symptoms and conditions under generic event categories.

Event Category A generic group of plant conditions; e.g., loss of power, equipment failure, radiation hazard, security threat, etc.

Exposure Pathway Plume Exposure Pathway

  • The pathway by which exposure to a radioactive plume and subsequent deposition of radioactive material could result in external exposure and by which inhalation of the radioactive plume could result in internal exposure.

Ingestion Exposure Pathway The pathway by which deposited radioactive materials could be ingested from contaminated water or food, such as milk or fresh vegetables which would cause internal -

exposure.

Full Staffing SERO positions which are beyond the required minimum staffing. Full staffing positions, as a goal, will be staffed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of SERO activation. Personnel assigned to fill these positions are drawn from a pool of qualified individuals .

Appendix A Hostile Action

  • An act toward a Nuclear Power Plant (NPP) 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 NPP. Non-terrorism based EALs should be used to address such activities (e.g., violent acts between individuals in the owner control 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.

Incident An unexpected occurrence that could lead to an emergency.

Independent Spent Fuel Storage Installation (ISFSD A complex designed and constructed for the interim storage of Millstone Power Station spent nuclear fuel.

  • Joint Media Center The Joint Media Center is the principal contact point between the media and Millstone Station, state, and local community representatives. It is a facility where informational releases are made to the public and media and press conferences are held.

Minimum Staffing Personnel assigned to fulfill a specific SERO position and who report to the station in accordance with Table 5-1. *

  • On-Shift Personnel assigned to duties as part of a normal shift complement.

Off-site The area outside the owner controlled area of the Millstone Power Station.

On-site The area inside the owner controlled area of the Millstone Power Station.

(

Appendix A Operational Support Center (OSC)

  • A center co-located with the TSC where operational support of the emergency is provided.

OSC Assembly Area An emergency repair team staging area supporting OSC activities.

Precautionary Dismissal A dismissal of non-essential personnel at the Alert level which directs all non-essential Millstone employees, contractors, and visitors to leave the site.

Procedures Emergency Operating Procedures {EOP)

Procedures which provide specific actions to mitigate the consequences of and terminate an emergency situation.

Emergency Plan Implementing Procedures (EPis)

Procedures which implement the Station Emergency Plan. These procedures specify the emergency organization and actions that would be required of station and other on-site personnel during an emergency.

  • Supplemental Procedures Station operating, health physics, radiological control, administrative, security and training procedures.

Projected Dose The estimated potential dose that could be. received by affected individuals if no protective actions are taken.

Protective Action Guides (PAGs) .

Projected absorbed dose to individuals in the general population which warrants protective action.

Radiation (ionizing)

The emission and propagation of energy through a medium in the form of electromagnetic waves or particles which impart their energy to the medium through the creation of electrically charged ion pairs directly or indirectly in its passage through the medium.

Appendix A Radioactivity

  • The property possessed by certain unstable radionuclides of spontaneously emitting charged particles, gamma photons or X-rays.

Radiopager System The system used by Millstone Power Station for prompt notification of emergency response personnel.

Shift Manager's Work Station The Unit 2 control room location from which indications and alarms for Unit 1 are monitored and control functions are performed.

Station Emergency Operations Center A facility in Hartford, CT, where responses to overall direction for major emergencies m Connecticut are coordinated.

Station Emergency Response Organization The organization responsible for station operations under emergency conditions.

State

Site Evacuation The orderly withdrawal of personnel from the owner controlled area except designated resource and SERO personnel.

State Plan The State of Connecticut Emergency Operations Plan, Annex V, Fixed Nuclear Facilities Radiological Emergency Response Plan.

Station Evacuation The orderly withdrawal of all personnel from the protected area, except designated resource and SERO personnel.

Symptom A predetermined site and unit specific parameter observable in the Control Room (or reported to the Control Room) that is the threshold for a plant "condition" that places the plant in a given emergency classification. A symptom can be an instrument reading, equipment status indicator, a measurable parameter (on-site or off-site), a discrete observable event, or the results of analyses .

Appendix A Technical Support Center (TSC)

  • A center located where technical support personnel monitor station conditions and provide data interpretation.

Appendix A ABBREVIATIONS AND ACRONYMS

Alternating Current Administrative Auxiliary Feedwater Assistant Director Technical Support As Low As Reasonably Achievable ALI Annual Limit on Intake ALS Advanced Life Support AMRDA Assistant Manager Radiological Dose Assessment AMT Accident Management Team ANI American Nuclear Insurers ANSI American National Standards Institute AOP Abnormal Operating Procedure ARC American Red Cross ARCOS Automated Rose Call Out System ARMS Area Radiation Monitoring System ARPS Assistant Radiation Protection Supervisor ASME American Society of Mechanical Engineers ATWS Anticipated Transient Without Scram BAST Boric Acid Storage Tank BLS Basic Life Support BP Blood Pressure BWR Boiling Water Reactor CAR Containment Air Recirculation (system)

CBETS Computer Based ExposureTracking System 3

CCorCM Cubic Centimeter CDA Containment Depressurization Actuation CDC Center for Disease Control CDE Committed Dose Equivalent CEDE Committed Effective Dose Equivalent CERT Community Emergency Response Team CBS Corporate Executive Spokesperson CFH Certified Fuel Handler CFM Cubic Feet per Minute CFR Code of Federal Regulations Ci Curie (Unit of Radioactivity)

CMS Central Monitoring Station co Control Operator

Appendix A CRDSEO Control Room Director of Station Emergency Operations

  • CRS css CST CT CTNG eves Control Room Simulator Core Spray System Condensate Storage Tank Connecticut Connecticut National Guard Chemical and Volume Control System DAC Derived Air Concentration DBA Design Basis Accident DBE Design Basis Earthquake DC Damage Control DEMHS Division of Emergency Management and Homeland Security DENC Dominion Energy Nuclear Connecticut DEEP Department of Energy and Environmental Protection DHS Department of Health Services (formerly DHEW)

DIL (FDA) Derived Intervention Level DLR Dosimeter of Legal Record DSEO Director of Station Emergency Operations DOE U.S. Department of Energy DOT Department of Transportation DPH Department of Public Health (CT) dpm/100 cm2 Disintegrations per minute per 100 square centimeter area DPM Disintegrations per minute DRO Director of Recovery Operations EAL Emergency Action Level BAS Emergency Alert System EC Emergency Communicator ECCS Emergency Core Cooling System ED Emergency Department (hospital)

EDAN Environmental Data Acquisition Network EDG Emergency Diesel Generator EIS Emergency Information Specialist EMR Emergency Medical Responder EMS Emergency Medical Services EMT-B Emergency Medical Technician - Basic EMT-P Emergency Medical Technician - Paramedic ENRS Emergency Notification and Response System ENS NRC Emergency Notification System telephone BOC Emergency Operations Center (State, local, or Site)

BOP Emergency Operating Procedure EOF Emergency Operations Facility EPA Environmental Protection Agency EPAP Emergency Plan Administrative Proc~dure EPC Emergency Planning Coordinator

Appendix A EPI Emergency Plan Implementing Procedure

  • HAB HEPA HP HP HPN Hostile Action Based High Efficiency Particulate Air Filter Health Physics High Pressure NRC Health Physics Network Telephone HVAC Heating Ventilation and Air Conditioning System I Iodine I&C Instrumentation and Calibration IC Incident Commander ICP Incident Command Post ICSC Innsbrook Corporate Support Center ILRT Integrated Leak Rate Testing INPO Institute of Nuclear Power Operations IPZ Ingestion Pathway Zone IRF Incident Report Form ISFSI Independent Spent Fuel Storage Installation ISI In Service Inspection JIC Joint Information Center JMC Joint Media Center

(

Appendix A KI Potassium Iodide

  • KW KWh LCO LER LI Kilowatt Kilowatt-hour Limiting Condition for Operation Licensee Event Report Level Indicator LOCA Loss of Coolant Accident LPCI Low Pressure Coolant Injection LPSI Low Pressure Safety Injection MA Massachusetts MAX Maximum MCI Mass Casualty Incident MCL Media Center Liaison MCRO Manager of Control Room Operations Met Meteorological MEOR Millstone Emergency Offsite Representative MOC Manager of Communications MOR Manager of Resources MOS Manager of Security MOV Motor Operated Valve MP Millstone Point MPS Millstone Power Station MRCA Manager of Radiological Consequence Assessment MRDA Manager of Radiological Dose Assessment mR MilliRoentgen mRad MilliRad mRem Millirem = 1/1000 Rem mRem/hr 1/1000 Rem per hour MRC Medical Reserve Corporation I

MSIV Mairi Steam Isolation Valve MSRC Management Safety Review Committee MTSC . Manager of Technical Support Center MW Megawatt NAP North Access Point NCRP National Council on Radiation Protection (and Measurement)

NEI Nuclear Energy Institute NFSA Nuclear Fuel and Safety Analysis (formerly RES)

NG National Guard NRC U.S. Nuclear Regulatory Commission NNM Nuclear News Manager NOUE Notification of Unusual Event NSSS Nuclear Steam Supply System

Appendix A NSST Normal Station Service Transfer

  • NUREG NY QBE OFIS OMF Nuclear Regulation New York Operational Basis Earthquake Off-site Facilities fuformation System

.Qffsite Monitoring Facility - EOF oos Out of Service ORO Organization for Recovery Operations osc Operational Support Center OSCAA Operational Support Center Assembly Area PA Physician's Assistant PA Public Address System PAD Protective Action Decision PAG Protective Action Guide PAR Protective Action Recommendation PASS Post Accident Sampling System PAT Plant Access Training PC Protective Clothing PD Police Department PEO Plant Equipment Operator PF Protection Factor PIO Public fuformation Officer PIR Plant Incident Report PORV Power Operated Relief Valve PRA Probabilistic Risk Assessment PSAP Public Service Answering Post PSI Pounds per Square Inch PSIG Pounds per Square Inch Gauge PWR Pressurized Water Reactor PZR Pressurizer Q Release Rate QA Quality Assurance R Roentgen. A unit of radiation exposure rad Unit of radiation dose RAE Radiological Assessment Engineer RC Reception Center RCA Radiological Control Area RCP Reactor Coolant Pump RCS Reactor Coolant System REM Unit of radiation dose Resp Respirations RERP Radiological Emergency Response Plan

Appendix A RHR Residual Heat Removal

  • RIEMA RL RMS RMT RO RP Rhode Island Emergency Management Agency Regulatory Liaison Radiation Monitoring System Radiological Monitoring Team Reactor Operator Radio Pager RPM Radiation Protection Manual RWP Radiation Work Permit RWST Refueling Water Storage Tank SAE Site Area Emergency SAP South Access Point SCBA Self-Contained Breathing Apparatus SDO Station Duty Officer SEOC State Emergency Operations Center SERO Station Emergency Response Organization SIS Safety Injection System SM Shift Manager SOP Step Off Pad SPDS Safety Parameter Display System Sp02 Oxygen saturation SRD Self Reading Dosimetery SRO Senior Reactor Operator STA Shift Technical Advisor State State of Connecticut TA Technical Assistant TEDE Total Effective Dose Equivalent TIC Technical Information Coordinator TSA Transportation Staging Area TSC Technical Support Center TSCEE Technical Support Center Electrical Engineer TSCSM Technical Support Center Shift Manager UC Unified Command us Unit Supervisor USCG US Coast Guard u Wind speed

µCi Microcuries X (chi) Concentration X/Q Relative Concentration

AppendixB APPENDIXB LETTERS OF AGREEMENT

AppendixB

  • Page B-3 B-4 Organization Amtrak Electric Boat Division of General Dynamics B-5 Institute of Nuclear Power Operations B-6 Lawrence & Memorial Hospital B-7 Middlesex Hospital B-8 Shipman's Fire Equipment Company, Inc.

B-9 State of Connecticut, Department of Emergency Services and Public Protection-Office of the Commissioner B-10 Teledyne Brown Engineering B-11 Town of Waterford Ambulance Service B-12 Town of Waterford Fire Service B-13 Town of Waterford Police Department  ;

B-14 AccuWeather B-15 GEL B-16 Norwich Fire Department B-17 Salem Volunteer Fire Department Note: The letters of agreement are reviewed annually and verified to be current. Only letters with significant changes require reissue.

AppendixB J)foveroher 1-3,,2017 w.ir- ~pnJ1 pau9,~i9J-W-Site Vice Rtesideht Ootriinion Nuclear Connecticut RopJ:l*Ferry Road W~ferforq_; OT 0:6_~85.

beat'Mr, tJaugherty:

Thl!S lett~r Js fo' confirm that tne National f{ailtoad Passenger Corporation will, when re~qe&teq respqpd in tn13:e.ventof ?n -~rnergency:~fJt1eMiJliton~ Power S.ta;tiorl on I ..on,9 lsJ~iJtl: ~04nd, in the fqllgwing ~reasi ** * **

fmplemenfatiort CHt~ria/Authorities. Respons16iiit1es nii? our-und9-rs~ndingthaf, in the event of an emetgency,; thenucieat faciJityDirector:Site Ememe.rrcy '.Qp~~t,pci's roay ceq1:1esfour-f.:lS$isJanc~, ,A$sistctnc:e should be requested by caJUiig th~ Ghief Tri:lin D.isp_at¢h$r pf ttie ~'qston (}ETC Office at .P1l3.45_"'.7474.. lndicat§ 0

fhe nature of the incident; the locatiort, and the type;ofiassistarn;:e reqqired.

Measures*to be.Prov1ded/Umits-0fAdions Qur commitment Jor 'P~ist&nce is fa ciire:OUr~in:traffi.c away from.any area$ that may be af(ect$d bythe erii~rgengf *

  • lnformatfon Exchange}Po,nf of .Contact atS1te:.

Verification communications fo the nuclear facility, Wilt be,by telephone,to: the Dfrector of

$ite Emerge,ngy Operatiqns. *~ 83078!!32:"Po!JO~ Jnf.ormafiqn exchange can be provided by 4siris tne,Ghil3fTran Qispat¢h~rs ovmot7t, -*

  • Training *and Driiis Ple*ai~ notjfy .us of your plant drill$ so. that we may: have the opportunity tcf observe,your emergenPY response alcitions an~f meet your e.mergency operations p~rsonnel, Please

-copraJhat?l PY .96nti:tcting n:W qfflq$. a.f 617/~45:.740:(f - *

AppendixB

  • :B:!~fe~t~~~;-~.

Pag~Twb . ' ..... .

This l~tt~ bfagre.e.rn~nt ~hc:1!Lr~m-~i11 in ~ffec:t µntil qaoqeUa~ion :by ejf:h~r :party, provid~d on 'ninefy'(90): cfays* priQr\;l(f~43f!:rtq,ti¢e, ari~ §hgll:1?/:!te.vi,~weq ang 9.~Jtjijeo a~in~Elcj~d.

a,_,, 1-

,ti:;~<

$inperely, :

Tran$portation

'N.o(fheast:$upDivl&.ien

-cc~ w~ Et Moore, DepµJt'Gni~f+*4\m~rp'k. Police.

s~ P49sl~y;. Amtrak Emergency Management

L_

AppendixB

  • Enclosure (1) to 438-37497 Page 1 of2 LETTER OF AGREEMENT BETWEEN ELECTRIC BOAT CORPORATION AND DOMINION NUCLEAR CONNECTICUT RADIOLOGICAL ASSISTANCE It is understood that the Electric Boat Corporation will, upon request, respond with personnel and equipment in the event of an emergency at the Mlllstone Power Station in accordance with the following:
1. In the event of a radiological emergency, the Director of the Site Emergency Organization may request personnel and equipment to assist in performing emergency radiological surveys. Assistance should be requested by calling:

Director of Radiological Services Telephone: 433-3139 (during normal business hours)

2. If after normal business hours, or no answer, call In order:

RAD CON Office: 433-5019 or 433-5392 Shipyard Security: 433-5530 or 433-5531

  • NOTE: If shipyard Security is contacted, request that RAD CON Management be notified.

It is understood that the Electric Boat Corporation's commitment for assistance includes providing trained radiological control personnel and equipment for the purpose of performing emergency radiation, contamination, and airborne radioactivity measurements. Personnel responding to the facility's request for assistance will report to the Manager of Resources who will be located in the Emergency Operations Facility (EOF) .

AppendixB

  • It Is understood that should the Electric Boat shipyard be affected by a radioactive Enclosure (1) to 438-37497 Page2 of2 release from another facility, Electric Boat resources will be used, as the first priority, to protect the shipyard and Its personnel; support will be provided to Millstone Station as available.

It is understood that In each case where assistance Is provided under this Agreement, all radiological waste from the emergency will remain the responsibility of the affected facility.

It is understood that verification of communications will be by telephone to:

Manager of Resources - 442-5139 Director Station Emergency Organization - 443-2276 Information exchange can be provided by using the same telephone number.

It is understood that MIiistone Station will train representatives of Electric Boat Corporation's Radlologlcal Training Section annually on the use of Station equipment and procedures. These Radiological Training Section individuals, In tum, will train selected Electric Boat Corporation personnel on this equipment and procedures. It is understood that this training will be performed annually and the Electric Boat Corporation will be given advance notification of plant drills or additional training that would be advantageous to both organizations.

This Letter of Agreement shall remain in affect until cancellation by either party, provided on ninety-(90) days prior written notice, and shall be reviewed and certified as needed.

Dominion Nuclear Connecticut Electric Boat Corporation By: *' -: ~#{/JU&& jh //2:U>v)*~

Name: _ _____,J,_,_.,._,Al'-"a,,_,n_._P-'-'ri""'ca,,___ __ M. Toner

Title:

Site Vlce-Presjdent President Date: -~,_I /_o_*y....._/_v_.,___ __

"+I

AppendixB

  • AGREEMENT BETWEEN PARTIES Nuclear Power Plant Emergency Response Assistance Agreement November 8, 2013 This Nuclear Power Plant Emergency Response Assistance Agreement (hereinafter "Agreement") has been entered into by and among INPO and electric utilities that have responsibility for the construction or operation of commercial nuclear power plants under a license issued by the U.S. Nuclear Regulato:ry Commission pursuant to Title 10 of the Code of Federal Regulations (hereinafter "nuclear power plants") and that have subscribed counterpart signature pages in the form attached hereto (hereinafter "Parties").

The Parties wish to set forth herein their understanding and agreement with respect to their mutual undertaking to each other in the situation wherein an emergency occurs at a nuclear power plant under the control of or operated on behalf of a Party or wherein an event arises during the transportation of nuclear materials shipped by or on behalf of a Party, and a request for assistance is issued to another Party and such assistance is provided. For purposes of this agreement, a nuclear power plant emergency is defined as an event warranting classification as a site area emergency or greater and that has -the potential to damage fuel.

This Agreement is intended only to define the terms and conditions under which such assistance will be rendered and received. It is understood that this Agreement does not impose any obligation on any Party to render or continue to render any such assistance, but this Agreement records the understanding of the Parties with respect to the rights and obligations that will be incurred in responding to requests for assistance. Attachment A, "Coordination Agreement on Sharing Emergency Information Among EPRI, INPO, NEI, and Their Member Utilities" describes the responsibilities and expected actions for EPRI, INPO, and NEI.

NOW, THEREFORE, it is agreed, that:

1. Assistance rendered by a Party as described hereunder may be given in response to a request by any Party for help following an emergency arising at a nuclear power plant or during the transportation of nuclear materials. If such assistance is given, it shall be rendered in accordance with the terms and conditions herein.
2. The Party that requests assistance shall be known as the "Requesting Company" and the Party furnishing assistance s:\].all be known as the "Responding Company."
3. Assistance shall be defined as the requested, offered and/or actual responsive assistance to a request under the terms of this Agreement by a Responding Company, as documented in an Assistance Agreement.
4. Assistance Agreement shall be defined as a scoping document that may be as informal as an email, fax, or phone request (followed with documentation) in emergency circumstances that lists the requested, offered and agreed upon Assistance, that references this Agreement, and that is agreed to by both the Requesting and Responding Parties.

1

AppendixB

  • 5. (a)

AGREEMENT BETWEEN PARTIES November 8, 2013 Requesting Company shall notify INPO or a Responding Company of the type of assistance requested and the anticipated duration during which such assistance is desired.

IfINPO is contacted directly, then INPO shall identify and contact the appropriate Responding Companies to ask for help in responding to an emergency. If a Responding Company is called directly, then the Responding Company may furnish such assistance that is within the scope of this agreement. Except as such companies may agree otherwise, Requesting Company shall be responsible for determining the procedures to be followed relative to the furnishing of such, assistance, directing the work, and making any

  • reports to governmental authorities and the news media regarding the emergency or the furnishing of assistance pursuant to this Agreement. Requesting Company shall notify Responding Company when its assistance is no longer needed.

(b)

The :furnishing of assistance hereunder shall be deemed to have commenced when personnel of the Responding Company are assigned to other than normal duties or transportation of equipment commences pursuant to a determination by the Responding Company to provide assistance to a Requesting Company under this Agreement and shall be deemed to have terminated when the transportation of such personnel or equipment back to its working base, or home (for personnel returning at other than regular working hours), is completed.

(c) .

The Responding Company shall make all arrangements for the transportation of its personnel and equipment from and to their working base or home.

6. (a)

Employees of Responding Company shall at all times continue to be employees of the Responding Company and shall at no time and for no purpose be deemed to be servants, agents, employees, or representatives of the Requesting Company.

(b)

Wages, hours, and other terms and conditions of employment applicable to personnel of the Responding Company shall be those of the Responding Company. Work procedures, security, and safety rules for such personnel shall be those of the Requesting Company.

(c)

Unless otherwise agreed, all personnel of the Responding Company shall be equipped by the Responding Company with such normal working and protective equipment as shall be compatible with the circumstances under which said personnel shall function hereunder; Requesting Company shall inform Responding Company of any specific equipment which may be required in a particular situation.

2

AppendixB

  • AGREEMENT BETWEEN PARTIES November 8, 2013
7. (a)

Responding Company shall furnish the requested personnel and equipment to the extent that the Responding Company may determine to do so in its sole judgment and discretion.

(b)

Any information which Responding Company may provide to Requesting Company (including drawings, reports, and analyses) or which Requesting Company provides to Responding Company, which either the Responding Company or the Requesting Company considers proprietary or confidential, shall be so designated. Such proprietary information shall be held in confidence and shall be used exclusively in connection with the emergency at the nuclear power plant at which the emergency has occurred (including necessary disclosures on a proprietary basis to others in that connection) and shall not be published or otherwise disclosed to others, except .as may be required by law. The restrictions set forth in this section 7.(b) shall not apply to information that the Receiving Company can establish by documentary evidence:

(1) is or has become generally lmown to, or readily ascertainable by, the public without fault or omission of either party or its employees or agents; or (2) was already lmown to the Receiving Company prior to the first disclosure of such information by the disclosing party; or (3) was received by the Receiving Company without restrictions as to its use from a third-party who is lawfully in possession and not restricted as to the use thereof; or (4) was independently developed through persons who have not had, either directly or indirectly, access to or knowledge of similar information provided by the other party.

(c)

Responding Company shall have the right, at any time and in its sole judgment and discretion and without any obligation to Requesting Company, to withdraw personnel and equipment furnished to the Requesting Company and return such personnel and equipment to its wor~g base. Without limiting Responding Company's rights under the preceding sentence, Responding Company shall attempt to schedule any such withdrawal of its personnel or equipment to accommodate the needs of Requesting Company.

Responding Company shall give written notice at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in advance to Requesting Company of the permanent withdrawal of personnel or equipment furnished. Responding Company's withdrawal of personnel or equipment shall not affect any obligations which may have been incurred hereunder prior to such withdrawal or which may arise out of events occurring prior to such withdrawal.

8. All time sheets and work records pertaining to Responding Company personnel and equipment shall be kept by the Responding Company. The Responding Company shall furnish the Requesting Company with a detailed statement of all costs and expenses paid or incurred by the Responding Company in connection with the furnishing of assistance to the Requesting Company, which statement shall be paid by Requesting Company within thirty (30) days after receipt.

3

AppendixB

  • AGREEMENT BETWEEN PARTIES
9. The Requesting Company shall reimburse Responding Company for all direct and November 8, f013 indirect costs and expenses, not :includ:ing a profit, incurred by Responding Company in giving assistance pursuant to this Agreement, includ:ing but not limited to costs and expenses related to or resulting from compliance with governmental requirements such as Title 10 of the Code ofFederal Regulations Part 20. Such costs and expenses shall be computed in accordance with Responding Company's standard rates and accounting practices, including such overheads as are determined by Respond:ing Company to be applicable to such direct and indirect costs and expenses incurred by Responding Company. Requesting Company shall have the right to request a third party audit the records of Responding Company relative to work performed pursuant to this Agreement.
10. (a)

In addition, and subject to the provisions of paragraph 1O(b) hereof: Requesting Company shall indemnify and hol!'.l Responding Company, its officers, directors, and employees, jointly and severally, harmless from and against any and all liability or loss, damage, cost, or expense which any of them may :incur by reason of bodily injury, including but not limited to death, to any person or persons, or by reason of damage to or destruction of any property, including but not limited, to any property located at the site of the Requesting Company's nuclear power*plant or the loss of use of any property, which results from furnishing assistance pursuant to this Agreement, whether due in whole or :in part to any act or omission, or negligence of Responding Company, its officers, directors; or employees;

  • (b)

Where payments are made by Responding Company or its insurers to Responding Company's officers, directors, or employees or their beneficiaries for bodily injury or death resulting from furnishing assistance pursuant to this Agreement, including but not limited to workers' compensation, disability, pension plan, medical and hospitalization, or other such payments, Requesting Company, shall make reimbursement to Responding Company to the extent such payments increase the Responding Company's employees' related costs, whether such increase in costs occur in the form of an increase in premiums or contributions, a reduction in dividends or premium refunds, or otherwise. Requesting Company shall also reimburse Responding Company for any deductible amounts or for any amounts paid by Responding Company as a self-insurer. Responding Company will request its insurer to waive any right of subrogation it may have against Requesting Company as a result of any payment described in this paragraph 1O(b) which such insurer may make on behalf of Responding Company because of Responding Company's furnishing of assistance pursuant to this Agreement.

4

(

AppendixB

  • (c)

AGREEMENT BETWEEN PARTIES November 8, 2013 Responding Company makes no warranty with respect to any goods or services provided to Requesting Company and NOWARRANTY, EITHER EXPRESS OR IMPLIED, ORAL OR WRITTEN, SHALL APPLY TO THE GOODS OR SERVICES PROVIDED, INCLUDING, WITHOUT LIMITATION, THEWARRANTIES OF MERCHANTABILITY AND OF FITNESS FOR SPECJFIED OR INTENDED PURPOSE. All equipment and services furnished by Responding Company pursuant to this Agreement are furnished as is.

(d)

In the event any claim or demand is made or suit, action, or proceeding is filed against Responding Company, its officers, directors, or employees, jointly or severally, alleging liability for which Requesting Company shall indemnify and hold harmless Responding Company, its officers, directors, and employees under this paragraph 10 hereof, Responding Company shall promptly notify Requesting Company thereof, and Requesting Company, at its sole cost and expense, shall settle, compromise, or defend the same in such manner as it in its sole discretion deems necessary or prudent Responding Company shall cooperate with Requesting Company in the resolution ofany such matter.

If a Requesting Company settles a liability suit with a 3rd party that involves a Responding Company, Requesting Company will e,:isure the Responding Compnay is released from liability.

(e)

Each Party to this Agreement agrees to carry the amount of financial protection required

  • by the Atomic Energy Act of 1954, as amended, and self-insurance or comprehensive liability insurance, including contractual liability coverage, covering the indemnification and defense obligations set forth herein, subject to such types and amounts of self-insurance, retentions, or deductibles as are consistent with standard business practice in the industry.

(f)

In the event a Responding Company provides assistance pursuant to this Agreement through an affiliate or subsidiary, the indemnification provided in this paragraph 10 to the officers, directors, and employees of that Responding Company shall apply with equal force to the officers, directors, and employees of that affiliate or subsidiary.

11. Each Party shall provide the Institute of Nuclear Power Operations (hereinafter "INPO")

with an executed counte:rpart signature page to this Agreement and to any amendments or attachments hereto. This Agreement shall become effective when counterpart signature pages executed by at least two Parties shall have been received by INPO. This Agreement shall remain in effect as to any Party until such Party has withdrawn from the Agreement as provided below.

5

AppendixB

  • 12. (a)

AGREEMENT BETWEEN PARTIES November 8, 2013 INPO may provide certain administrative and emergency response support services in furtherance of this Agreement, such as maintaining and distributing to the Parties a roster ofthe signatories to this Agreement; providing copies of the Agreement and any amendments thereto to all Parties; and preparing and distributing to the Parties other documents, such as a list of sources of emergency manpower and equipment. INPO may provide such other services as may be requested of INPO from time to time by the Parties. The Parties recognize that INPO shall not be responsible for implementing, enforcing, or intetpreting this Agreement.

(b)

The Parties shall defend, indemnify, and hold harm.less INPO, its officers, directors, and employees, jointly and severally, from and against any and all liability or loss, damage, cost, or expense which results from performance of INPO's functions described in paragraphs 12(a) and 12(c) of this Agreement Each Party hereby expressly waives any right it may have to assert any claim against lNPO, its officers, directors, or employees arising out of its or their performance of INPO's functions described in paragraphs 12(a) and 12(c).

(c)

Following an emergency at a nuclear power plant the Requesting Company may contact INPO for help in locating and coordinating delivery of requested resources and equipment. Based on that contact from the Requesting Company, INPO will proceed to locate requested equipment and human resources and coordinate assistance delivery. This agreement does not preclude the Requesting Company from contacting other Parties (Responding Companies) for assistance. In either case the Assistance Agreements will be established between the Requesting Company and Respon~g Companies.

(d)

If lNPO :furnishes assistance and unless otherwise agreed by INPO and the Requesting Company, the Requesting Company and INPO l';hall have the same rights and obligations as ifINPO were a Responding Company (including but not limited to the Requesting Company's obligations to INPO, its officers, directors, and employees under paragraph 10 hereof), except that paragraphs 8 and 9 and lO(e) shall not apply to INPO.

13. This Agreement will.not create any rights or defenses in favor of any entity or person not a signatory to this Agreement-except to the extent provided in this paragraph and in paragraphs 10 and 12 of this Agreement. This agreement shall be bina.ing upon and inure to the benefit of each signatory to this Agreement and the subsidiaries and affiliates of each such signatory.

6

AppendixB

  • AGREEMENT BETWEEN PARTIES November 8, 2013
14. Except as otherwise provided in paragraph 15, any Party may withdraw from this Agreement upon at least thirty (30) days prior written notice to INPO with a copy to all of the other Parties. Notice of withdrawal shall not affect any obligations which may have been incurred hereunder prior to the effective date of such notice or which may ~rise out of events occurring prior to the date. No Party may withdraw from this Agreement while it is receiving assistance pursuant to this Agreement.
15. This Agreement may be amended by the agreement of a majority of the Parties hereto.

Such amendment shall be effective and binding upon all Parties thirty (30) days after INPO has received counterpart signature pages for the amendment executed by at least a majority of the Parties to the Agreement. INPO shall notify all Parties when at least a majority of the Parties have executed an amendment to the Agreement. No amendment shall affect any obligation that may have been incurred hereunder prior to the effective date of such amendment or that may arise out of events occurring prior to that date.

Notwithstanding the first sentence of paragraph 14, any Party may withdraw from this Agreement by submitting written notice to JNPO at any time during the thirty (30) day period prior to the effective date of such amendment with a copy to all of the other Parties.

16. If any provision of this Agreement is determined to be "invalid or unenforceable as to any Party or otherwise, such determination shall not affect the validity or enforceability of the other provisions of this Agreement as to that Party or otherwise.
17. In the event (i) an emergency occurs at a nuclear power plant under the control of or operated on behalf of a Party, or an event associated with transportation of nuclear materials shipped by or on behalf of a Party; (ii) a request for assistance is issued to another Party hereto in respect to such emergency; and (iii) such !:ISSistance is provided, this Agreement shall be construed in accordance with the law of the State in which the nuclear power plant is located with respect to all rights and obligations arising out of such emergency.
18. This Agreement, together with the attachments hereto, shall constitute the entire agreement between and among the parties hereto relating to nuclear power plant emergency response. This agreement, once signed, supersedes previous assistance agreements among the parties hereto.

7

AppendixB

  • EXHIBIT AGREEMENT BETWEEN PARTIES November 8, 2013 COUNTERPART SIGNATURE PAGE The undersigned company hereby agrees to become a Party to the Nuclear Power Plant Emergency Response Assistance Agreement and its attachments.

Date 11)1'2..,.)!3 Company "1) 0 N '"' 1"'.J By~ (Corporate OJ;ficer Signature)

Printed Name: Df\v '-.O (+/-. \:\::t'"& c~ Cf(.

8

AppendixB

  • Coordination Agreement on Sharing Emergency Information Among EPRL INPO. NEI. and Their Member Utilities

Background:

In order to provide for the efficient and timely transfer of technical and public information regarding emergencies at nuclear power stations and to maximize their assistance roles to their utility members and the industry, the Electric Power Research Institute (EPRI), the Institute of Nuclear Power Operations (INPO), and the Nuclear Energy Institute (NEI) have agreed to coordinate their actions and activities as outlined in this agreement.

It is recognized that the primary responsibility for release of appropriate information concerning an emergency situation to the public and the news media rests with the affected utility. The pU.Ipose of this agreement is to provide a coordinated process by which the industry organizations can effectively convey information to the rest of the industry and to the media, in order to lessen the burden on the affected utility.

Agreement:

1. Among the three organizations involved in this coordination agreement, NEI will provide information concerning industrywide implications of an emergency and will use existing mechanisms and media contacts to disseminate timely information regarding the emergency.
  • NEI will develop and issue, in coordination with the affected utility, appropriate p1,1blic st_atements to the news media, as necessary.
  • NEI will provide information about the emergency and associated press releases to its members and other industry organizations.
  • NEI also will make all relevant information available to Edison Electric Institute (EEi) andEPRI.
  • NEI will maintain an emergency response capability for consultation on regulatory issues and handle inquiries from media, government, and other organizations and individuals.
2. Among the organizations, INPO will coordinate assistance requests from the utility tq other INPO members and participants.
  • INPO will notify NEI and EPRI of U.S. events classified Alert or higher or non-U.S.

events classified as level 4 or higher on the International Nuclear Events Scale.

  • INPO will provide communications to its members, participants, EPRI and NEI to facilitate the flow of technical information about the emergency and share information provided by the affected utility on a selected basis.

9

AppendixB

  • INPO will maintain an emergency resource capability to furnish EPRI and NEI technical information relevant to the. emergency as obtained from the utility and/or available in its ovvn databases.
  • JNPO will maintain information on industry assistance capabilities including:

o Personnel with specialized plant or emergency response knowledge a Emergency response equipment available for sharing with the affected utility.

  • INPO will coordinate the delivery of persons and material under its Nuclear Power Plant and Transportation Agreements, as requested by the affected utility.
3. Among the organizations, EPRI will maintain an emergency response capability and will be available for consultation and to conduct in-depth analyses of the emergency as appropriate.
  • Both EPRI and INPO will be available to assist the affected utility through their technical analysis and events analysis capabilities, respectively. EPRI and INPO will coordinate such efforts with each other.
4. EPRI, INPO, and NEI will develop and share written procedures governing emergency notifications and specifying points of contact to provide for cross-notification of emergencies.

10

AppendixB

  • EXHIBIT COUNTERPART SIGNATIJRE PAGE AGREEMENT BETWEEN PARTIES November 8, 2013 The undersigned company hereby agrees to become a Party to the Nuclear Power Plant Emergency Response Assistance Agre=ent and its attachments; Date January 3. 2014 Company Institute ofNuclear Power Operations By LJ.J~ C:. G J ~ ~ (CGrporate Officer Signature)

Printed Name: William E. Webster, Executive Vice President

AppendixB

  • I 1\11 LAWRENCE

~ I +MEMORIAL SRUCE D. CUMMINGS Pr<>sldent & Chief Ex<lcutlve Officer email: bcummings@irnhc-sp.org 365 Montauk Avenue I New London, CT 06320 860.442.0711, Eld. 4545 I FAX860.271.4474 November 23, 2015 John Daugherty, Station Vice President Dominion Nuclear Connecticut Inc.

PO Box128 Waterford, CT 06385

Dear Mr. Daugherty,

This letter is to confirm that Lawrence+ Memorial Hospital will respond in the event of a radiological emergency at Millstone Power Station.

Implementation Criteria /Authorities. Res.ponsibilities It is our understanding that in the event of an emergency, the nuclear facility may request medical assistance. The Hospital Emergency Department is to be contacted at calling (860)442-0711 ext.

2261 and requesting to speak to Emergency Department Charge Nurse to activate our Radiation Accident Plan.

Measures to be Provided/Limits of Action Our commitment for medical assistance includes patients who might be injured as a result of an industrial or radiation accident and who are in need of medical treatment at Lawrence+ Memorial Hospital.

This letter of agreement shall remain in effect until cancelation by either party, provided on ninety (90) days prior written notice, shall be reviewed and certified as needed.

Sincerely,

~ - ,. ~ ? ,..-_

--- .,'§:"..c-.--~*

D. Cummings, FACHE President and CEO cc:

  • Oliver Mayorga, MD, Chair, Emergency Department - Lawrence+ Memorial
  • Ron Kersey, Emergency Medical Services Coordinator - Lawrence+ Memorial
  • Karen Ramus-Stone RNC, MSN, Director of Parent/Child, Critical Care, Paramedics and Emergency Services - Lawrence+ Memorial
  • D. Smith, Emergency Planning Service - Dominion Nuclear Connecticut, Inc.

AppendixB

  • ADMINISTRATION

/~MIDDLESEX HOSPITAL November 19, 2015 Mr. John Daugherty Vice Pl'esident & Senior Nuclear Executive Dominion Nuclear Cormecticut, lnc.

Millstone Power Station Rope Ferry Road Waterford, CT 06385

Dear Mr. Daugherty:

This letter represents a continuance of the Letter of Agreement between Millstone Power Station and Middlesex Hospital.

Middlesex is ready to receive and administer treatment to accident victims sent to us by Millstone Power Station. We will provide backup and supp01t for Lawrence and Memorial Hospital, acting as the secondary medical treatment facility for the Millstone Station. Any expenses incurred as a result of providing these services will be the responsibility of Millstone Power Station.

In case of au emergency situation, we would follow the plan for "Decontamination and Treatment of the Radioactively Contaminated Patient at Middlesex Hospital," currently in effect between our institution and the facility mentioned above.

If you have any questions concerning our arrangements for contaminated patients, please contact me.

Gary vican Vice President Strategic Planning & Ambulatory Operations GH:aac c: David A. Smith, Manager, Emergency Preparedness, Millstone 28 Crescent Stteet

Middletown, Connecticut 06457-3650 tel 860 344-6000 A member of rhe Middlesex Healrh System fax 860 346-5485

AppendixB

  • Sl:fi.PM.AN'S ff8E:~uur~MENT:CO., lNG.
m.~RQSS RP!
\P WATERFOJ\'Q, CQNN,1:CTlc;t.!T9-6;!~~"025'7 (860) 442.:0573,

-Mr)omr b~ugl'ierty Sife Veice President

.Dowiri.fon N.uifeaj,G!i.iuiectfo\it Mi.llsfone Station:

Jtop¢ Fetiy,.Road WaJerforii, er*oGsss,

'fh1$* iett¢f1~ to i;:iiil:f!rin that ship emei;gencyabthe.MllJsfonePow*:

.!'.(esidi:iilt cc;* .D~.vicl A.., -S)llith; Ei:µ~tgetj~yff!:Pa~¢cine~s Plapn,:i~g:$erv'ilies p;parµnen~ Millstone FIRE&..SAFETY ElllJIPMENT WWliV.SJi[pma(i~;~Oj'n; EmaU:Jnfp@~tilpmar,s.com*

.FAX"(860) 444'7395 B-8 Millstone Station Emergency Plan Revision 56 March 2018

AppendixB STATE OF CONNECTICUT DEPARTMENT OF EMERGENCY SERVICES & PUBLIC PROTECTION OFACE OF THE COMMISSIONER November 14, 2014 Stephen E. Scace, Site Vice President Dominion Nuclear Connecticut Millstone Station Rope Ferry Road, RT 156 Waterford, CT 06385

Dear Mr. Scace:

  • This letter is to confirm that personnel and equipment from the Department of Emergency Services and Public Protection will, when requested, respond in the event of an emergency at the Millstone Power Station.

This response is submitted in accordance with the State of Connecticut Radiological Emergency Response Plan.

Sincerely,

\-x-~ 5 __,A/\J'-A,O

~ B . Schriro

  • COMMISSIONER cc: William P. Shea, Deputy Commissioner Col. Brian Meraviglia, Deputy Commissioner 1111 Country Club Road Middletown, CT 06457 Phone: (860) 685-8000 I Fax: (860) 685-8354

.'A.n :Affirmative J'lction/:Equa.C Oyyortuni.ty :Emyf.oyer '

B-9 Millstone Station Emergency Plan Revision 56 March 2018

AppendixB

  • November 13, 2017 4~TELEDYNE

.'-"111 *aROW.N ENGINEERING Ev.$.rywJ:i~r$yoilltiOk" 2508 Quality Lane Knoxville, TN 37931 Mr. John Daugherty Site Vice President Dc;,minion Energy Nuclear Conn.ecticut Rope Ferry Road Waterford, CT 06385.

Reference:

Emergency Services Letter of Agreement

Dear Mr. Daugherty,

This Jetter serves as our "Letter of Agreement" to provide assistance in the event of an emergency._

We hi!ve l6 gammi! detectors and 40 grqss a:lpha/be1;a proportional counters which are used for gross alpha and beta, 1-131,. and Sr-89 and Sr-90 counting. During an emergency we could dedicate a large portion of these detectors to provide fast turn-around analysis. Table 1 lists the types of analyses and the number of analyses that c~n l:!e performed on a one-day, two-day, or three-day basis. Also listed are the types of sample media and detection sensitivities. Table 2 lists typical sampi1;i vol.umes required for analysis.

The following is a list of phone numbers for contacting us in case of an emergency. The numbers should be called in the order listed:

Teledyne: Brown Engineering (865} 690-6819 Keith Jeter {865) 934-0373 (865) 621-9118 {cell)

Marty Webb (865) 934-0375 (.865) 776-0573 (cell)

Rebecca Charles (865)934-0379 (865) 924-6041 {cell)

The .agreement letter ~hall remain In effect until cancellation by either party, provided by a ninety t90}

, day pribrwriiten 11otic;e, 11ndshiill be reviewed am:f certjfied~sneeded, If you need additional. information, you may contact me at the above number.

~*~

Keith J e t : ; ~

laboratory Manager Enclosure

AppendixB

  • Emergency Analytical. Services Table 1

~- ...

Analysis Matrix Days Detection Level Quc!ntity for Analysis Gamma Scan 1-131 charcoal, 1 .04pCi/CmM 20 Milk, Water, 5 pCi/L (Cs-137}

Other ...

.os pCi/g ;(Cs-137}

Tritium Water i 200 pCi/L 30 1-131 Water, Milk 3 1.0pCi/L 20 Vegetation 3 .OSpCi/L Gross Beta Air .Particulate::;. 1 .01 pCi/Cu.M 80 Totaf Strontium Milk,W<1ter 2 1.0 pCi/L 20

  • Based .on volume of 200 Cubic Meter:s
  • Analysis Gamma Table2 Medium Water or Miik Volume 4 liters

.sou SOD grams Vegetation SOD grams Tritiurn Water 100ml 1-131 Milk 4 liters Vegetation SOOgrams Gross beta Air partfculate As sampled Water 1 Liter Soil 50grams Total Stronti'um Water or Milk 1 liter

AppendixB

'\¥aterford Ambulance Se:rvice, Incorporated August 5, 2015 Mr. John Dougherty Millstone Power Station Dominion Nuclear Connecticut Rope Ferry Road Waterford CT 06385 Dear Mr. Daugherty This letter of agreement is to confirm that the Waterford Ambulance Service will, when called upon, respond in the event of emergencies at the Millstone Power Station complex in the following areas.

Implementation Criteria/Authorities. Responsibilities It is our understanding that, in the event of an emergency, the Millstone Shift Manager/Director of Station Emergency Operations or designee will request ambulance services to assist in the emergency operations. Assistance should be requested by calling the Waterford Emergency Communications Center (911), or by other means provided.

Measures to be Provided/Limit of Action, Responsibilities Our commitment is to provide emergency medical services to personnel who might be injured or become ill at the Millstone Power Station Complex. In the event of a large scale incident or hostile action based event, we will coordinate with Waterford Fire Service and with the Waterford Police Department in accordance with standard operating guidelines and within the Incident Command System.

Information Exchange/Points of Contact Verification of communication to the site may be by telephone to the Control Room or emergency operations facility.

Training and Drills We would appreciate and welcome notification of the plant drills or additional training which you feel would be advantageous to us.

Please do not hesitate to contact me should you have any question or concerns Sincerely, Ste.ueu 1). tfa,wia President, Waterford Ambulance Service Copies distributed David Smith, Manager, Millstone Emergency Preparedness Department Daniel Steward, First Selectman, Town of Waterford Lt. Stephan Bellas, Waterford Police Department/ Emergency Management Director 204 Boston Post Road, P.O. Box 137, Waterford Connecticut 06385

AppendixB

  • FIFIBl!NROPl!FERR\'ROAD WATl!IU-'ORD, CT 06385-:1886 August 6, 2015 Mr. John Dougherty Millstone Power Station - Dominion Nuclear Connecticut Rope Feny Road Waterford CT 06385 Dear Mr. Daugherty This letter is to confmn that personnel and equipment for the Waterford Fire Service will, when requested, respond in the event of an emergency at Millstone Power Station.

Implementation Criteria/Authorities. Responsibilities It is ourunderstanding that, in the event ofan emergency, the Millstone Shift Manager/Director of Station Emergency Operations/ designee may request personnel and equipment to handle the emergency. Assistance should be requested by calling the Waterford Emergency Communications Center (911 ), or by other means that may be provided.

Measures to be Provided/Limits of Actions Our commitment for assistance is to respond to the best of our ability with persmmel and equipment in the event of a fire emergency or a rescue at Millstone Power Station Complex and attempt to control the situation with the resources that may be available. We will request the assistance ofregional and state assets as needed. In the event of a large scale incident or hostile action based event, we will coordinate establishment of Incident Conm1and with the Waterford Police Department, regional, state and federal assets.

Information Exchange/Points of Contact Verification of communication to the nuclear facility will be by telephone to the Control Room or Director of Station Emergency Operations/Designee.

Training and Drills We would appreciate advanced notification of the plant drills or additional training which you feel would be advantageous to us. This notification should also include any additional security requirements that are being implemented at the Millstone nuclear facility.

This letter of agreement shall remain in effect until cancellation by either party, provided on 90 days prior to written notice, and shall be reviewed and certified as needed.

Sincerely,

~

Bruce A. Miller Director of Fire Services cc: David Smith, Manager, Millstone Emergency Preparedness Department Daniel Steward, First Selectman, Town of Waterford Lt. Stephan Bellos, Waterford Police Department/ Emergency Management Director President Steven Garvin, Waterford Ambulance Service

AppendixB

  • WATERFORD POLICE DEPARTMENT 41 AVERY LANE WATERFORD, CT 06385-2819 Brett Mahoney (860) 442-9451 TEL Chief of Police bmahoney@waterfordct.org September 14, 2015 Mr. John Dougherty Dominion Nuclear CT, Millstone Power Station P. 0. Box 12.8 Waterford, CT 06385

Dear Mr. Dougherty:

This Jetter is to confirm that personnel from the Waterford Police Department shall serve as the primaiy Jaw enforcement.age11cy which, when requested, will re*spond to the Millstone Power Station.

In the event of an emergency, the Millstone Shift Manager/Director of Statioi1 Emergency Operations/

desiguee may request personnel and equipment fI:om the Waterford Police Department by utiliz.lngthe established hot lines within the Wate1ford Emergency Communication Center. calling the Waterford Emergency Communications Center (9 I I), or by other means that may be prov.ided.

The Waterford Police Department's commitment for assistance to provide personnel and equipment may include, but not be limited to, traffic control, secµrity and/or tactical assistance. When assistance is requested, infonnation wilf be verified by the Waterford Police Department utilizing a call back verification method, which shall be conducted by the ranking Executive Officer on du.ty. In addition, for an event S\1ch as a hostile action based event the*Waterford Police Department may establish incident comniand, request regional,.state and federal assistance and be.the initial staging area for incidents involving outs_ide law enforcell)ent agencies.

The Waterford Police Department shall be notified of all notewmthy plant drills or additional training that would be advantageous to law enforcement.

This response is in accordance with criteria as set forth in the Federal Regulations, IO CFR, Part 73.55, "Requirements for Physical Protection of Licensee Activities in Nuclear Power Reactors Against Radiological Sabotage" and 10 CFR, Part 37, "Physical Protection of Category I and Categmy 2 Quantities of Radioacth1e Material."

~ Brett Mahoney Chief of Police cc: David Smith, Manager, Mi!Jstone Emergency Preparedness Department Daniel Steward, First Selectman, Town of Waterford Lt. Stephen Bellos, Waterford Police Department/ Emergency Management Director

  • wv,w;waterfordpolice.org

AppendixB

  • AccuWeather EIIITERPRISE'SOLUTIONS'"

Mr;Jci~O<!l!gherly 11/27./17

$iteYice presiµen~

Mill~one.Pow~rS.tat;ion J\1r. i;iaugherty, Per our (mgqing dfocuss1on.andyom: not$catjo11, AccuWeather-wiU b.e ;ivailali\e:fortelephpne cop.s_li)):atfoni4'!iours a day 7. daysperweek.

_/\ccuweatheti:-1eteorologi$wiil.be m.ade. a,v;3jlable dur\'1g, IH~iderrts, D.rills and Alerl:s to ,pjscuss tile w_eatper.s potential)IJ!p*a~.to the Millstone Power~tation, . . . . . .

1'1ni; senrice wi!Ifodude {heJmpact 1)01:entfai fronr all~weathetevents*potentiai!y afl\ctirtgtq¢physical )m;;:ition.

Adilitiortally AccuWeatheI' will :participate in the. periodic*weather forecast simtilations with the.Millstone Power.Staff.

The fee:j}et.consultation .request is $495.00 per 24-hotir period. We locikfurward to.continuing to support the Millstone PowerStatioil. . . .. .. . ...

  • Regar:ds, Lou.

Louis $Seidel Directbt BusinessDe,re]opment AcctiWeather Enterprise solutions 814.235 !:36Q8.

I,0uSeid~l@AccuWeather,cbm 38$ Sciericef>arJ,Road, St;,te;C9!.lege,PA.16llo;3-2215* ?8,J/1.237!0309' F S14;238:1339 E safes@ao:cuweathetcom* fos;.tu\/:iJ~athir~C.Om!EmE}1"f~ris~S6lutionr;

AppendixB

  • f©]! ILaboratories1Lc a member of Tti? 111:rnroupwc ?O,Box)rril2 G~arlcslon. SC 294lt QO\\ll :Sa,agfi Roa~ Clprl~sjon-, Sc 29~07

.l.' *M:..s~ton1

.F .8{3,765.1 178 g.eLcl:iiii Mr; John Daugherty Vice President Millstone Pow~ Station Pominjon N1,1cl~m- (pnnecticut 1'013oxl28 Waterford, CT -06385 Re: Einetgencr Pl$

GELLaboratori¢s, LLG (GEL) fa prov.i:~rtg. thl:{1eti;er to DominiQn as a eonm;utmeprto prqv.j_d,e emergency respcmse rad.i0,chemical amµysis of-environrnental.smnpk$ to -assist your organization in the event of ail.

emer_gency:situation or,emergency drill.

  • Please.n'Qte tm;!t in the event of an emergency, Dom.inion wHI be re$I)01llli.lJle.ifor J:he:s.ample :an11ly.~i; cos.ts as we:J.J, as the sample.disposal costs; Prices for wquested ,analysis will 'be -established at the time-services are requested, ;andiinai.ySJ.s wiii *be:ibased Oil GBV s Standard Operating Procedilres, GEL"s.sttfridard: tenn:s :and eondi.tio~,which ~e enc;:Ios.e4; viiU ?.PP1Yto1h~
analysis as wel1'.

Sh~tr1d;y6u have. any questions -0fneed iidditl:o11al irifofuiii.tion, please calf me at 843~S56-8l 7l, Yours vexy truly. .

~*:: . . .

Anna K 'W}iit¢ Contract Manager protil~m sD\v,ep.

AppendixB

  • City of Norwich Fire Depl 10 North Thames &tre@l Kenneth J. &ruidariato fire L'hi1;f .

Norwich; .Conneaticul 06360 (860). 892,6080 f:ax {860) g8.6-'Z5'55 Oc.tobet l l, 201.7 John, Daugherty

  • Site Vice President Mrllstone Po.wer Station
  • .Dominion Nuclear CT
  • Rope Ferry Rd.

Waterford, CT '06385 D¢ar ~- Da1,1gherty:

This leitedsto confirm thatthe'Nornith Fire D~partinentwill, to the best of its ability

.dtitinga:statione1t1etgen:cy., fill breathing bottle!-lbroughtto; the N:orvdch Fire Department by ];)om.inion Nu:clearConnectjcut upon teh:phoneteqilest by its Emergency Rysponse Qpe@tions, *

  • The Emergency P.ianning Services Depimment at .Millstone Station is responsible for any questionspertaining to this agreement {Contact: Tom Dembek at 860-440-4223)

This.agreement shall r.emain.).n .effect until revised, as agreed upon by both parties, or canC'¢lled by either party wtth 90 days written notice.

sm;ere/~ * ~tf()

~ rJ _

k~~

~enne.tJ;lJ. . c .dar.iato, EFO CfEl Frre Chief ,, *

  • KJSjjs* *

. .cc:, Dav,idA. Smith, Ma:nagef Emergeni:y Prepaiedjicss .Dept; Millstone

  • B-16 Millstone Station Emergency Plan Revision 56 March2018 L _ _ __ _

AppendixB

  • SALEM:VQLUN:TEER FJRE COMJ>AN\7, INC.

424 Harif.ord Road Sd/,e"1:! Connecticut-06420 (860) 855/-,()942 fax (a60Jas9::.2961

""1'>>'.salenz.f"1reco.coni October 9; '2017 Mr. Nlm :Omigherty Vice President & Sr; .Nuclear :f;xecutive D9minion Energy Nucle;a;rConnecticµt; Inc.

P.O. Box 128 Waterford, CT :063&5 Dea,r ~; Dl!-ugherty :

This letter is to confirm thatthe Town of saiem l!-lld the Salem Volunteer Fire Department wili, to the* best of its ability; durip,g a, ~11!-tiort .ewerge11-cy, fill breathmg bottles bro"(lght to the Salem Volunteer Fh Station by Dominio11 Energy N:ui;:lear Connecticut, Inc. upon telephone request by its Emergency Response Operations.

The *Emergency *Preparedness. Department at Millstone *Station is responsible for any questions pertaining to this agreement.

This agreement shall remain 'in effect U11ti1 revised, a,s agree41,1pon by both parties, or cancelle.d by either party with 90. days written notice, Sincerely, *

  • Eugene R. Maiorano Fire Chief S1J.lem Vqli.mteerFire Department cc: bavid Smith, Emergenc)'Pr:epar:edness Depilrtment; :ly.[illstone

Appendix C APPENDIXC MAPS OF PLUME EXPOSURE AND INGESTION EXPOSURE EPZ, LOCATIONS OF ON-SITE AND OFF-SITE RADIOLOGICAL MONITORING STATIONS, STATION EVACUATION ROUTES

EMERGENCY :PLANNING ZONE

'EVACUATION, ROUTE$ 0

~

....~

watetfO!dto ~~tHl!rtt't!nl:

Afe,WNoitlilorte.&Z\'l'ellt lndi>.11lbl1t1ii11!!.2W!!s!

10,eJ<itSA:lMalnSt.) ;l'tili,lttat f r

nghton!l;8rewerstto * .

in!eme,,;liogwif!tl'"F!>"S:~

l,,Jt9nto:~Slfo.Eas\:

Harl!oriJ1:ii9ii$dlo<JI, QldColeh~Roadti>*Rte*.

35<Uti Rte,. !!West toeidt5A Groto11 c'rty: & Groton

@ainSQ. 'lJietiSi!melll!: TOW'il:toNol'Wlch:

~to.Eastl:fad!O!dliS. 'Rte. 12tlcrllth$.i?AWesno On: J,39$.1!1'11> l:ldt 1~t 1'e}.

l-39;;Noll!ttorta2:We.stt.>. 'Take ite,~lo-169:N El4tSAlf,1nlllSlPhei1!18ll)a 'Rd.):Rlgltl.o:m Oit:fflll:Rll.

as. all<lv!lf<>Ellit~ HS; :liefo1t>Mafuin'Drivelnto /.lol?ifdi Teclln~Higll.Stlll>Ot. '

.'OR, 1-,95 Si\>!o Rf..!! N¢hto Ol't l-9tt'lortll lo E,o't$1W rue. 349.NC!lh(CllSl)IJrJ)!iWYl (ile.-a Noiliit t~e.ecitl!5; !6,t,:95,Jli1oiiei 1ftl.o11lr(o **

<<os!)Ovet'P.1!1ti~llntige .rti,,. 2Wetltolli>.-18!HllQnli'

  • tom,;2westtoEidtSII. .  :(Harlahil Rd;J. *rog1ito11:oic N 0

n (MainSt) Therlsaineas. Hi!lRli *l\imrigl!tl;lef~

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iibaiilt'to E<1$1tlaill<inHlS. MahiiltDrliielnlei NclWicb

'l&clinii:ill titghS<ll!,ilil. =

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Figure C-2 Locations of On-Site and Off-Site Radiological Monitoring Stations (As specified by the Radiological Effluent Monitoring and Off-Site Dose Calculation Manual)

Figure C-3 Map of Millstone 10 Mile Emergency Planning Zone Distance Zone i Community (0-2mi) A Waterford(A-1)

East Lyme (A-2)

(2-5 mi) B East Lyme (B-1)

Waterford (B-2)

New London (B-3)

(5-IOmi) C EastLyme(C-1)

Montville (C-2)

. . . . . . . . . . . . . . . . . . . . . . !. . . . . . . . . . . . . . .;. Waterford.(C-3)........................................................

! D IOld Lyme (D-1)

I i Lyme (D-2)

. . . . . . . . . . . . . . . . . . . . . . !. . . . . . ~. . . . . . !.

1

~:~~C:dc~~ ~.Town.. CE-2) ....................

I F I Fishers Island

! N/A IPlum Island

Figure C-4

  • Map Of Millstone SO-Mile Emergency Planning Zones I Connecticut

'\j'

  • )Hattl<wd I

r L-~~

10-Mile E merg~ncy Planning Zone\

t\BLOCK ISL",,ND 50-Mile Ingestion Pathway Planning Zone

  • C-5 Millstone Station Emergency Plan Revision 56 March 2018 L ___ -- - --- -

Figure C-5 Map of Millstone Station Evacuation Routes ALTERNATE ROUTE VIA ALTERNATE ROUTE VIA OLD MILLSTONE ROAD*

BALLFIELD ACCESS ROAD*

PRIMARY ACCESS ROUTE MILLSTONE ACCESS ROAD

  • May be used as a pedestrian route if security blocks are in ALTERNATE ROUTE VIA place.

OLD MILLSTONE ROAD*

C-6 Millstone Station Emergency Plan Revision 56 March 2018

AppendixD APPENDIXD SUPPORTING PROCEDURES LIST

AppendixD

MP-26-EPI-FAP01 CR Emergency Operations Emergency Plan Section(s) 5.1 MP-26-EPI-FAP02 TSC Activation and Operation 5.2, 5.3, 7.3 MP-26-EPI-FAP03 OSC Activation and Operation 5.2, .5.3, 7.4 MP-26-EPI-FAP04 EOF Activation and Operation 5.2, 5. 2.14, 5.2.16, 5.3, 7.2 MP-26-EPI-FAP05 State Emergency Operation Center (EOG) Activation and 5.2, 5.2.1.4, Operation 5.2.1.6, 5.3 MP-26-EPI-FAP06 Classification and PARs 4, 5.2.1, 6.2, 5.2.5 MP-26-EPI-FAP07 Notification and Communications 5.1, 6.1 MP-26-EPI-FAP08 Evacuation and Assembly 6.4.1 MP-26-EPI-FAP09 Radiation Exposure Control 6.4, 6.5 MP-26-EPI.-FAP10 Dose Assessment 6.2.1, 6.2.3 MP-26-EPI-FAP11 Core Damage Assessment 6.2.4 MP-26-EPI-FAP12 Thermal Hydraulic Evaluation 5.2.18, 5.3.13 MP-26-EPI-FAP14 Recovery 9.0 MP-26-EPI-FAP15 Common Forms N/A MP-26-EPI-FAP16 Innsbrook Corporate Support Center 5.4 MP-26-EPI-FAP18 Offsite Incident Command Post (ICP) Activation and Operation N/A Emergency Plan Administrative Procedures MP-26-EPA-FAP01 Management Program for Maintaining Emergency 7.0, 8.0 Preparedness MP-26-EPA-FAP05 Emergency Planning Facility Maintenance 7.0, 7.5 MP-26-EPA-FAP08 Public Alerting System Administration 8.2 MP-26-EPA-FAP09 Public Alerting System Test and Maintenance 8.2 MP-26-EPA-GDL05 Emergency Response Data System (ERDS) Change Process N/A MP-26-EPA-GDL06 OFIS 7.1, 7.2, 7.3 MP-26-EPA-REF01 Millstone Unit 1 Defueled Emergency Action Level (EAL) Basis N/A Document MP-26-EPA-REF02 Millstone Unit 2 Emergency Action Level (EAL) Basis N/A Document MP-26-EPA-REF03 Millstone Unit 3 Emergency Action Level (EAL) Basis N/A Document MP-26-EPA-REF04 Off-Site Programs 8.0 MP-26-EPA-REF08B Millstone Emergency Planning Resource Book 8.2.1

AppendixD Emergency Plan Procedure Number Section{s)

Fleet Procedures EP-AA-101 10 CFR 50.54(q) Change Evaluation NIA EP-AA-102 Revision and Control of Emergency Plan, Emergency Action NIA Levels (Technical Basis and Matrix), and Reference Manual EP-AA-103 Emergency Preparedness Performance Indicators NIA EP-AA-104 Emergency Preparedness Steering Committee NIA EP-AA-105 Emergency Preparedness Department Staff Training NIA EP-AA-303 Equipment Important to Emergency Response Various EP-AA-400 Drill and Exercise Program 8.2 EP-AA-505 B.5.b Program NIA EP-AA-600 Emergency Plan Offsite Interfaces NIA EP-AA-601 Emergency Press Releases NIA EP-AA-3001 Cyclic and Prompted Emergency Preparedness Tasks 8.0 Nuclear Training Procedures TR-AA-TPG-2300 Millstone Fire Protection Program, Training Program Guide 8.1.3.b.

TR-AA-TPG-2400 Emergency Plan Training Program Guide 8.1.1 Radiation Protection/Radiation Monitoring RP-AA-163 Inspection and Inventory of Respiratory Protection Equipment Various REMP Section 2.1 Sample Identification and Transmittal to the Contractor 6.2.4 Analyses REMP Section 2.6 Terrestrial Biota Sampling 6.2.4 REMP Section 2.4 Soil Sampling 6.2.4 REMP Section 2.7 Terrestrial Water Sampling 6.2.4 RPM Section 4.8.5 Emergency Radiological Equipment Maintenance and Various Inspection REMODCM Radiological Effluent Monitoring and Off-Site Dose Calculation Figure C-2, Manual Appendix H Table H-2

AppendixD Emergency Plan Procedure Number Section(s)

Millstone Unit-2 Severe Accident Management Guidelines (SAMG)

SAMG 4211 Phase 1 Initial Diagnosis 5.2.2, 5.1.3, 5.3.12 SAMG 4212 Phase 2 Verification of Diagnosis 5.2.2, 5.1.3, 5.3.12 SAMG 4213 Phase 3 CHLA Implementation 5.2.2, 5.1.3, 5.3.12 SAMG 4214 Phase 4 Restorative Actions 5.2.2, 5.1.3, 5.3.12 SAMG 4215 Calculational Aids 5.2.2, 5.1.3, 5.3.12 EDMG 2.01 MP2 B.5.b Event Initial Response 5.2.2, 5.1.3, 5.3.12 EDMG 2.02 MP2 B.5.b Event TSC Response 5.2.2, 5.1.3, 5.3.12 Millstone Unit-3 Severe Accident Management Guidelines (SAMG)

SACRG-1 Severe Accident CR Guideline Initial Response 5.2.2, 5.1.3, 5.3.12

  • SACRG-2 SACRG-3 SAG-1 Severe Accident CR Guideline for Transients after TSC is Activated Severe Accident CR Guideline for MP3 8.5.B Initial Event

Response

Injection into the Steam Generators 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.3, 5.3.12 SAG-2 Depressurize the RCS 5.2.3, 5.3.12 SAG-3 Inject into RCS 5.2.3, 5.3.12 SAG-4 Inject into Containment 5.2.3, 5.3.12 SAG-5 Reduce Fission Product Releases 5.2.3, 5.3.12 SAG-6 Control Containment Conditions 5.2.3, 5.3.12 SAG-7 Reduce Containment Hydrogen 5.2.3, 5.3.12 SAG-8 Flood Containment 5.2.3, 5.3.12 SAG-9 Severe Accident CR Guideline for MP3 8.5.B TSC Event 5.2.3, 5.3.12

Response

SCG-1 Mitigate Fission Product Release 5.2.3, 5.3.12 SCG-2 Depressurize Containment 5.2.3, 5.3.12 SCG-3 Control Hydrogen Flammability 5.2.3, 5.3.12 SCG-4 Control Containment Vacuum 5.2.3, 5.3.12 SAEG-1 TSC Long Term Monitoring 5.2.3, 5.3.12 SAEG-2 SAMG Termination 5.2.3, 5.3.12 D-4 Millstone Station Emergency Plan Revision 56 March2018

AppendixD Emergency Plan Procedure Number Title Section{s)

CA-1 RCS Injection to Recover Core 5.2.3, 5.3.12 CA-2 Injection Rate for Long-Term Decay Heat Removal 5.2.3, 5.3.12 CA-3 Hydrogen Flammability in Containment 5.2.3, 5.3.12 CA-4 Volumetric Release Rate from Vent 5.2.3, 5.3.12 CA-5 Containment Water Level and Volume 5.2.3, 5.3.12 CA-6 RWST Gravity Drain 5.2.3, 5.3.12 CA-7 Hydrogen Impact when Depressurizing Containment 5.2.3, 5.3.12 DFC TSC Diagnostic Flow Chart 5.2.3, 5.3.12 SCST Severe Challenge Status Tree 5.2.3, 5.3.12 Common Operating Procedures COP 200.2 Response to Security Events 6.4.1 COP 200.2AIR Airborne Threat 6.4.1 COP 200.3 Response to Medical Emergencies 6.5.4, 6.5.5 CSP 600.1 Paging Evacuation Alarm System Operability Test 8.2.1 CSP 600.2 Communications-ENRS/ARCOS and Callback Monthly 8.2.1 Operability Test

  • CSP 600.3 CSP 600.4 CSP 600.20 State Police and Waterford Police Radio Systems Operability Test Communication- Radiopaging and ENRS/ARCOS Practice Test Communications-Emergency Response Data System EROS Quarterly Operability Test 8.2.1 8.2.1 8.2.1 Chemistry Department Procedures CP 3804K PASS RCS/RSS Sample (Unit 3) N/A CP 3804AC Liquid Waste Sample Sink (Unit 3) N/A CP 3804L PASS Containment Air Sample (Unit 3) N/A CP 3804M PASS Ventilation Samples (Unit 3) N/A CP 2804L Unit 2 Reactor Coolant and Liquid Waste PASS N/A CP 2804M Unit 2 Vent and Containment Air PASS N/A

AppendixE APPENDIXE MILLSTONE EMERGENCY EQUIPMENT

AppendixE FigureE-1 Millstone Emergency Equipment Summary<6>

Emergency Item Control TSC/ NAP/ Ambulance EOF RMT RMT Room osc SAP Kit Kit 1

Kit' Radiological Monitoring Equipment:

RM-14 Frisker (or equivalent) U3 X X X R0-2A Survey Meter (or equivalent) X X X X ASP-1 / HP-270 (or equivalent) X X X Teletector (or equivalent) X X X Air Sampler- 11 O vac X X xm Air Sampler- 12 vdc X xm X Area Radiation Monitor X X L-2241-2/HP-21 O (or equivalent) U2 X X X Cont. Air Monitor (AMS-3 or equiv.) X Portal Monitor (4) X Iodine Sampling Materials (5) X X X X X On-Site RMT Kit (locations) X X X X (5) (5)

Off-Site RMT Kit (locations) x(2J (5) (5)

Emergency Dosimetry X X (5) X X X X 3

Protective Equipment / Materials  :

Respirators X X X X (5) (5)

SCBA X X Fire Fae Protective Clothing X X X X X Personnel Decontamination Material X X X Facility Rad Control / Decon Material X X Potassium Iodide Tablets U2,U3 X X X X X 3

Communications Equipment  :

Dedicated Telephone Lines U2,U3 X X Emergency Radios X X X Satellite Phones U2,U3 X X 3

Emergency Supplies / Materials  :

Emergency Preparedness Procedures X X X X X X x(2)

RMT Vehicles Tools, Lights, Office Supplies (3) X X (1) On-Site RMT Kit (2) Off-Site RMT Kit (3) Additional tools and equipment can be obtained from tool cribs located in U2/U3. ERF items maintained in accordance with EP procedures.

(4) Permanently installed at this location.

(5) RMT kit resupply equipment is stored at this location.

(6) HP materials and equipment are maintained and surveilled in accordance with the site Radiation Protection Manual. Detailed inventory of other equipment is provided in MP-26-EPA-FAPOS, EP Facility Maintenance.)

(7) 11 Ov - RMT1 (U2,3 CR) TSC/OSC 12v - NAP/SAP over water

AppendixF APPENDIXF DIAGRAMS AND ARRANGEMENT OF EMERGENCY FACILITIES

Figure F-1

  • HVAC Equipment Room Not to Scale- Typical Layout

FigureF-2

  • Diagram of Emergency Operations Facility Boiler Meth1mltal RL NRC RMT Switchgear Garage Dose EQC Assessment Copy

.Area RMTBtorage.

UPS Computer R6d Ro.om Men \A/9men Bre.iK Mµster Alternate Area Area T';,C/bSC

  • Ent.ranc:e

FigureF-3

  • Diagram of OSC Assembly Area Layout Building 475 Walkway Walkway Cafeteria Office Areas Kitchen Area OSC Assembly Area-Conference Room-102 Drawing not to scale*

AppendixG APPENDIXG CROSS-REFERENCE TO NUREG-0654 CRITERIA

Appendix G

  • Planning Standard Summary of Planning Standard A. ASSIGNMENT OF RESPONSIBILITY (ORGANIZATION CONTROL)

A.1.a Identify State, Local, Federal and private organizations who are Plan Cross Reference (Section or Item) 1.1, 1.2, Table 1-1, part of emergency plans. Figure 1-1 , Appendix B, Table 2-1 A.1.b Each organization shall specify its concept of operations and Sections 1, 5, 6, 9 relationship to total effort.

A.1.c Illustrate relationships by block diagram. Figures 1-2, 5-1, 7-1 a, b,c A.1.d Title of individual in charge of emergency operations. 5.2.1, Figure 5-1 A.1.e Provide for 24 hr./day emergency response and manning of Section 5.0 communications.

A.2.a Specify functions and responsibilities for major elements and key NIA- State and Local individuals by title. requirement only.

A.2.b Each plan shall contain the legal basis for such authorities. NIA- State and Local requirement only.

A.3 Include written letters of agreement. Include concept of 5.4.1, 5.4.2, Appendix B operations, emergency measures to be provided, criteria for implementation and exchange of information.

A.4 Title of individual responsible for assuring continuity of resources. 5.2.17, 5.4.3 B. ON-SITE EMERGENCY ORGANIZATION B.1 .Relationship between on-site emergency organization and normal Table 5-1 staff.

B.2 Specify title of emergency coordinator who is on-site 24-hr./day. 5.1.1, Table 5-1 B.3 Line of succession for emergency coordinator. Specify conditions 5.1.1, 5.2.1, 5.2.5 for high level officials assuming this function.

B.4 Specify functional responsibilities of emergency coordinator. 5.1.1, 5.2.1 Specify responsibilities which cannot be delegated (e.g., may not delegate the decision to notify and to recommend protective actions to authorities).

B.5 Specify title and corresponding qualifications of emergency Table 5-1 personnel. Include Table B-1, "Minimum Staffing Requirements for Nuclear Power Plant Emergencies." Specify minimum on shift and available within 30 minutes and 60 minutes following declaration of emergency.

8.6 Specify interfaces between on-site and off-site organizations. 1.2, Figures 1-1, 1-2, 1-Illustrate in block diagram. 3, 5-1 B.7 Specify corporate organization. Provide a table similar to B-1. 5.0, Table 5-1, Figure 5-1 B.7a Logistics support for emergency personnel 5.2.17 B.7b Technical support for planning, reentry, recovery Section 9 B.7c Management interface with government authorities 6.1, Figures 7-1a, c B.7d Release of information to news media 5.2.14, 5.2.16

AppendixG

  • Planning Standard B.8 B.9 Summary of Planning Standard Specify private organizations and contractors who would provide assistance.

Specify services to be provided by local agencies. Include transportation and treatment of injured personnel who may be Plan Cross Reference 5.4 (Section or Item) 6.3.1, 6.4.1.b, 6.5.5, 6.5.6 contaminated.

B.9 Append letters of agreement with contractor, local, and private 7.10, Appendix B agencies which include authorities, responsibilities, and limits of actions.

C. EMERGENCY RESPONSE SUPPORT AND RESOURCES C.1 Make arrangements with DOE for FRMAP/RAP assistance. 1.2, 1.4 C.1.a Specify persons by title authorized to request federal assistance. 1.4, 5.4.3 C.1.b Specify federal resources expected, including expected times of 1.4, 5.4.3 arrival at specific nuclear facility sites.

C.1.c Specify resources available to support the federal response. 1.4, 5.4.3 C.2.b Licensee may dispatch a representative to principal off-site 5.2.15, 5.2.16 governmental EOCs.

C.3 Identify radiological laboratories, capabilities, and expected 7.10, Table H-2, availability. Appendix B, Table H-1 C.4 Identify facilities, organizations, and individuals which can be Table H-2, Appendix B relied upon in an emergency D. EMERGENCY CLASSIFICATION SYSTEM D.1 Establish EAL scheme per Appendix 1. Section 4, Table 4-1, 4-2, 4-3 4-4, Appendix I D.2 Initiating conditions shall include the example conditions in Section 4, Table 4-1, 4-Appendix 1 and accidents in the FSAR. 2, 4-3 4-4, Appendix I E. NOTIFICATION METHODS AND PROCEDURES E.1 Establish procedures for notification of response organizations 1.3, 6.1 consistent with Appendix 1. Provide verification of messages.

E.2 Establish procedures for notifying, alerting, and mobilizing 6.1 emergency response personnel.

E.3 Initial emergency message shall include: class of emergency, 6.1 whether a release is taking place, potentially affected areas, whether protective measures may be necessary.

E.4 Provide for follow-up messages. Includes the 14 listed items. 1.3, 6.1, 6.2.1, 6.2.2 E.6 Establish administrative and physical means and the time 1.5, 6.1 required to notify public in plume EPZ per Appendix 3. Licensee will ensure means exist. Responsibility of State and Local governments to activate the system.

E.7 Provide written messages intended for the public, consistent with 1.3, 1.5, 6.2.2, 7.7, 8.4 the operator's classification. Role of the licensee is to provide supporting information for the messages .

_J

Appendix G

  • Planning Standard F. EMERGENCY COMMUNICATIONS F.1 Summary of Planning Standard Identify organizational titles and alternates for communications links. Establish primary and backup communications.

Plan Cross Reference (Section or Item}

1.3, 6.1, Figures 7-1 a, b, c, 7.9, Appendix B F.1.a Provide 24-hr./day notification and activation and 24-hr./day 5.1.4, 6.1 manning of communications links.

F.1.b Provide communications with contiguous State/Locals within the 6.1, Figure7-1a Emergency Planning Zones.

F.1.c Provide communications with Federal Emergency Response Figure 7-1b, 7-1c Organizations.

F.1.d Provide communications between State and Local centers, and 1.3, 6.1, 7.2.5, Figure 7-field assessment teams. 1a, 7-1c F.1.e Provide for alerting and activating emergency personnel. 6.1 F.1.f Provide communications to NRG Headquarters, NRG Regional Figure 7-1b, 7-1c Office EOG, EOF, and RMT assembly area.

F.2 Ensure that coordinated communication links for fixed and mobile 7.9 medical support facilities exists.

F.3 Periodic testing of communications systems. 8.2.1, 8.2.1.b, 8.2.2 G. PUBLIC INFORMATION G.1 Provide periodic information at least annually to public concerning 1.6, 8.4, 8.5 public notification and protective actions in an emergency including the special needs of the handicapped .

G.2 Information must reach population within plume EPZ and should 1.6, 8.4 include written material that would likely be available in an emergency. Updated information should be disseminated annually. Notices to refer the transient populations to the sources of local information.

G.3.a Provide point of contact and physical location for use by news 7.7 media.

G.3.b Provide space for a limited number of news media at EOF. 7.7 G.4.a Designate a spokesperson. 5.2.15 G.4.b Arrange for timely exchange of information among spokesperson. Figure 1-1 , 5.2.14, 5.2.15, 5.2.16, 6.1, 6.6 G.4.c Coordinate arrangements for dealing with rumors. 5.2.14 G.5 Conduct informational programs for news media at least annually. 8.5 H. EMERGENCY FACILITIES AND EQUIPMENT H.1 Establish TSG and OSG per NUREG-0696 7.3, 7.4, Appendix E, F H.2 Establish EOF per NUREG-0696 7.2, Appendix E, F H.4 Provide fpr activating and staffing facilities in a timely manner. Section 5, Table 5-1, 6.1 H.5 Provide on-site monitoring systems to be used to initiate Table H-1 emergency measures per Appendix 1, including:

H.5.a Geophysical Table H-1

AppendixG

  • Planning Standard H.5.b H.5.c Radiological Process Summary of Planning Standard Plan Cross Reference (Section or Item) 6.2.3, Table H-1, Figure C-2 Table H-1 H.5.d Fire Table H-1 H.6 Provide off-site monitoring equipment including:

H.6.a Geophysical Table H-2 H.6.b Radiological Figures C-2, Table H-2 H.6.c Laboratory facilities 7.10, Table H-1, H-2 H.7 Provide off-site radiological monitoring equipment. Appendix E, Table H-2 H.8 Provide meteorological instrumentation and procedures per 7.13, Table H-1, H-2 Appendix 2. Obtain meteorological information from other sources.

H.9 Provide on-site Operational Support Center (assembly area) with 7.4, Figures F-2, F-3 adequate capacity and supplies.

H.10 Provide for inspection, inventory and operational checking of 7.5, Appendix E, equipment at least once each calendar quarter and after each Appendix D use. Have sufficient reserves of equipment to replace that which was removed from emergency kits for calibration or repair.

Calibrate equipment per suppliers recommended intervals.

H.11 In appendix, provide inventory of emergency kits. Appendix E

  • H.12 1.1 Establish central point for receipt and analysis of field monitoring data (preferably associated with EOF) and coordination of sample media.

I. ACCIDENT ASSESSMENT Provide EALs and corresponding emergency class.

6.2.3, 7.10, Table H-1, H-2 Section 4, Tables 4-1, 4-2, 4-3, 4-4 and Appendix I 1.2 On-site capabilities to provide initial values and continuing N/A assessment (per NUREG-0578 and NRG letter of 10/30/79) including:

Cont'd Post-accident sampling capability Appendix D Cont'd Radiation and effluent monitors Table H-1 Cont'd In-plant iodine instrumentation Table H-1 Cont'd Containment radiation monitors Table H-1 1.3 Establish methods and techniques for determining: N/A 1.3.a Source term (e.g., relation of containment radiation monitors and 6.2.3, Appendix D material available for release.)

1.3.b Magnitude of release based on plant parameters and effluent 6.2.3, Appendix D monitors.

1.4 Establish relationship between effluent monitor readings and 6.2.3, Appendix D, exposures and contamination for meteorological conditions. 6.2.4.c

__J

f

(

AppendixG

  • Planning Standard 1.5 Summary of Planning Standard Acquire meteorological information per Appendix 2. Provide meteorological data to EOF, TSC, CR, and off-site NRG center.

Make available to the State suitable meteorological data processing interconnections.

Plan Cross Reference (Section or Item) 6.2.3, 6.2.4.d, 7.13 1.6 Determine release rate/projected doses if instruments are off- 6.2.3, 6.2.4 scale or inoperable.

1.7 Field monitoring within plume EPZ. 6.2.3, 6.2.4.h 1.8 Provide for rapid assessment of radiological hazards. For field 6.2.3, 6.2.4.h, teams include: activation, notification, composition, transportation Appendix D communication, monitoring equipment and deployment times.

1.9 Have capability to detect radio-iodine in air as low as 10-7 µCi/cc. 6.2.3, 6.2.4.h.4 1.10 Relate measured parameters to dose rates. Estimate integrated 6.2.3, 6.2.4.c, 6.2.4.e dose from dose rates and compare to PAGs.

J. PROTECTIVE RESPONSE J.1 Establish means and time to warn individuals in owner-controlled 6.4.1 areas.

J.2 Provide evacuation routes and transportation for on-site 6.4.1 individuals to off-site locations, including alternatives.

J.3 Provide radiological monitoring for people evacuated from the 6.4.1.i site.

J.4 Provide evacuation of on-site non-essential personnel in Site Area 6.4.1.d, 6.4.1.i or General Emergency. Provide decontamination capability near off-site location.

J.5 Account for all individuals on-site and ascertain names of missing 6.4.1.d, 6.4.1.h individuals within 30 minutes. Account for all individuals continuously thereafter. -

J.6 Provide for individuals remaining or arriving on-site, respiratory 6.4.3, 6.4.4, 5.2.2, 5.2.5 protection, protective clothing, radioprotective drugs.

J.7 Establish a mechanism for recommending protective actions to 1.3, 6.2.1, 6.2.2, 6.2.3, state/local authorities per EALs of Appendix 1 and Tables 2.1 and Figure 1-1, Table 4-4 2.2 of the EPA PAGs.

Cont'd Provide prompt notification to off-site authorities in plume EPZ as Section 4, Tables 4-1, specified in NUREG-0654, Appendix 1. 4-2, 4-3, 4-4, 6.1, Figures 7-1 a, b, c J.8 Time estimates for evacuation in plume EPZ in accordance with Appendix J Appendix 4.

J.10 Plans for protective measures to include:

J.10.a Maps Appendix C J.10.b Population distribution AppendixJ J.10.c Means for notifying population 1.5, 6.1 J.10.m Public protective strategies from plume exposure. 6.2.1

AppendixG

  • Planning Standard Summary of Planning Standard K. RADIOLOGICAL EXPOSURE CONTROL K.1 K.1.a Establish on-site exposure guidelines for:

Removal of injured persons Plan Cross Reference 6.5 (Section or Item)

K.1.b Corrective actions 6.5 K.1.c Assessment actions 6.5 K.1.d First aid 6.5 K.1.e Personnel decontamination 6.5 K.1.f Ambulance service 6.5 K.1.g Medical treatment 6.5 K.2 Provide on-site emergency radiation protection programs. Specify 5.1, 5.2.1, 5.2.2, 5.2.5, individual (s) who can authorize exposure in excess of 10CFR20 6.4, Table 6-1 limits.

Cont'd Provide procedures for volunteers to receive radiation exposures 5.1, 5.2.1, 6.4 in lifesaving activities.

K.3.a Provide 24-hr./day dose determination 6.4 K.3.b Maintain dose records and read dosimeters at appropriate 6.4 frequencies.

K.5.a Levels for decontamination 6.4 K.5.b Establish means for radiological decontamination of personnel, 6.4.3

  • K.6 K.6.a K.6.b supplies, equipment, and waste disposal.

Provide on-site contamination control, including:

Area access control Drinking water and food supplies 5.2.2, 5.2.4, 5.2.5, 6.4.1, 6.4.3 6.4.3.c K.6.c Criteria for permitting return of areas and items to normal use in 6.4.3 accordance with ANSI 13.12 K.7 Capability to decontaminate relocated on-site personnel, including 6.5.3 extra clothing and decontaminates (particularly for radio-iodine contamination).

L. MEDICAL AND PUBLIC HEALTH SUPPORT L.1 Describe hospital and medical services, including preparations to 6.5.4, 6.5.5, 6.5.6, handle contaminated individuals. Appendix B L.2 Provide on-site first-aid capability. 6.5.4, 7.11 L.4 Arrange for transporting patients of radiological accidents to 6.5.5 medical facilities .

__j

AppendixG

  • Planning Standard Summary of Planning Standard M. RECOVERY AND REENTRY PLANNING AND POST-ACCIDENT OPERATIONS M.1 Develop general plans and procedures for recovery and means by which decisions are made to relax protective actions.

Plan Cross R *

(Section or 11-~\

Section 9 II M.2 Specify position/title, authority, and responsibility for key positions Section 9, Figure 9-1 in the recovery organization. .

M.3 Means to inform personnel that recovery is to be initiated and Section 9 changes in organization.

  • M.4 Method of periodically estimating total population exposure. 6.2.3, 9.2.5 N. EXERCISES AND DRILLS N.1.a Conduct an exercise as set forth in NRG and FEMA rules. 8.2.2.f N.1.b Include mobilization of state and local resources. Provide for 8.2.2 critique by Federal and State evaluators N.2 Conduct drills, in addition to the annual exercise, at the 8.2 frequencies indicated.

N.2.a Communication drills (Quarterly), FEMA - IP State 8.2 N.2.b Fire drills - per technica.l specifications 8.2 N.2.c Medical drills - annually to include contaminated individual, 8.2 ambulance, and off-site medical help. (Off-site portions may be part of annual exercise).

N.2.d Radiological monitoring - annually (include collection and analysis 8.2 of sample media).

N.2.e Health Physics - semi-annually to include simulated elevated 8.2 environmental samples; analyze actual in-plant liquid samples with elevated radiation levels.

N.3 Describe the conduct of drills and exercises. 8.2 N.4 Official observers from Federal/State/Local governments critique 8.2.2.g exercises. Hold critiques. Formal evaluation based on critiques.

N.5 Establish means and management control for incorporating 8.2.2 observer's comments into plan and implementing corrective actions.

0. RADIOLOGICAL EMERGENCY RESPONSE TRAINING 0.1 Make provisions for training appropriate individuals. 8.1 0.1.a Provide training to off-site organizations 8.1.2 0.2 Training for on-site organization to include drills in which 8.2 individuals demonstrate abilities. On-the-spot corrections to be made and instructor to show proper performance.

0.3 First-aid teams trained in courses equivalent to Red Cross Multi- 6.5.4 Media.

0.4 Establish training programs, including initial training and retraining. Specify scope, nature, and frequency for:

0.4.a Directors and coordinators 8.1.1 0.4.b Personnel responsible for accident assessment 8.1.1

  • 0.4.c Radiological monitoring teams 8.1.1, 8.1.2 G-8 Millstone Station Emergency Plan Revision 56 March2018

Appendix G

  • Planning Standard 0.4.d 0.4.e 0.4.f Summary of Planning Standard Police, security, and fire-fighting personnel On-site repair and damage control/corrective action teams First aid and rescue personnel Plan Cross Reference (Section or Item) 8.1.2 8.1.1 8.1.1, 8.1.2 0.4.g Local support services 8.1.2 0.4.h Medical support personnel 8.1.2, 8.1.3 0.4.i Licensee's headquarters support personnel 8.1.1 0.4.j Personnel responsible for transmission of emergency information 8.1 instructions.

0.5 Provide initial and annual retraining of personnel. 8.1.1 P. RESPONSIBILITY FOR THE PLANNING EFFORT P.1 Train individuals responsible for planning effort. Section 8 P.2 Identify by title, individual with overall authority and responsibility Section 8 for radiological emergency response planning.

P.3 Designate Emergency Planning Coordinator. Section 8 P.4 Review and certify plan annually. Update plans as needed. 8.3 Incorporate changes identified by drills and exercises.

P.5 Forward plans and approved changes to responsible individuals 8.3 and organizations. Revised pages shall be dated and marked to show where changes have been made.

  • P.6 P.7 P.8 Each plan shall contain a detailed list of supporting plans and their source.

In appendix, list, by title, procedures required to implement the plan, including sections of the plan to be implemented by procedures.

Include specific table of contents and index.

Section 2, Table 2-1 Appendix D Table of Contents Cont'd Cross reference to NUREG-0654 criteria Appendix G P.9 Conduct independent reviews at least every 12 months and 8.3 include:

Cont'd Plan, procedures, practices, training, readiness, testing, 8.3 equipment and interfaces with State and Local governments.

Cont'd Include management controls for implementation and correction 8.3 of audit findings.

Cont'd Document reports to management and involved Federal, State 8.3 and Local organizations. Retain for 5 years.

P.10 Provide for updating telephone numbers in emergency 8.2.1.a procedures at least quarterly.

(

AppendixH APPENDIXH RADIOLOGICAL ASSESSMENT EQUIPMENT AND FACILITIES

(

TableH-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector Individual Applicability

1. Geophysical Monitors Meteorological Tower 4 Wind speed indicators Monitor wind speed at 33', 142', 374',

and 447' elevations 4 Wind direction indicators Monitor wind direction at 33', 142',

374', and 447' elevations 3 Delta temp. sensors Monitor temp. difference between 33' and 142' 33' and 374' 33' and 447' Meteorological Mast 1 Wind speed indication Monitor wind speed at 33'.

1 Wind direction indicator Monitor wind direction at 33'.

Time History Containment base slab (Unit 2) Record ground accelerations with Accelerographs respect to time Auxiliary building "

Intake structure "

Free field "

Peak Accelerographs Containment base slab Record peak ground accelerations

  • Seismic Trigger Response Spectrum Steam generator support Pressurizer support Safety injection tank support Containment base slab Containment base slab Activate an annunciator Records ground accelerations Recorder
1. Radiological Monitors Unit 1 Process Monitors RM-SFPl-02 Measure gaseous activity Unit 2 Process Monitors RM8123A Containment Monitor particulate activity recirculation air particulate RM8123B Containment Monitor gaseous activity recirculation air gaseous RM8262A Containment Monitor particulate activity recirculation air particulate RM8262B Containment Monitor gaseous activity recirculation air gaseous RM8434A Radwaste ventilation Monitor particulate activity particulate RM8434B Radwaste ventilation Monitor gaseous activity gaseous

TableH-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector Individual Applicability Unit 2 Process Monitors RM8011 Control room ventilation Monitor gaseous activity (Cont'd) gaseous RM8145A Spent fuel pool Monitor particulate activity ventilation particulate RM8145B Spent fuel pool Monitor gaseous activity ventilation gaseous RM8997 Radwaste ventilation Monitor particulate activity particulate RM8998 Radwaste ventilation Monitor particulate activity particulate RM4299 A, B & C Main steam Measure gaseous activity line monitors RM8999 Radwaste ventilation Monitor particulate activity particulate RM8132A Unit 2 stack discharge Monitor particulate activity particulate RM8132B Unit 2 stack discharge Monitor gaseous activity gaseous RM8168A Unit 2 stack high Monitor high level gaseous activity range RM8168B Unit 2 stack mid range Monitor gaseous activity RM5099 Steam jet air ejector Monitor gaseous activity RM9095 Waste gas storage Monitor gaseous activity tanks discharge gaseous RM4262 Steam generator Monitor liquid activity blowdown RM6038 Reactor bujlding closed Monitor liquid activity cooling water RM9049 Clean radwaste Monitor liquid activity discharge RM9116 Aerated radwaste Monitor liquid activity discharge RM9327 Condensate recovery Monitor liquid activity tank 2CND-RE245 Condensate Monitor liquid activity polishing neutralizing sump RM-8169 Wide Range Gas Monitors particulate and gaseous Monitor radioactivity

Table H-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector Individual Applicability Unit 3 Process Monitors 3HVR-RE10 A & B Ventilation Monitors particulate and gaseous Vent radioactivity 3HVR-RE11 &12 {A&B) Auxiliary Monitors particulate and gaseous Building (lower levels) radioactivity 3HVR-RE13, 14 & 15(A&B) Monitors particulate and gaseous Auxiliary Building (upper levels) radioactivity 3HVR-RE16 (A&B) Charging Monitors particulate and gaseous Pump Cubicle radioactivity 3HVR-RE17 (A&B) Fuel Building Monitors particµlate and gaseous activity 3HVR-RE18 (A&B) Waste Monitors particulate and gaseous Building radioactivity 3HVR-RE19 {A&B) SLCRS Monitors particulate and gaseous radioactivity 3HVR-RE91 (A&B) Control Monitors particulate and gaseous Room activity 3HVQ-RE49 ESF Building Monitors particulate and gaseous radioactivity 3CMS-RE22 A&B Containment Monitors particulate and gaseous Atmosphere radioactivity 3HVZ-RE09 A&B Hydrogen Monitors particulate and gaseous Recombiner Cubicles Ventilation radioactivity 3HVC-RE16 A&B Control Monitors gaseous radioactivity Building Inlet ventilation 3MSS-RE75, 76, 77,784 Main Monitors gaseous radioactivity Steam Relief lines 3ARC-RE21 Condenser Air Monitors gaseous radioactivity Ejector 3GWS-RE48 Hydrogenated Vent Monitors gaseous radioactivity 3MSS-RE79 Turbine Driven Monitors gaseous radioactivity Auxiliary Feedwater Pump Discharge 3SSR-RE08 Steam Generator Monitors liquid radioactivity Slowdown 3CCP-RE31 Reactor Plant Monitors liquid radioactivity Component Cooling 3CNA-RE47 Auxiliary Monitors liquid radioactivity Condensate 3LWS-RE70 Liquid Waste Monitors liquid radioactivity 3DAS-RE50 Turbine Building Monitors liquid radioactivity Drains

Table H-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector Individual Applicability Unit 3 Process Monitors 3LWC-RE65 Regenerant Monitors liquid radioactivity (Cont'd) Evaporator Unit 1 Area Radiation RM-SFPl-01 Monitor Radiation Levels Monitors Unit 2 Area Radiation RM-7892 Drumming and Measure radiation levels Monitors decontamination area RM-7894 Engineered safeguards Measure radiation levels systems area RM-7895 Sampling area Measure radiation levels RM-7896 Radioactive waste gas Measure radiation levels processing area RM-7899 Control room Measure radiation levels RM-8139 Spent fuel pool (south Measure radiation levels wall)

RM-8142 Spent fuel pool (north Measure radiation levels wall)

RM-8156 Spent fuel pool (north Measure radiation levels wall)

RM-8157 Spent fuel pool (south Measure radiation levels wall)

RM-8240 Containment High Measure radiation levels Radiation RM-8241 Containment High Measure radiation levels Radiation 2-RMS-9813 Drumming area Measure radiation levels 2-RMS-9799A Control Room Measure radiation levels ventilation air supply 2-RMS-97998 Control Room Measure radiation levels Ventilation air supply 2-RMS-04 (not in use) CPF- Measure radiation levels solid waste 2-RMS-05 (not in use) CPF- Measure radiation levels Condensate demineralizers 2-RMS-06 (not in use) CPF- Measure radiation levels Access area 2-RMS-08 (not in use) CPF- Measure radiation levels Evaporator

Table H-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector Individual Applicability Unit 3 Area Radiation 3RMS-RE01 Manipulator Crane Measure radiation levels Monitors 51 '4" Containment 3RMS-RE02 Fuel Transfer Measure radiation levels Tube51 '4" Containment 3RMS-RE03 In-Core Inst. Trans. Measure radiation levels 24'6" Containment 3RMS-RE04A Containment HR Measure radiation levels Internal 51 '4" Containment 3RMS-RE05A Containment HR Measure radiation levels Internal 51 '4" Containment 3RMS-RE06 Decontamination Measure radiation levels Area 24'6" Fuel Bldg.

3RMS-RE07 Calibration Room Measure radiation levels 66'6" Auxiliary Bldg.

3RMS-RE08 Spent Fuel Pit/Hoist Measure radiation levels 52'4" Fuel Bldg.

3RMS-RE09 Aux. Bldg. General Measure radiation levels (A) 18'6" Aux. Bldg.

3RMS-RE1 o Aux. Bldg. General Measure radiation levels (B) 4'6" Aux. Bldg .

3RMS-RE11 Aux. Bldg. General Measure radiation levels (C) 4'6" Aux. Bldg.

3RMS-RE12 Aux. Bldg. General Measure radiation levels (D) 24'6" Aux. Bldg.

3RMS-RE13 Aux. Bldg. General Measure radiation levels (E) 24'6" Aux. Bldg.

3RM-RE14 Aux. Bldg. General Measure radiation levels (F) 24'6" Aux. Bldg.

3RMS-RE15 Aux. Bldg. General Measure radiation levels (G) 43'6" Aux. Bldg.

3RMS-RE16 Aux. Bldg. General Measure radiation levels (H) *43'6" Aux. Bldg.

3RMS-RE17 Waste Disp. Bldg. Measure radiation levels 3RMS-RE18 Waste Disp. Bldg. Measure radiation levels 4'6" Waste Bldg.

4RMS-RE19 Solid Waste Measure radiation levels Storage 24'6" Waste Bldg.

3RMS-RE20 Sample Room 43'6" Measure radiation levels Aux. Bldg.

3RMS-RE21 Service Bldg. Measure radiation levels Laboratory 24'6" Service Bldg .

Table H-1 On-Site Assessment Equipment and Facilities Functional S~stem Instrument Detector Individual A~~licabilit~

Unit 3 Area Radiation 3RMS-RE22 Control Room Measure radiation levels Monitors (Cont'd) Monitor 47'6" Control Bldg.

3RMS-RE24 Waste Disposal Measure radiation levels Bldg. (C) 24'6" Waste Disp. Bldg.

3RMS-RE25 Waste Disposal Measure radiation levels Bldg. (D) 24'6". Waste Disp Bldg.

3RMS-RE28 Fuel Bldg. Pipe Measure radiation levels Rack 11 '0 Fuel Bldg.

3RMS-RE29 Spent Fuel Cask Measures radiation levels Area 52'4" Fuel Bldg.

3RMS-RE31 Fuel Transfer Tube Measures radiation levels 24'6" Containment 3RMS-RE32 Containment Air Measure radiation levels Compressor 24'6" Containment 3RMS-RE33 RHR Cubicle "A" Measure radiation levels (Normal Range) 4'6" ESF Bldg.

3RMS-RE34 RHR Cubicle "B" Measure radiation levels (Normal Range) 4'6" ESF Bldg.

3RMS-RE35 In-Core Inst. Measure radiation levels Thimble Area 3'8" Containment 3RMS-RE36 Fuel Pool Monitor Measure radiation levels 52'4" Fuel Bldg.

3RMS-RE37 Condensate Demin. Measure radiation levels Area 14'6" Cond. Polishing Bldg.

3RMS-RE38 Regeneration Area Measure radiation levels 38'6" Cond. Polishing Bldg.

3RMS-RE41 Fuel Drop Monitor Measure radiation levels 51'4" Containment 3RMS-RE42 Fuel Drop Monitor Measure radiation levels 51 '4" Containment 3RMS-RE52 Recombiner Measure radiation levels Control Room 24'6" Recombine Bldg.

2. Radiation Monitors and Gamma spectrometers Isotopic identification and analysis Sam12ling Egui12ment Geiger-Mueller survey Measure gamma and beta radiation instruments (0-1,000 R/hr range) dose rate Ionization chamber (0-1,000 R/hr . Measure gamma and beta radiation range) dose rate Contamination survey Count samples for gross alpha and beta

__J

Table H-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector Individual Applicability Radiation Monitors and Air sampling equipment Sample for airborne radionuclides Sampling Equipment (particulate, iodine, gaseous, and (Cont'd) tritium)

Neutron survey instrument Measure neutron radiation dose rate TLD Measure personnel radiation dose Direct reading pocket ion Measure personnel gamma radiation chamber dose

3. Fire Detection Smoke detectors Detects products of combustion Rate of rise heat detector Detects quick rise of temperature Fixed heat detector Detects a set temperature
4. Facilities Chemistry laboratory Equipped for chemical and radiological analysis 9 radiation monitoring stations Measure gamma radiation dose 4 Fixed air sampling stations Sample particulates and iodines Health Physics Laboratory Equipped for radiologica.l analyses

AppendixH

  • Functional System
1. Geophysical Monitors TableH-2 Off-Site Assessment Equipment and Facilities Instrument Detector Individual Applicability Meteorological Meteorological forecasting Provide current and forecast weather contractor for full weather for Millstone area forecast service Seismic United States Geological Survey Record ground accelerations (USGS) for Strong motion recorder
2. Radiological Monitors Environmental As specified by REMODCM Gamma radiation dose and sample Monitoring particulates and iodines
3. Laboratory Facilities Radiochemistry Teledyne Brown Engineering Equipped for chemical and laboratory Environmental Services radiological analysis GEL Environmental Laboratory Equipped for chemical and radiological analysis
4. Facilities Emergency Operations Facility Equipped for limited radiological analyses .

Appendix I APPENDIX I EMERGENCY ACTION LEVEL SCHEME

  • NOTE: The EAL scheme provides an example of how the Emergency Plan meets the standards of 50.47(b) and requirements of Appendix E. The EAL Tables in the Station Emergency Assessment procedure MP-26-EPI-FAP06 are used to classify event

__J

Appendix J APPENDIX.J EVACUATION TIME ESTIMATE PLUME EXPOSURE PATHWAY

Millstone Unit 1 Emergency Action Levels

  • D UNUSUAL EVENT DELTA ONE IN-PLANT RADIATION

~AA_1_M_A_c_T_o_R_B_~~-D-lli~G-~11u1 RADIATION (D-AA2) .

n SECURITY THREAT/ DESTRUCTIVE PHENOMENA SECURITY EVENT (D-HAl)

UNUSUAL EVENT DELTA TWO FIRE/GASES n ALERT CHARLIE ONE FUEL POOL EQUIPMENT FAILURE UNPLANNED OFFSITE RELEASES IOAl . OFFSITE DOSE (D-AAl) 11 JAl JUDGEMENT

~~~~NT 11 CLASSIFICATION ALERT L Unplamied release of . CHARLIE ONE

  • 1. Area radiation monitor 1. Any on-going or imminent security radioactivity 2: 3.42E-1 Any condition for which judgment reading in Reactor Building compromise t9 the ~afety ofthe plant. µCi/cc to the environment indicates that the level of safety Events are in progress or.h:ive or survey results indicate an UNCONTROLLED i11-crease in radiation levels by
  • I .

TA2 DESTRUCTIVE PHENOMENA (NIA)

(2:200 times MMODCM

.release limit) for 2:15 minutes.

for the Re.a..ctor Building or otll.er a:reas importap.t for maintaining the integrity of the spent fuel is occurred which indicate an actual or potential substantial degradation of the level of safety 100 mR/hr that is not the 2. Grab sample analyses indicate substantially degraded and which of the plant, to plant personnel, or An event that damages systems, structures, or rinplanrted gaseous release result of a planned evolution. requires Station Emergency to the safe storage of fuel in the components needed to maintain :Spent fuel rate 2: 3.42E~l µCi/cc (:2:::200 AND impedes operation of Response Organization {SERO) spent fuel pool.

int~grity that may result in overexposure ofsite times the MMODCM limit)

  • systems needed to maintain staffing.
  • personnel or resuits- in an uncontrolled decrease for :2:::15-rniriutes.

spent fuel integrity.

in the spent fuel pool water level or damage to

2. Valid radiation rrionitor spent fuel.
  • reading or survey results indicate greater than 15 mR/hr in areas required. to be occupied 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day.
  • ~R_u_1_M_A_c_T_o_R_B__

~_D_m RADIATION (D-AU2)

___G_J TutI 1

SECURITY EVENT (D-HUl)

Fill (D-HU3) Ill.IE_u_i_r;..::_-s_t_i.;..)o_o_L_L_E_v_E_L_ I 1o_u_1_~_L_i_~_s_E_S_(~_-_A_u_1)_ _11 ...JU-l----~---~-E....;2~_N_T_ _ ____.ll1 ..- I

_..11 ... I _UNU_D_:-~-;-~-:-:-:-N_T___.11

~-~~~~---J f-oaseous effluentmorritc>~ -1 Area radiation monitor reading in l. Security events as determined for Station Fire in the Reactor Building or other Uncontrolled decrease in fuel pool Any condition for which OR Reactor Building or survey results Safeguards Contingency Plan and reported areas important to maintaining the level indicated by a low level 2: 3.42E-3 µCi/cc(;::_ 2 times - I judgement indicates the potential DELTA ONE indicate an UNCONTROLLED increase in radiation levels by by Security Shift Supervision. integrity of the spent fuel NOT extinguished within 15 minutes of alarm actuation with all spent fuel assemblies remaining covered by IL_.__ MMODCM limits) for~ 60 j minutes.* *.. -**-*-**-*-*----*----_J or actual degradation in the level of safety of the Reactor Building Events are in progress or have

2. A credible site-specific security threat occurred which indicate a 25 mR/hr that is not the result of a Control Room notification OR within water. or other areas important to notification. 2. Grab sample analyses indicate potential degradation of the level planned evolution. 15 minutes of the fire alarm actuation maintaining the integrity of the 1..--------------,1 unplanned gaseous release of safety of the plant.

1G*n th eControlRoom. IEU2 FUELPOOL I rate 2: 3.42E-3 µCi/cc (:2::: 2 spent fuel.

1I TU2 DESTRUCTIVE PHENOMENA (D_-_HU_3)_ _ _ _ _ _ _ _ _ _ 1 11 02 TOXIC/FLAMMABLE GASES (D-HU3)

TEMPERATURE (D-SUl)

Uncontrolled heatup of the spent times the IBMODCM limit) for :2:::60 minutes.

l. Earthquake detected per ONP 514C, l,___ _ _ _ _..___.....__ _ _ __.1 fuel pool such that the bulk pool Earthquake.
l. Life threatening toxic gases OR temperature exceeds 150°F.
2. Report of tornado striking within the flammable gas concentrations as Protected Area (PA) that has the potential to identified in C-OP 200.5, "Oil, affect equipment needed to maintain spent Hazardous Material, Hazardous fuel integrity. Waste and Mixed Waste AREAS NEEDED TO MAINTAIN SPENT FUEL 3.

4.

On-Site sustained wind speed >75 mph.

Explosion or visible damage to structures, Contingency Plan," affecting activities in areas needed to maintain spent fuel integrity.

  • INTEGRITY Reactor Building - 4th and 5th Floors 1

systems, or components within the Protected Area with the potential to affect equipment required to maintain the integrity of the

2. Notification of a near-site release that may require evacuation of MPI.
  • Reactor Building, Fuel Pool Pump Mezzanine - 2nd floor Millstone spent fuel. *
  • H&V Room - Lower Level (DHR)
5. Flood Level> 19 Feet Mean Sea Level.
  • H&V Room - Roof- Coolers
6. Vehicle crash within the PA that could potentially affect equipment needed to maintain spent fuel integrity .
  • Specific setpoints are contained in EPI-FAP06, "Classification and PARs."

Millstone Emergency Plan Revision 56 March 2018 Page 1-2 of8

MILLSTONE UNIT 2 EMERGENCY AC110N LEVELS SITE AREA EMERGENCY

  • D GENERAL EMERGENCY ALPHA O GENERAL EMERGENCY BRAVO D CHARLIE-TWO D ALERT CHARLIE-ONE D UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE BARRIER FAILURE LOSS OF POWER EQUIPMENT FAILURE OFFSITE RELEASES CLASSIFICATION I BG1 _I I

, -- ~ '-*' '*

ALL THREE BARRIERS

-~**

11 Mode 1, 2, 3, 4 I ~ I STATION BLACKOUT II Mode 1, 2, 3, 4 I ~ I ATWS/INADEQUATE COOLING II Mode 1 I I OG1 II OFFSITE DOSE II Mode ALL I I GENERAL EMERGENCY I

Loss of Voltage on Buses 24C AND 24D AND ANY of the Functional Recovery of Reactivity Control Ineffective AND See Barrier Failure Reference table Following: EITHER of the Following: 1. MP2 Kaman Vent Monitor (RM-8168) Reading~ 2 µCi/cc I ALPHA I

. Restoration of Power to AT LEAST One Vital Bus is NOT . RCS Heat Removal by Steam Generator Heat Removal for > 15 Minutes

2. MP2 WRGM Site Stack Effluent Activity (RM-8169)

OR BRAVO Likely Within Four Hours Reading~ 30 µCi/cc for> 15 Minutes Events are in process or have occurred which

. Core Exit Thermocouple Readings Indicate Superheat SFSC Criteria Can NOT Be Satisfied 3. MSL Monitor (RM-4299/A/B/C) ReadingL2 R/hr involve actual or imminent substantial core

. Inadequate SG Heat Removal Capability as Indicated by Core Exit TC Temperature Readings> 800°F for> 15 Minutes

4. Measured Plume Dose Rate OnSite L 1,000 mR/hr for > 15 Minutes degradation or melting with potential for loss of containment integrity or security events that result in an actual loss of physical control of the SG Water Level .5. 10% in BOTH SGs AND Inadequate
5. Rad Assessment Determines Integrated Dose Offsite facility. Releases can be reasonably expected to Terry Turbine Feedwater Flow L 1 Rem TEDE OR~ 5 Rem CDE Thyroid exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

~j ANY TWO BARRIERS II Mode 1, 2, 3, 4 I ~ I STATION BLACKOUT II Mode 1, 2, 3, 4 I ~ I ATWS I I Mode 1 Manual Reactor Trip Attempted At Panel C04 AND Reactor Is I ~ I OFFSITE DOSE II Mode ALL I I SITE AREA EMERGENCY I NOT Shutdown 1. MP2 Kaman Vent Monitor (RM-8168) ReadingL 0.2 µCi/cc CHARLIE-TWO See Barrier Failure Reference Table Loss of Voltage on Buses 24C AND 24D > 15 Minutes for > 15 Minutes

~ I INABILITY TO MAINTAIN HOT S/D I I Mode 1, 2, 3, 4 I 2. MP2 WRGM Site Stack Effluent Activity (RM-8169) Reading Events are in process or have occurred which involve an actual or likely major failure of plant

§] I LOSS OF DC I I Mode 1, 2, 3, 4 I 1. No RCS Heat Removal Via Steam Generators AND Once Through Cooling NOT Effective AND Shutdown Cooling is NOT In Service L 10 µCi/cc for > 15 Minutes functions needed for protection of the public

2. RCS Boration Capability Unable to Eliminate Inadvertent Criticality 3. MSL Monitor (RM-4299A/B/C) ReadingL 0.3 R/hr or security events that result in intentional Loss of Voltage on DC Buses 201A AND 201 B > 15 Minutes for > 15 Minutes damage or malicious acts; (1) toward site

~ I IN-VESSEL FUEL UNCOVERY I I Mode 5, 6 Shutdown Cooling Has Been Lost AND ANY of the Following Conditions I 4. Measured Plume Dose Rate Onsite L 50 mR/hr for > 15 Minutes personnel or equipmentthatcould lead to the likely failure of or; (2) prevents effective

..Exist:

Alternate Methods for Restoring RCS Inventory are NOT Effective RVLMS Reading = 0% with OPERABLE #8 string (NA if no

5. Rad Assessment Determines Integrated Dose Offslte L 0.05 Rem TEDE OR L 0.25 Rem COE Thyroid access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which OPERABLE #8 string)
  • Core Exit TC Temperature Readings Indicate Superheat exeed EPA Protective Action Guideline

~ ~ass OF ANNUNCIATORS/TRANSIEN) I Mode 1, 2, 3, 4 I exposure levels beyond the site boundary.

.. Loss of Most (75%) MCB Annunciators AND BOTH of the Following Significant Transient in Progress Loss of SPDS AND ICC Instrumentation

§JI FUEL CLAD OR RCS BARRIER II Mode 1, 2, 3, 4 I ~ I STATION BLACKOUT I I Mode 5, 6, O I ~ I AUTOMATIC RX TRIP FAILURE II Mode 1, 2 I ~ I OFFSITE DOSE I I Mode ALL I I ALERT I Failure of Automatic Reactor Trip AND Manual Trip Was Successful 1. MP2 Kaman Vent Monitor (RM-8168) Reading L 0.02 µCi/cc CHARLIE-ONE See Barrier Failure Reference Table Loss of Voltage on Buses 24C AND 24D > 15 Minutes for > 15 Minutes Events are in process or have occurred which I EA2 I I 1NABILITY TO MAINTAIN COLDS/DI I Mode 5, 6 I 2. MP2 WRGM Site Stack Effluent Activity (RM-8169) Reading involve an actual or potential substantial I PA2 I I SINGLE AC POWER SOURCE II Mode 1, 2, 3, 4 I 1. Uncontrolled RCS Temperature Increase> 10°FThat Results ~ 1 µCi/cc for > 15 Minutes degradation of the level of safety of the plant or a security event that involves probable life I BA2 I I STEAM LINE BREAK 11 Mode 1, 2, 3, 4 I Only One AC Power Source Available to Supply Buses 24C AND/OR 24D > 15 Minutes Such That Loss ofThat Power 2.

in RCS Temperature> 200°F Inadvertent Criticality

3. MSL Monitor (RM-4299A/B/C) Reading L 0.03 R/hr for > 15 Minutes threatening risk to site personnel or damage to site equipment because of intentional malicious Unisolable Steam Line Break Outside CTMT Source Would Result in a Station Blackout (Unit 3 Buses 34A/B CANNOT be Credited unless already aligned to Unit 2 Bus 24C I EA3 I ~ass OF ANNUNCIATORS/TRANSIEN) I Mode 1, 2, 3, 4 I
4. Measured Plume Dose Rate Onslte L 5 mR/hr for > 15 Minutes dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

or 24D) Loss of Most (75%} MCB Annunciators > 15 Minutes AND EITHER of the Following: 5. Rad Assessment Determines Integrated Dose Offslte

~,

L 0.005 Rem TEDE ORL 0.025 Rem COE Thyroid Significant Transient in Progress Loss of SPDS AND ICC Instrumentation I

CTMT BARRIER 11 Mode 1, 2, 3, 4 I ~ I LOSS OF OFFSITE POWER II Mode ALL I ~

1.

I LOSS OF COLD S/D FUNCTION I I Loss of Shutdown Cooling> 15 Minutes AND Refuel Pool Mode 5, 6 I OU1 I I UNPLANNED RELEASE

... II Mode ALL I I UNUSUAL EVENT I See Barrier Failure Reference Table Loss of all OFFSITE power to buses 24C AND 24D for

> 15 Minutes. 2.

Water Level < 35 Ft., 6 In.

Uncontrolled RCS Temperature Increase> 10°F Effluent Monitors in Alarm OR Unplanned, Unmonitored or Uncontrolled Offsite Release AND DELTA-lWO Posture Code Limits I DELTA-TWO I as Determined from EPI-FAP06, "Classification and PARs,"

C§.J I RCS LEAKAGE I I Mode 1, 2, 3, 4 I

3. RCS Boron Concentration < Minimum Required Exceeded.

OR

~ II DELTA-ONE

1. Pressure Boundary Leakage > 1O GPM I

LOSS OF DC Mode 5, 6 I ~ IREFUEL/SPENT FUEL POOL LEVELi I Mode 6, O I *.

Note: Effluel)t Monitors Indicate Release Above Alarm Setpoint - Events are in process or have occurred which

2. Unidentified Leakage > 10 GPM Loss of Voltage on DC Buses 201A AND 201 B > 15 Minutes 1. Uncontrolled Spent Fuel Pool Water Level Decrease Causing Continuing > 60 minutes and Reporta~ility Evaluations indicate a potential degradation of the level of safety Loss of Cooling Suction Flow NbT Complete of the plant or indicate a security threat to facility
3. Identified Leakage > 25 GPM
2. Uncontrolled Refuel Pool Water Level Decrease Requiring protection. No releases of radioactive material
4. Primary to Secondary Leakage >25 GPM requiring offslte response or monitoring are Containment Evacuation £ili.Q. All Spent Fuel Assemblies in Safe Storage Locations expected unless further degradation of safety

~I FUEL CLAD DEGRADATION I Mode ALL I systems occurs.

II I I

~ I 2

LOSS OF ANNUNCIATORS Mode 1, 2, 3, 4

1. RCS Activity> 60 µCi/gm 1-131 DEQ
2. Dose Rate at One Foot from Unpressurized RCS Loss of Most (75%) MCB Annunciators > 15 Minutes AND SPDS OR . . . .

ICC Instrumentation Available Sample 2: 2 mR/hr/ml

~ I LOSS OF COMMUNICATIONS II Mode ALL I 1.

2.

Loss of ALL Onsite Electronic Communications Methods Loss of ALL Electronic Communications Methods With Government Agencies Millstone Millstone Emergency Plan

~ I SHUTDOWN LCO EXCEEDED II Mode 1, 2, 3, 4 I ..

Revision 56 March 2018 I NOTE: When two or more EALs apply, always choose the EAL of the highest incident classification; also always read from top to bottom in each category. I Unit NOT Brought To Required Mode Within Applicable LCO Action 1-3 of 8 Statement Time Limits -* . -**-*- ----~**---~----* **- .. . ----~---~-

  • - -~~.. "
    • ,,_ * * +

.... ", -*m "*-**-"*-'°' **-'-- -***" """'""'"

l MILLSTONE UNIT 2 EMERGENCY ACrfION LEVELS SITE AREA EMERGENCY GENERAL EMERGENCY ALPHA O GENERAL EMERGENCY BRAVO O CHARLIE-TWO D ALERT CHARLIE-ONE [ill UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE SECURITY THREAT/ FIRE/GASES JUDGEMENT CLASSIFICATION DESTRUCTIVE PHENOMENA

,~ I SECURITY EVENT *I I Mode ALL ~ ,_!___J_U_D_G_E_M_E_NT_ ____.! I Mode ALL I GENERAL EMERGENCY I A HOSTILE FORCE has taken control of plant equipment such that Other Conditions Exist For Which Judgement Indicates:

1. Actual Or Imminent Substantial Core Degradation 1;;~:1°~1;'~';+:;f:'°i:A(.P,HA"."~~;;~;);t~V"£i:::I plant personnel are unable to operate equipment required to With Potential For Loss Of Contii;inment, OR maintain safety functions. Any of the following meet this EAL:

OR BRAVO

.1. Loss of Control Room Events are in process or have occurred which

2. Potential For Uncontrolled Radiqlogical Releases.

~- Loss of Hot Shutdown Panel (C-21) (West 480v SWGR Room) involve actual or imminent substantial core These Releases Can Be Reasonably Expected To

3. Loss of Cold Shutdown Panel (C-1 O) (Upper 4160v SWGR Room) degradation or melting with potential for loss of Exceed EPA PAG Plume Exposure Levels Outside containment integrity or security events that
4. Security reports the loss or imminent loss of a Target Set The Site Boundary " result in an actual loss of physical control of the OR facility. Releases can be reasonably expected to A HOSTILE ACTION has caused failure of Spent Fuel Cooling exceed EPA Protective Action Guideline Systems and IMMINENT (for EALs) fuel damage is likely for a freshly exposure levels offsite for more than the off-loaded reactor core in pool. immediate site area.

SPENT FUEL DAMAGE Mode ALL ]~ I...__ s_E_C_U_R_ITY_E_V_EN_T_'_ __.!!,____M_o_de_A_L_L___. ~  ! CONTROL ROOM EVACUATION ! ,_!_M_o_de_A_L_L__, ~ I.____J_U_D_G_E_M_E_NT_~:]__,  ! Mode ALL SITE AREA EMERGENCY Spent Fuel is Exposed from Open Vessel or Cavity AND BOTH Unit Control from Hot Shutdown Panel C-1 O Or C-21 Other Conditions Exist For Which Judgement Indicates CHARLIE-TWO A notification from the site security force that an armed attack, of the Following: NOT Established Within 15 Minutes After Control Room Actual Or Likely Major Failures of Plant Functions Needed Events are in process or have occurred which explosive attack, airliner impact, or other HOSTILE ACTION is Evacuation involve an actual or likely major failure of plant For Protecton OfThe Public Spent Fuel Has Decayed < 30 Days occurring or has occurred within the protected area. functions needed for protection of the public or security events that result in intentional damage CTMT Integrity Established or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exeed EPA Protective Action Guideline exposure levels beyond the site boundary.

~  ! SPENT FUEL ASSEMBLY DAMAGE I ._!_M_o_d_e_A_L_L__,  ! TA1 I  !.____ _s_E_c_u_R_ITY_E_VE_N_T_ _ _.! I..._M_o_de_A_L_L__, ~ I CONTROL ROOM EVACUATION I Mode ALL ~ ,_l_ _ _ J_U_D_G_E_M_E_NT

_ ____,] l Mode ALL ALERT

1. Security Events as determined for Station Safeguards Contingency
1. Spent Fuel is Exposed from Open Vessel, Cavity, or SF Pool Any Condition For Which Judgement Indicates That Safety CHARLIE-ONE Plan and reported by Security Shift Supervision. (Addresses events Control Room Evacuation Initiated AND Spent Fuel Has Decayed..:::. 30 Days that involve Actual or Potential Substantial degradation to the level of Systems May Be Degraded AND Which Requires Emergency Events are in process or have occurred which
2. Fuel Handling Accident Causing Damage to Spent Fuel, Indicated by Fuel Building OR Containment Radiation Monitors Increasing 2.

safety of the plant.)

A notification from the stte security force that an armed attack, explosive attack, airliner impact, or other HOSTILE ACTION is I I j,___

GA2 F_IR_E_IEX_P_LO_s_1_o_N_ _ _.j !____ M_o_d_e_A_LL_ _

Response Organization Staffing involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life occurring or has occurred within the OCA. Fire or Explosion Affecting Safe Shutdown Area AND Damage threatening risk to stte personnel or damage to stte

! RA2  ! I...__ P_LA_NT_RA_D_IA_T_IO_N_ _.....  ! ,_! _M_o_de_A_L_L____. 3. A validated notification from the NRG of an airliner attack threat less than 30 minutes away.

to Structures OR Safe Shutdown Equipment Indicated. equipment because of intentional malicious dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA

1. Radiation Readings > 15 mR/hr in Control Room OR Central Alarm Station OR Secondary Alarm Station  ! TA2 !I DESTRUCTIVE PHENOMENA  ! ._!_M_o_d_e_A_L_L__, l GA3  !  ! TOXIC/FLAMMABLE GASES I ,_!_M_o_de_A_L_L__.

Protective Action Guideline exposure levels.

2. Radiation Reading > 5 R/hr in Areas Requiring Access for 1. Seismic Event > o.ogg ZPA Life Threatening Toxic Gases OR Flammable Gas Concentrations Safe Shutdown 2. Onsite Sustained Windspeed > 90 MPH as Identified in C-OP 200.5, "Oil, Hazardous Material, Hazardous
3. Visible Damage to Structures or Equipment AND Affecting Safe Shutdown Waste and Mixed Waste Contingency Plan" Affecting Areas for
4. Vessel or Vehicle Collision AND Affecting Safe Shutdown Safe Shutdown *
5. Missiles Affecting Safe Shutdown
6. Flooding Affecting Safe Shutdown

~  !.____ _ RA_D_M_O_N_IT_O_R_s_ _ _.! I..._M_o_de_A_L_L__, ~ I...__s_E_c_u_R_ITY_E_V_EN_T_ __.I I. . _M_o_de_A_L_L__, ~ .._l_ _ _ _ F_IR_E_ _ _ _.....,! ._!_M_o_de_A_L_L__. ~ ,._!_ _ _J_U_D_G_E_M_E_NT _ _ _]__.  ! Mode ALL UNUSUAL EVENT

1. Security Condttion as determined for Station Safeguards Contingency 1. Fire in Building OR Areas Adjacent to Areas Needed for Safe Any Condition For Which Judgement Indicates Potential
1. Uncontrolled Refuel Pool Water Level Decrease AND Rad Plan and reported by Security Shift Supervision. (Addresses events Shutdown NOT Extinguished Wtthin 15 Minutes of Notification OR Degradation in the Level of Safety of the Plant h:';~::L:J ,j!i:>,~LT.{\~,)WQ't:!:~+'s',t:d Levels Require Evacuation of CTMT or Spent Fuel Pool Area that involve Potential degradation in the level of safety of the plant.) Verification of Control Room Alarms
2. Fire Affecting a Loaded ISFSI Confinement Boundary NOT OR
2. A credible stte specific security threat notification.
2. Unexpected Area Rad Monitor Reading Offscale High OR Extinguished Wrthin 15 Minutes of Notification. DELTA-ONE

> 1000 Times Normal Reading 3. A validated notification from the NRG providing information of an Events are in process or have occurred which

! TU2 aircraft threat.

!! DESTRUCTIVE PHENOMENA !I Mode ALL

! GU2  !  ! TOXIC/FLAMMABLE GASES  !  !.____M_o_de_A_L_L__, indicate a potential degradation of the level of safety of the plant or indicate a security threat to faciltty

1. Life Threatening Toxic Gases OR Flammable Gas Concentrations as protection. No releases of radioactive material
1. Seismic Activity Detected Per.AOP-2562, Earthquake Identified in C-OP 200.5, "O(Hazardous Material, Hazardous Waste requiring offstte response or monttoring are
2. Report by Plant Personnel of Tornado Striking Wrthin Protected Area and Mixed Waste Contingency Plan" Affecting Normal Operation expected unless further degradation of safety
3. Visible Damage to Structures or Equipment Wtthin the Protected Area 2. Notification of a Near-Stte Release That May Require Evacuation systems occurs.

2

  • 4. Onstte Sustained Windspeed > 75 MPH
5. Explosion Wtthin the Protected Area AREAS OF CONCERN FOR SAFE SHUTDOWN
6. Turbine Failure Causing Observable Casing Damage Control Room Switchgear Rooms
7. Vessel or Vehicle Collision With Structures OR Equipment Required Cable Vaults Intake Structure Millstone for Safe Shutdown or a loaded ISFSI Confinement Boundary Turbine Building Switchgear Area
8. Flood Level > 19 Feet Mean Sea Level Penetration Areas Coolant Tanks Area
9. Flooding in Areas Containing Safe Shutdown Equipment RBCCWRooms Containment Diesel Generator Room DC Equipment and Battery Rooms Millstone Emergency Plan Charging Pump Cubicles Safety Injection Pump Rooms Revision 56 NOTE: When two or more EAL.s apply, always choose the EAL of the highest incident classification; also always read from top to bottom in each category. Switchyard March 2018 1-4 of 8

MILLSTONE 2 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE IMMINENT - No Turnaround in Safety System Performance is Expected AND Escalation to General Emergency Conditions Will Occur Within 2 Hours DICATORS FUEL CLAD BARRIER RCS BARRIER CTMT BARRIER ----------------

THREE BARRIERS MORE THAN I FCB1 I I ONE BARRIER LOSS I I RCB1 I I LOSS I

Not Applicable L p L p L p AFFECTED SAFETY FUNCTION Not Applicable CTMT STATUS/

FUNCTIONAL I POTENTIAL LOSS I I POTENTIAL LOSS I

Uncontrolled RCS Cooldown AND RCS Pressure-Temperature To RECOVERY 0 the Left Of the PTS Limit 200°F Subcooling Maximum Curve 0 No RCS Heat Removal Via Steam Generators AND Once Through Cooling NOT Effective AND Shutdown Cooling System Is NOT In Service I 0 No RCS Heat Removal Via Steam Generators AND Once Through Cooling NOT Effective AND Shutdown Cooling System Is NOT In Service I FCB2 I I LOSS I I RCB2 I I LOSS I I CNB1 I I LOSS I . 3/3 CORE EXIT TC Not Applicable TEMPERATURES [TI Core Exit Thermocouple Readings > 1200'° F

[TI RCS Subcooling < 30°F I I I POTENTIAL LOSS I POTENTIAL LOSS I POTENTIAL LOSS I ~ Core ExitTCTemperature Readings >1200°FAND Do 0 Core Exit Thermocouple Readings> 700 °F Not Applicable NOT Decrease Within 15 Minutes I RCB3 ! I LOSS I I CNB2 I I LOSS I Not Applicable [I] Rapid Unexplained CTMT Pressure Decrease YES Following Initial Increase PRESSURE I POTENTIAL LOSS I [I] No CTMT Pressure Increase When Expectation Exists I POTENTIAL LOSS I 0 Uncontrolled RCS Pressure Decrease and Increasing Containment Radiation Monitors 0 CTMT Pressure > 1O PSIG AND Increasing AND No Containment Spray Pump 0 CTMT H2 Concentration~ 4% TWO BARRIERS I RCB4 I I LOSS I I CNB3 I I LOSS I L p L p L p SITE AREA

.... [I] Reactor Coolant Leak > eves Capacity AND Entry Into [TI Primary to Secondary > Tech Spec Limits and EITHER exists: CLAD RCS CTMT EOP-2534, Steam Generator Tube Rupture or EOP 2540,

  • Nonisolable Steam Release from Affected S/G to EMERGENCY Functional Recovery, to Address Steam Generator Tube Rupture . environment Prolonged Release From Affected S/G to Environment COOLANT I POTENTIAL LOSS I When Used for Cooldown (see basis for description of prolonged release) CHARLIE-LEAKAGE Reactor Coolant Leak > eves Capacity AND Entry Into [TI Leakage Through BOTH Isolation Valves AND a Pathway to TWO

.. 0 EOP-2525, Standard Post Trip Actions the Environment Exists Requiring Actions Outside the Control Room to Isolate 0 Reactor Coolant Leak Rate~ eves Capacity AND EITHER I I of the following:

.. Entry Into EOP 2534, Steam Generator Tube Rupture m POTENTIAL LOSS Leakage Exists Outside CTMT Requiring Isolation From 2/3 Entry Into EOP 2540, Functional Recovery, to Jl.ddress inside the Control Room AND EITHER of the following:

Steam Generator Tube Rupture Entry Into EOP 2532, Loss of Coolant Accident Entry Into EOP 2540, Functional Recovery, to Address Loss of Coolant Accident I FCB3 I I LOSS I '*

I RCB5 I I LOSS I I CNB4 I I LOSS I

[TI RM-8240/8241 Reading> 300 R/hr

[I] RM-8240/8241 Reading> 5 R/hrWithout Fuel Clad [I] Offsite Dose Plume Rate~ 10-BTimes RM-8240/8241 ONLY ONE BARRIER AFFECTED cg RM-8240/8241 Reading> 5 R/hr Without RCS Release lnsideCTMT Barrier Loss Reading if Release is to CTMT cg At Least 5% Fuel Clad Damage As Determined By Core ALERT Damage Estimate OR Sample System Dose Rates Obtained Using CP 2802N, "Primary System Sampling Analysis" I POTENTIAL LOSS I I POTENTIAL LOSS I

RADIATION cg Dose Rate at One Foot from Unpressurized RCS Sample Not Applicable 0 RM-8240/8241 Reading > 1,200 R/hr

~ 28 mR/hr/ml CHARLIE-I POTENTIAL LOSS I 0 At Least 20% Fuel Clad Damage As Determined By Core Damage Estimate L p i. p L p ONE Not Applicable i CLAD RCS CTMT I FCB4 I I LOSS I I CNB5 I I LOSS I

cg

2 Not Applicable WATER No CTMT Sump Level Increase When Expectation Exists I I UNUSUAL LEVEL 0 =

POTENTIAL LOSS RVLMS Reading 0% with OPERABLE #8 string (NA if no I POTENTIAL LOSS I EVENT OPERABLE #8 strina) Not Applicable I FCB5 I  ! I RCB6 I I CNB6 I DELTA-ONE JUDGEMENT Any Condition For Which Judgement Indicates ~oss or Potential

  • Loss of Fuel Clad Barrier Due to:

. 1.

Imminent Barrier Degradation Based On Current Safety Any Condition For Which Judgement Indicates Loss or Potential Loss of RCS Barrier Due to:

Imminent.Barrier Degradation Based On Current Safety Any Condition For Which Judgement Indicates Loss or Potential Loss of CTMT Barrier Due to:

. Imminent Barrier Degradation Based On Current Safety Millstone

. System Performance

  • Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate

. System Performance Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate

. System Performance Degraded Rssion Barrier Monitoring Capability Making Barrier Status lndeterm in ate Millstone En\ergency Plan Revision 56 ;

March201B

  • 1-5 ofB

MILLSTONE 01' ...'f 3 EMERGENCY AC . . ION LEVELS

~

w,_J§ GENERAL EMERGENCY ALPHA O GENE'.RAI, EMERGENCY BRAVO D SITE AREA EMERGENCY CHARLIE-TWO D ALERT CHARLIE-ONE @I UNUSUAL EVENT DEf-TA-TWO D UNUSUAL EVENT DELTA-ONE BARRIER FAILURE

  • LOSS OF POWER EQUIPMENT FAILURE OFFSITE RELEASES CLASSIFICATION I I I. . __

F,'G1 s_T_A_TI_O_N_B_LA_c_K_O_UT

_ _....., I Mode 1, 2, 3, 4 §J I ATWS/INADEQUATE COOLING I !. . __ M_o_d_e_1_ _. GENERAL EMERGENCY I

?Loss of Voltage on Buses 34C AND 34D (Station Blackout Reactor Power> 5% Following Entry into FR-S.1 AND EITHER l'.'.~;;i,.;f;'.c~b~\1'(.A'EPHt.\<t}-' C. :t,: I

Diesel cannot be credited) AND ANY of the of the Following: OR
Following: Core Cooling - RED BRAVO

~'

  • Restoration of Power to AT LEAST One Bus is NOT Events are in process or have occurred which All SG Wide Range Levels < 21 % involve actual or imminent substantial core Likely Within Four Hours degradation or melting with potential for loss of (24% Adverse CTMT)

!* Core Cooling - RED containment integrity or security events that result in an actual loss of physical control of the

  • Heat Sink - RED AND Required Feedwater Flow Can facility. Releases can be reasonably expected to NOT be Established Within 15 minutes exceed EPA Protective Action Guideline

~xpos~re l:vels offsite for more than the ANY TWO BARRIERS Mode 1, 2, 3, 4 ~ I. . __ s_T_A_TI_O_N_B_LA_c_K_O_UT

_ _....., I Mode 1, 2, 3, 4

~ I. . ____ A_TW_s_ _ _ __.! I. . __M_o_d_e_1_ ..... OFFSITE DOSE Mode ALL SITE AREA EMERGENCY FR-S.1 is Entered Direct] From E-0 CHARLIE-TWO

1. MP3 Ventilation Vent Monitor (3HVR*RE1 O) Reading..:::. 0.1 µCi/cc See Barrier Failure Reference Table Loss of Voltage on Buses 34C AND 34D > 15 Minutes

~ INABILITY TO MAINTAIN HOT S/D I Mode 1, 2, 3, 4 for > 15 Minutes (Station Blackout Diesel cannot be credited) Events are in process or have occurred which *

1. Heat Sink- RED AND BOTH of the Following: 2. MP3 SLCRS Monitor (3HVR*RE19) Rec\(ling.:::. 10 µCi/cc involve an actual or likely major failure of plant
  • Required Feedwater Flow Can NOT Be Established Wrthin 15 Minutes for > 15 Minutes I *Ps2 ! I. . ___Lo_s_s_o_F_D_c_ ____.l I Mode 1, 2, 3, 4 2.
  • RCS Bleed and Feed Can NOT Be Established RCS Boration Capability Unable to Eliminate Inadvertent Criticality
3. MP3 Safeties or Steam Dump Monitor (3MSS-RE75/76m/7B) functions needed for protection of the public or security events that result in intentional damage or Reading.:::. 0.8 µCi/cc for >. 15 Minutes_ malicious acts; (1) toward site personnel or Loss of Voltage on DC Buses 1, 2, 3 AND 4 > 15 Minutes ~  ! IN-VESSEL FUEL UNCOVERY j j Mode 5, 6 4. Terry Turbine Monitor (3MSS-RE79) Reading.:::. 1 µCi/cc equipmentthatcould lead to the likely failure ofor; (2) prevents effective access to equipment RHR Has Been Lost AND ANY of the Following Conditions Exist: for > 15 Minutes Alternate Methods for Restoring RCS Inventory Are NOT Effective needed for the protection of the public. Any
5. Measured Plume Dose Rate Onslte..:::. 50 mR/hr releases are not expected to result in expo.sure RVLMS Reading Decreasing Toward 19% Level (Plenum) with for > 15 Minutes levels which exeed EPA Protective Action OPERABLE 19% sensor (NA tt no OPERABLE 19% sensor)
6. Rad Assessment Determines Integrated Dose Offslte..:::. 0.05 Guideline exposure levels beyond the site GET Readings Indicate Superheat Conditions Rem TEDE OR.:::. 0.25 Rem CDE Thyroid boundary.

! ES4 I boss OF ANNUNCIATORS/TRANSIEN,j ! Mode 1, 2, 3, 4 Loss of Most (75%) MCB Annunciators AND BOTH of the Following:

~  ! FUEL CLAD OR RCS BARRIER !I Mode 1, 2, 3, 4 ~ I. . __ sr_A_T_IO_N_B_LA_C_K_O_UT

__ _.I I Mode 5, f;l, 0 ~  ! AUTOMATIC RX TRIP FAILURE I j.__M_o_d_e_1,_2_ _. I OA1  ! ._I_ _o_F_F_S_IT_E_o_os_E_....,.....~]_. I Mode ALL ALERT Failure of Automatic Reactor Trip .Afill. Manual Trip Was Successful 1. MP3 Ventilation Vent Monitor (3HVR*RE10) Reading See Barrier Failure Reference Table Loss of Voltage on Buses 34C llliQ. 340 > 15 Minutes

! PA2  !.I SINGLE AC POWER SOURCE !I Mode 1, 2, 3, 4

! EA2 ! I INABILITY TO MAINTAIN COLD S/D II Mode 5, 6 2.

..:::. 0.01 µCi/cc for > 15 Minutes MP3 SLCRS Monitor (3HVR*RE1 9) Reading_:::. 1 µCi/cc for CHARLIE-ONE Events are in process or have occurred which

1. Uncontrolled RCS Temperature Increase > 10 ° F That Results > 15 Minutes
  • I I I. . __

BA2 s_TEA_M_L_IN_E_B_R_E_A_K_ __,, I Mode 1, 2, 3, 4 Only One AC Power Source Available to Supply Buses 34C AND/OR 34D

>'15 Minutes Such That Loss of That Power Source Would Result in a 2.

in RCS Temperature > 200 ° F Inadvertent Criticality

3. MP3 Safeties or Steam Dump Monitor (3MSS-RE75/76/77/78)

Reading..:::. 0.08 µCi/cc for > 15 Minutes involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life Unisolable Steam Line Break Outside CTMT Station Blackout (Station Blackout Diesel CANNOT be Credited)  ! ! boss EA3 OF ANNUNCIATORS/TRANSIENi  ! Mode 1, 2, 3, 4

4. Terry Turbine Monitor (3MSS-RE79) Reading Of..:::. 0.1 µCi/cc for> 15 Minutes threatening risk to site personnel or damage to site equipment because of intentional malicious
5. Measured Plume Dose Rate Onslte,2:. 5 mR/hr for> 15 Minutes dedicated efforts of a hostile act. Any releases are Loss of Most (75%) MCB Annunciators > 15 Minutes AND EITHER of expected to be limited to small fractions of the EPA the Following: 6. Rad Assessment Determines Integrated Dose Offslte.:::. 0.005 Protective Action Guideline exposure levels.

Significant Transient in Progress Rem TEDE OR.:::. 0.025 Rem CDE Thyroid Loss of SPDS AND ICC Instrumentation

~ I...___ c_T_MT_BA_R_R_IE_R_ _ __.! I Mode 1, 2, 3, 4 ~  ! LOSS OF OFFSITE POWER  ! I. . _M_o_d_e_A_LL_ _. ~ I LOSS OF COLD S/D FUNCTION I Mode 5, 6 UNUSUAL EVENT

1. Loss of RHR Cooling > 15 Minutes AND Valid PZR Water Level See Barrier Failure Reference Table CossofallOFFSITEpowerto buses34CAND34Dfor > 15Minutes (LT 462) Reading< 40% j,i)~;:~~/!;;;_,:'DEj;,1_A;:hW9;, ';:, ~,L?'I

~ ~'_ _ _R_c_s'"'"L_EA_KA_G_E_ _ __.! I Mode 1, 2, 3, 4

2. Uncontrolled RCS Temperature Increase> 10°F OR I;Pu2 I I. . ---,--Lo_s_s_o_F_Dc_ _ __.l -I_M_o_d_e_5_,6_..... 3. RCS Boron Concentration< Minimum Requiredr---------, DELTA-ONE 1.

2.

Pressure Boundary Leakage > 1o GPM Unidentified Leakage > 1O GPM Loss of Voltage on DC Buses 1, 2, 3 AND 4 > 15 Minutes

! !I EU2 CAVllY SEAL FAILURE  !! Mode 6, O Events are in process or have occurred which indicate a potential degradation of the level of Refueling Cavity Seal Failure AND EITHER of the Following: safety of the plant or indicate a security threat to

3. Identified Leakage > 25 GPM Valid PZR Level (LT 462) Reading < 40% facility protection. No releases of radioactive I I______

material requiring offsite response or monitoring Valid SFP Level (LI 26) Reading = 0%

I II BUS FUEL CLAD DEGRADATION Mode ALL __, Applies in Mode O when transfer gate is open.

are expected unless further degradation of safety systems occurs.

~  !

3

1. RCS Activity > 60 µCi/gm 1-131 DEQ I LOSS OF ANNUNCATIROS .-1-M-o-de-1,-2-,3-,-4--,
2. Dose Rate at One Foot from Unpressurized RCS Sample Loss of Most (75%) MCB Annunciators> 15 Minutes AND SPDS OR

~ 1 mR/hr/ml ICC Instruments Available /'!

~  ! LOSS OF COMMUNICATIONS  !! Mode ALL 1.

2.

Loss of ALL Onsite Electronic Communications Methods Loss of ALL Electronic Communications Methods With Government Agencies Millstone

~ I SHUTDOWN LCO EXCEEDED  ! I Mode 1, 2, 3, 4 Millstone Emergency Plan Revision 56 NOTE: When two or more EALs apply, always choose the EAL of the highest incident classification; also always read from top to bottom in each category. Unit NOT Brought To Required Mode Within Applicable LCO Action Mach 2018 Statement Time Limits 1-6 ofB

MILLSTONE UJ:_~T 3 EMERGENCY AC. ____ lON LEVELS

  • SITE AREA EMERGENCY GENERAL EMERGENCY ALPHA O GENERAL EMERGENCY BRAVO O CHARLIE-TWO D ALERT CHARLIE-ONE D UNUSUAL EVENT DE~TA-TWO D UNUSUAL EVENT DELTA-ONE IN -PLANT RADIATION DESTirffc?}R1t;lP1H:~11fuNA FIRE/GASES JUDGEMENT CLASSIFICATION

~

r l SECURITY EVENT ll Mode ALL JUDGEMENT :J ._l _M_o_d_e_A_L_L___, GENERAL EMERGENCY I

A HOSTILE FORCE has taken control of plant equipment such that Other Conditions Exist For Which Judgement Indicates:

plant personnel are unable to operate equipment required to main- 1. Actual Or Imminent Suj)stantial Core Degradation tain safety functions. Any of the following meet this EAL: With Potential For Loss Of Containment, OR OR BRAVO 1;'. Loss of Control Room I

2. Potential For Uncontrolled Radiological Releases. Events are in process or have occurred which
!: Loss of Remote Shutdown Panel These Releases Can Be Reasonably Expected To involve actual or imminent substantial core a'. Security reports the loss or imminent loss of a Target Set Exceed EPA PAG Plume Exposure Levels Outside degradation or melting with potential for loss of containment integrity or security events that result OR The Site Boundary '. - in an actual loss of physical control of the facility.

A HOSTILE ACTION has caused failure of Spent Fuel Cooling Releases can be reasonably expected to exceed Systems and IMMINENT (for EALs) fuel damage is likely for a freshly EPA Protective Action Guideline exposure levels off-loaded reactor core in pool. offsite for more than the immediate site area.

SPENT FUEL DAMAGE Mode ALL I *TS1 I .... l _ _s_E_c_u_R_ITY_E_V_EN_T_ ___.l .... I _.M_o_d_e_A_LL_ _. ~ l CONTROL ROOM EVACUATION ll- _M_o_de_A_L_L _.l ~ l. . ___ J_U_DG_E_M_E_N_T_ ___.l ....

I _M_o_de_A_L_L___, SITE AREA EMERGENCY Spent Fuel is Exposed from Open Vessel, or Cavity AND BOTH of A notification from the site security force that an armed attack, Unit Control from Auxiliary Shutdown Panel NOT Established CHARLIE-TWO Other Conditions Exist For Which Judg.ement Indicates the Following: explosive attack, airliner impact, or other HOSTILE ACTION is Within 15 Minutes After Control Room Evacuation Events are in process or have occurred which Actual Or Likely Major Failures of Plant Functions Needed occurring or has occurred within the protected area. involve an actual or likely major failure of plant Spent Fuel Has Decayed < 30 Days For Protecton Of The Public functions needed for protection of the public or CTMT Integrity Established security events that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exeed EPA Protective Action Guideline exposure levels beyond the site boundary.

~ l SPENT FUEL ASSEMBLY DAMAGE l I. . __ M_od_e_A_L_L_ _.

I TA1 I ... I __s_E_c_u_R_ITY_E_V_EN_T_ ___.I -1_M_o_d_e_A_LL_ _.

~ I CONTROL ROOM EVACUATION I Mode ALL

~ I. . ___ l J_U_DG_E_M_E_N_T_ _.... l....___M_o_de_A_L_L_.

ALERT

1. Spent Fuel is Exposed from Open Vessel, Cavity OR SF Pool 1..
  • Security Events as determined for Station Safeguards Contingency Control Room Evacuation Initiated Any Condition For Which Judgement Indicates That Safety AND Spent Fuel Has Decayed~ 30 Days Plan and reported by Security Shift Supervision. (Addresses events Systems May Be Degraded And Which Requires Emergency
2. Fuel Handling Accident Causing Damage to Spent Fuel, Indicated by Fuel Building OR Containment Radiation Monitors that involve Actual or Potential Substantial degradation to the level of safety of the plant.)
2. A notification from the site security force that an armed attack, I IGA2 L_FIRE/EXPLOSION  ! l. . _M_o_de_A_L_L__.

Response Organization Staffing CHARLIE-ONE Increasing explosive attack, airliner impact, or other HOSTILE ACTION is Fire or Explosion Affecting Safe Shutdown Area AND Damage Events are in process or have occurred which occurring or has occurred within the OCA. to Structures OR Safe Shutdown Equipment Indicated. involve an actual or potential substantial I RA2 I I....__P_LA_N_T_RA_D_IA_T_IO_N_ ____,l ....I _M_o_d_e_A_LL_ __. 3. A validated notification from the NRC of an airliner attack threat less than 30 minutes away.

degradation of the level of safety of the plant or a security event that involves probable life

1. Radiation Readings > 15 mR/hr in Control Room OR Central Alarm Station OR Secondary Alarm Station l ll TA2 DESTRUCTIVE PHENOMENA ll Mode ALL I GA3 l  ! TOXIC FLAMMABLE GASES l ._I_M_o_d_e_A_LL_~

threatening risk to site personnel or damage to site equipment because of intentional malicious dedicated efforts of a hostile act. Any releases are

2. Radiation Reading > 5 R/hr in Areas Requiring Access for 1. Seismic Event > 0.09g ZPA Life Threatening Toxic Gases QB. Flammable Gas Concentrations expected to be limited to small fractions of the EPA Safe Shutdown 2. Onsite Sustained Windspeed > 90 MPH as Identified in C-OP 200.5, Oil, Hazardous Material, Hazardous Protective Action Guideline exposure levels.
3. Visible Damage to Structures or Equipment AND Affecting Safe Shutdown Waste and Mixed Waste Contingency Plan Affecting Areas for Safe
4. Vessel or Vehicle Collision AND Affecting Safe Shutdown Shutdown
5. Missiles Affecting Safe Shutdown
6. Flooding Affecting Safe Shutdown

~ .... I ___RA_D_M_O_NI_TO_R_s_ ___.l ,...._M_o_d_e_A_LL_ __.  !*TU1 l l.___s_E_c_u_RI_TY_E_V_E_N_T_ ____.l I .Mode ALL ~ ._l_ _ _ _ F_IR_E_ _ ____,, ._l _M_o_d_e_A_LL_ _. ~ ._l_ _ _J_U_DG_E_M_E_N_T_ ___.l !.__M_o_de_A_L_L___,

UNUSUAL EVENT

1. Containment OR Fuel Building Area Rad Monitor Alarms Indicate 1'. Security Condition as determined for Station Safeguards Contingency 1. Fire in Buildings OR Areas Adjacent to Areas Needed for Safe Any Condition For Which Judgement Indicates Potential Cavity Seal Failure Plan and reported by Security Shift Supervision. (Addresses events that involve Potential degradation in the level of safety of the plant.)

Shutdown NOT Extinguished Within 15 Minutes of Control Room Notification OR Verification of Control Room Alarms Degradation in the Level of Safety of the Plant 1~,;~~~1ll*1:t~~.~~tli~mt~~%~tf~~1~;.~~~?I

2. Unexpected Rad Monitor Reading Offscale High OR 2. A credible site specific security threat notification. 2. Fire affecting a loaded ISFSI confinement boundary NOT OR

> 1000 Times Normal Reading extinguished within 15 minutes. DELTA-ONE

3. A validated notification from the NRC providing information of an Events are in process or have occurred which aircraft threat.

I lI Gu2 TOXIC/FLAMMABLE GASES I I. . _M_o_d_e_A_LL_ _. indicate a potential degradation of the level of safety I IjTU2 DESTRUCTIVE PHENOMENA l ._l_M_o_d_e_A_LL_ _. 1. Life Threatening Toxic Gases OR Flammable Gas of the plant or indicate a security threat to facility protection. No releases of radioactive material

  • 3
1. Seismic Activity Detected Per AOP-3570, Earthquake Concentrations as Identified in C-OP 200.5, Oil, Hazardous requiring offsite response or monitoring are Material, Hazardous Waste and Mixed Waste Contingency expected unless further degradation of safety
2. Report by Plant Personnel of Tornado Striking Within Protected Area 3.

f 5.

Visible Damage to Structures or Equipment Within the Protected Area Onsite Sustained Windspeed > 75 MPH Explosion Within the Protected Area 2.

Plan Affecting Normal Operation Notification of a Near-Site Release That May Require Evacuation AREAS OF CONCERN FOR SAFE SHUTDOWN

-*=*

6. Turbine Failure Causing Observable Casing Damage Millstone
7. Vessel or Vehicle Collision With Structures or Equipment Required for Containment Building Intake Structure Safe Shutdown or a Loaded ISFSI Confinement Boundary Auxiliary Building Station Transformers
8. Flood Level> 19.7 Feet Mean Sea Level Control Building Emergency Generator Enclosure
9. Flooding in Areas Containing Safe Shutdown Equipment Main Steam Valve Building Fuel Building Millstone Emergency Plan Demineralized Water Storage Tank Revision 56 NOTE: When two or more EAL.s apply, always choose the EAL of the highest incident classifiC(ltion; also always read from top to bottom in each category. ESF Building March 2018 1-7 ofB

MILLSTONE 3 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE

  • IMMINENT - No Turnaround in Safety System Performance is Expected AND Escalation to General Emergency Conditions Will Occur Within 2 Hours INDICATORS I FCB1 I

[I]

FUEL CLAD BARRIER Core Cooling - RED I

I LOSS POTENTIAL LOSS I

I I RCB1 I RCS BARRIER I LOSS I Not Applicable I CNB1 I CTMT BARRIER I LOSS I

Not Applicable MORE THAN ONE BARRIER AFFECTED STATUS TREES 0 Core Cooling - ORANGE I POTENTIAL LOSS I I POTENTIAL LOSS I

0 . Heat Sink- RED AND BOTH of' the Following:

Required Feedwater Flow Can NOT Be Established 0 RCS Integrity - RED 0 Containment - RED

. Within 15 Minutes RCS Bleed and Feed Can NOT Be Established 0 Heat Sink - RED AND Required Feedwater Flow Can NOT Be Established Within 15 Minutes I FCB2 I I LOSS I I RCB2 I I LOSS I I CNB2 I I LOSS I

[I] Core Exit TC Temperatures> 1.200 °F [I] RCS Subcooling < 32 °F Due to RCS Leak (115°F Not Applicable CORE EXIT TC Adverse CTMT)

I POTENTIAL LOSS I

TEMPERATURES I POTENTIAL LOSS I I POTENTIAL LOSS I 0 Entry Into FR-C.1, Response to Inadequate Core Cooling, or FR-C.2, Response to Degraded Core Cooling with RVLMS

.5. 19% ,(Plenum) with OPERABLE 19% sensor (NA if no 0 Core Exit TC Temperatures> 718 °F Not Applicable OPERABLE 19% sensor)AND Core Exit TC Temperatures Do NOT Decrease Within 15.Minutes

\ I RCB3 I I LOSS I I CNB3 I I LOSS I TWO BARRIERS Not Applicable m Rapid Unexplained CTMT Pressure Decrease Following Initial Increase SITE AREA PRESSURE I POTENTIAL LOSS I m No CTMT Pressure Increase When Expectation Exists I POTENTIAL LOSS I EMERGENCY 0 Uncontrolled RCS Pressure Decrease and Increasing 0 CTMT Pressure _a 60 PSIA AND Increasing CHtWcJE-

-- Containment Radiation Monitors 0 CTMT H2 Concentration _a 4%

I RCB4 I I I I CNB4 I I I

! LOSS LOSS m Entry Into E-3, "Steam Generator Tube Rupture" 6NQ Reactor Coolant Leak > Capacity of One Charging Pump

- m. Primary to Secondary > Tech Spec Limits AND EITHER exists:

Nonisolable Steam Release from Affected S/G to environment.

I POTENTIAL LOSS I *- . Prolonged Release From Affected S/G to Environment When Used for Cooldown. (see basis for description of COOLANT 0 Reactor Coolant Leak > Capacity of One Charging Pump

[I]

prolonged release)

Failure of BOTH Isolation Valves AND a Pathway to the ONLY ONE BARRIER AFFECTED LEAKAGE AND ANY of the following:

Entry into E-0, "Reactor Trip or Safety Injection" Entry into AOP 3555, "Reactor Coolant Leak" m Environment Exists Entry Into ECA-1.2, LOCA Outside Containment, Is Required AND Reactor Coolant Leakage is Verified ALERT-0 Entry into AOP 3576, "Steam Generator Tube Leak" I POTENTIAL LOSS I CHARLIE-ONE Entry into E-3, "Steam Generator Tube Rupture" AND Reactor Coolant Leak.s Capacity of One Charging Pump 0 Entry Into ECA-1.2, LOCA Outside Containment I L p I FCB3 I I LOSS I I CLAD m Sustained Valid RE-D4N05A Reading >

  • R/hr. Readings are I RCB5 I I LOSS I I CNB5 I I LOSS I

considered sustained valid when the effects of TIC have dissipated.

Sustained valid RE-D4N05A Reading > 5 R/hr Without RCS m Sustained Valid RE-04/05A Reading > 5 R/hr Without Fuel Clad Barrier Loss. Readings are considered m Offsite Dose Plume Rate _a 5x1 Q-6 Times RE-04A/RE-05A Reading if Coolant Loss is to CTMT UNUSUAL EVENT

[TI Release Inside Containment. Readings are considered sustained valid when the effects of TIC have dissipated.

RADIATION sustained valid when the effects of TIC have dissipated. I POTENTIAL LOSS I DELTA-ONE

[TI At Least 5% Fuel Clad Damage As Determined By Core Damage Estimate

  • I POTENTIAL LOSS I 0 Sustained Valid RE-04ND5A Reading >
  • R/hr.

Readings are considered sustained valid when the

[TI Dose Rate at One Foot from Unpressurized RCS Sample Not Applicable effects of TIC have dissipated. Table 1

_a 50 mR/hr/ml **

0 FCB3 CNB5/RG1 m RE-41/42 Reading >0.040 R)'hr S/D or> 0.060 R/Hr Full Power for> 15 Min. Without RCS Release Inside Containment At Least 20% Fuel Clad Damage As Determined By Core Damage Estimate Time After Shutdown (hrs).:

Fuel Clad Loss Threshold (R/hr)

Containment Loss Threshold (R/hr)

  • See Table 1 I POTENTl~L LOSS Not Applicable I *See Table 1

< 2 *.: 200 BOO

>2to4. 125 500 WATER I FCB4 I I LO~S I I CNB6 I I LOSS I >4to12 50 200 Not Applicable > 12 r LEVEL IT] No CTMT Sump Level Increase When Expectation Exists 25 100 I POTENTIAL LOSS I I I 3

POTENTIAL LOSS 0 RVLMS .S 19% (Plenum) with OPERABLE 19% sensor (NA if no OPERABLE 19% sensor) Not Applicable I FCB5 I I RCB6 I IAny CNB7 I JUDGEMENT Any Condition For Which Judgement Indicates Loss or Potential Loss of Fuel Clad Barrier Due to:

Any Condition For Which Judgement Indicates Loss or Potential Loss of RCS Barrier Due to:

Condition For Which Judgement Indicates Loss or Potential Loss of CTMT Barrier Due to:

Millstone

. Imminent Barrier Degradation Based On Current Safety . Imminent Barrier Degradation Based On Current Safety . Imminent Barrier Degradation Based On Current Safety Millstone Emergency Plan

. System Performance Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate

. System Performance Degraded Fission Barrier Monitoring Capability Making . System Performance Degraded Fission Barrier Monitoring Capability Making Revision 56 March 2018 1-8 ofB Barrier Status Indeterminate Barrier Status Indeterminate

AppendixJ

  • Estimates for Evacuation of the Plume Exposure EPZ The following tables summarize the results of the Evacuation Time Estimate (ETE) prepared for the Millstone Power station in 2012, to reflect the 2010 U.S. Census and the current EPZ evacuation zones. The population estimates are based on the 2010 U.S. Census block level population and housing data.

The ETE statistics provide the elapsed times for 90 and 100 percent, respectively, of the population within the impacted region, to evacuate from within the impacted region.

The various population components are presented for fourteen basic scenarios. The road network for evacuation planning consists of designated routes plus additional roadways needed to accurately simulate conditions during an evacuation.

An analytical tool DYNEV 11, was used to generate the ETEs. The model accounts for road and intersection capacity, variable vehicle loading rates, and the geographic distribution of vehicles entering the network.

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AppendixK APPENDIXK SERO PERSONNEL TRAINING

SUMMARY

AppendixK The following table provides a summary of training, for the qualification of SERO personnel.

Detailed lesson plans and administrative controls are maintained in EP Training Program Guide TR-AA-TPG-2400. In addition, EPA-FAPOl defines specific training requirements. See Reference #4 below Training Summary Table 5-1 Ref.#

Provide an overview of responsibilities and actions that occur during an 1 emergency. This includes classification system, notifications, communications, Station Emergency Response Organization, Emergency Response Facilities and equipment. This lesson may be computer based training and is used for initial and continuing training.

Provide hands-on instruction for the operation of the OFIS computer program. 2 Provide instruction on the function and operation of the Emergency Notification 3 and Response System, in addition to providing instruction on the various reports available.

Provide practical application of specific emergency duties and responsibilities as 4 well as hands-on experience with emergency equipment during the conduct of a MP training drill, facility walk-through or on-the-job training. EPA-FAPOI Provide overview of meteorological conditions and their impact during an 5 emergency, including equipment and resources available to access this data.

Provide training on the event based EAL tables, including structure and practical 6 applications using scenarios .

Provide familiarization training on the event based EAL tables. 7 Identify NRC initiatives in the area of accident management and familiarize 8 students with types of severe accident phenomena.

Provide SERO position specific duties and responsibilities as delineated in the 9 Emergency Plan and procedures.

Explain basic principles of meteorological analysis and forecasting, including 10 interpretation and communication of data.

Provide methods for performing containment curie level estimation and for 11 assessing core uncovery projections.

Provide methods for performing radiological dose calculations. 12 Demonstrate operation of the applicable computer programs for radiological dose 13 assessments.

Provide training on process for preparing protective action recommendations to the 14 State of Connecticut.

Provide training for performance of on-shift radiological dose calculations using 15 computer programs .

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