ML16138A204

Millstone, Units 1, 2, and 3 - Revision 053 to MP-26-EPI-EPMP, Emergency Plan

ML16138A204
Person / Time
Site:	Millstone
Issue date:	05/05/2016
From:	Stanley B L Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
MP-26-EPI-EPMP, Rev. 053
Download: ML16138A204 (186)

Text

{{#Wiki_filter:TIPCK02 To Facility Address From Date/Time DOCUMENT CONTROL . DESK MP Department U.S. NUCLEAR REGULATORY COMMISSION DOCUMENT CONTROL DESK (7108) WASHINGTON, DC 20555-0001 CONTROLLED 05/05/16 11:38 DOCUMENTS Trans No. 000155179 Transmittal Group Id: 1610665 Total Items: 00001 Item Facility Type Sub Document Number I Title

• 0001 MP PROC EP MP-26-EPI-EPMP Sheet MILLSTONE POWER STATION EMERGENCY PLAN Revision 053 Please check the appropriate response and return form to NDS Bldg 475/3 Millstone Station or Fax to 860-440-2057.

§ All documents received. Documents noted above not received (identify those not received) . I no longer require distribution of these documents. Date: PASSPORT DOCUME TRANSMITTAL rrni Doc Date Copy # Media Copies 99 p 01 ,Dominion"' Administrative Procedure or Guidance and Reference Document Approval AD-AA-101 -Attachment 4 Page 1 of 1 1. Document Number: MP-26-EPl-EPMP

4. Title: . Millstone Power Station Emergency Plan 5. Requestor(s)

Print Name(s) I Bryce Wilkens 8. Document Request D New 181 Revision 9. Applicable Nuclear Station(s) Millstone 181 10. Reason and Brief Descriptio{l of Change: Modified U3 EAL GU1 and TU2 to include ISFSI 11. Records Retention Requirements Affected?

2. Revision:

3. Document Type: 053 181 Administrative Procedure D Cancel North Anna D 6. Date 4/16/16 D Supersede SurryD 12. Change Management:

0GARD 7. Requestor Phone 0973 D Temporary D Yes (Complete NRRS form from RM-M-101) 181 No Attach Appropriate Pl-M-4000 Attachment(s)

13. Level of Use: D Continuous Use D Reference Use 181 Information Use D Multiple Use Fleet Approval 14. Fleet Approval Required by: (Check one box only. Enter Peer Group Name, i.f applicable)

15. Printed Approver Name i .. "NIA 0 Peer Grou OR D Functional Area Mana er FAM t-l/A . . . l=S=i=te=A=p=p=ro=v=a;;::f

. =======:.======

.* .. -*= 18. Implementation Prerequisites: (Items in addition to those listed on Document Traveler or Change Management Plan) None 19. Implementation Prerequisites Reviewed-.Pro dl (..). :£-r*o;.,;

21. Check Nuclear Station(s) for Which Document is being Approved for Implementation.

Millstone 181 North na D 25. Facility Safety Review Co 1 ee Required?

26. Facility D No 181 Yes 28. Site Vice President Required?

29. Site Vice President)

Print Name/Signature 181No D Yes N/A 20. Date c.1 /rf'/rr NOTE: The individual s ostin a new or revised document to EDMS are res onsible for ensurin Nuclear E-Forms ls u dated. 31. Nuclear E-Forms Updated for Site(s)? 32. Nuclear E-Forms Updated Print Name/Signature

33. Date D MP D NA D SU 'lg] N/A 34. Document.

Number: MP-26-EPl-EPMP

35. Revision:

053 36. Effective Date Key: GARD-Guidance and Reference Document, EDMS-Electronic Document Management System 37. Expiration Date N/A Form No. 728620(0ct 2014) Do111inion Emergency Plan Title: Millstone Power Station Emergency Plan Revision Number: Effective Date: 53 5/12/16 Revision Summary:

• U3 *EAL GUl, added item 2 "Fire affecting a loaded ISFSI confinement boundary NOT extinguished within 15 minutes"
• U3 EAL TU2, added "or a Loaded ISFSI Confmement Boundary" to item 7, TABLE OF CONTENTS Section Page L. t fA di , . .. is o ppen ces ........................................................................................................................

vn List of Tables ............................................................................................................................... viii List of Figures ..............

...................................................................................................................

x ' 1. Concept of Emergency Operations ................ 1-1 1.1 *Description of the Millstone Emergency Planning Zones ..................

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1:.1 1.2 Interrelationships ofState/LocaVLicensee Emergency Plans ........................................ 1-2 1.3 Actions ................................................................................. , .......................................... 1-2 1-.4 Assistance .........

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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 (Re.served) ....................................................................... 3-1 4. Classification System .............................................................

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4-1 5. Emergency Response Organization ..................................................................................... 5-1 5.X** * . P6sitions ................

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........ : ..............

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._;._ .. s:.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 .. '. .................

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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 FirstAidTeam. .................................................................................................... 5-5 i Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 5.2 Minimum Staffmg 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 (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.l2-E('.ff i)Zc) ...........

, ;, ...............................

........ ;.:.'.i:.;5-J***:

.. * ,_. _,, /' 5.2.13 OSC -Assistant Radiation Protection Supervisor (ARPS) ...................... ...... .-:. 5-8 5:2.14 Emergency Information Specialist (EIS) .................................................

.........

5-8 5.2.15 Chief Technical Spokesperson (CTS) ................................................................ 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 ...................

.. ***************************************

5-9 5 .2.23 Corporate Support Director ................................................................................ 5-9 ii Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 5.3 Full Staffing Positions .................................................................................................... 5-9 5.3.l 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 ..........................................

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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 ....... ,.-:;* ... :; ........................ .-... ,,:.,fr:.: .. :i ...... ; 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.l6 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.l Corporate Support Coordinator ........................................................................ 5-12 5 .4.2 Corporate Plant Information Coordinator ........................................................ 5-12 5 .4 .3 Corporate External Affairs Manager ................................................................ 5-12 iii Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 5.4.4 Corporate Emergency Plan Specialist.. ............................................................ 5-12 5.4.5 Corporate Executive Spokesperson (CBS) ....................................................... 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 ********oa*o****************************11*****0*********0*********************************0***111**********0** 6-=-1 6.1 Notification and Activation of Emergency Organizations ............................................. 6-1 6.2 Assessment Actions ........................................................................................................ 6-3 6.2.1 Initial Assessment. .....................................................................

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6-3 6.2.2 Protective Action Recommendations (P ARs) .................................................... 6-3 6.2.3 Dose Assessment ................................................................................................ 6-4 r 2 4 <1,.':hc.*dc,."'gy . * ... -* ** 6-6 t), * -.,,, \.*.

• .* .Ll..Llti ,v '.*'. . *
  • • • ......... .* ... * ** * * *.** *:-*** ****.** . . ...
• ' . . . . -6.2.5 Sec*:mdaty Dose Assessment..

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• ......................................................

6-10 6.3 Corrective Actions ...............................................................................

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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 Detennination ........................................................ 6-14 6.5 Aid to Affected Personnel ............................................................................................ 6-15 6.5.l Exposure Control Guidelines**:******************** .................................................... 6-15 6.5.2 Emergency Exposure Control Guidelines for Off-Site Personnel.. .................. 6-15 iv Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 6.5.3 Decontamination ...................................................

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6-16 6.5.4 First Aid ..............................................

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6-16 6.5.5 Medical Transportation ...............................................

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6-16 6.5.6 Medical Treatment ........................................................................................... 6-17. 6.6* Public Information ........................................................................................................ 6-17 7. Emergency Facilities and 7-1 7.1 Control Room .......................................... ......................................

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7-1 7.1.l Normal Operations .............................................................................................. 7-2 7.1.2 Alert and Notification .....................................

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7-2 7.1.3 Communications ....................

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7-2 7.2 Emergency Operations Facility ...................................................................................... 7-3 7.2.1 Function .........................................................

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7-3 7:2.3 Structure and Habitability .......................... , ......... , .............................

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7-3 .* 7.2.4* Layout ................................................................................................................. 7-3 -7.2.5 Communications ................................................................................................. 7-4 7.2.6 Power Supplies ............................. .-....................................

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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 ..................

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7-4 7.3.l Function ..................

• ............................................................................................

7-4 7.3.2 Location .....................................................

• ... .-.....................................................

7-5 7.3.3 Structure and Habitability .................................................................................. 7-5 7.3.4 Layout .......................................................

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7-5 7.3.5 Communications ................................................................................................. 7-6 v Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS

• Section 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 .............................................

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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 Emergency Equipment .. : .................................

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7-7 7.5.1 Emergency Response Data System (ERDS) ...................................................... 7-8 7.6 Security Posts ..............................................................................................................

.. 7-8

., ..... '. .. ,;., *. .-: .. ....* ..*. ...................

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....... . .:. *. : .** , ..*...*...

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.... --*: *-7.8 *Alternate

.ecation

... : ...... : ....... ........................................................

.....

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7-8 *'***", 7 .9 Communication Systems ................................................................................................ 7.:.9 7.10 Assessment Facilities ...................................................................................................... 7-9* 7.11 First Aid and Medical Facilities ....................................................................

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7-9 7.12 Damage Control Equipinent ......... .. '. .........................................

....... ; ..........................

7-10 7.13 Meteorological Data ................................................................................. 7-10 7.14 Innsbrook Corporate Support Center (ICSC) ............................................................... 7-10 8. Maintaining Emergency .... ................................. ., ........................................ 8-1 8.1 Training ....................................................................................... ., .................................. 8-1 8. 1 .1 SERO Training ................................................................................................... 8-1 8.1.2 Off-Site Emergency Response Training ..................................

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8-2 8.1.3 Additional Emergency Preparedness Training ................................................... 8-2 vi Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 8.2 Tests, Drills, and Exercises ............................................................................................ 8-3 8.2.l 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 .......................................... 8-7 8.4 Public Information Programs .................................................................................. , ...... 8-7 8.5 Media Information Program ........................................................................................... 8-8 9. *Recovery

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • ci******a*ci***********ao*o************o*o***o*o*********a****1100***********************

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 .'3f .. ,, ..... : .. ., ... ? ....... .......................... ,.... ................. , *:*.. ..

9.2.5 Manager

of Radiation Con\rol/Radwaste ...................

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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 9.2.9 Licensing Department .....................

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9-3 9.2.10 Millstop.e Representative in the SEOC and Joint Media Center ........................ 9-3 vii Millstone Station Emergency Plan Revision 53 Apri12016 ,;_\, .. 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 .........................

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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 ....................................................................... 1-1 Appendix J -Evacuation Time Estimate: Plume Exposure Pathway ............. .......................... J-1 Appendix K-SERO Persorniel Training Summary ................................................................ K-1 viii Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section LIST OF TABLES 1-1 Off-Site Host Community and Reception Centers .......................................................

........ 1-4 2-1 Supporting Plans and s*ources ...............................................................................................

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:i J;ime Estfrnat.:1 Summary: ............................

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.. ,.; ....

ix Millstone Station Emergency Plan Revision 53 April2016 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-la Notification ofE!llergency Response Organizations

..... ." ................................................... 7-12 7-lb NRC Emergency Notification System and Health Physics Network ................................ 7-13 7-1 c 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 EvacuationRoutes.C-2 C-2 Locations

• of On-Site and Off-Site Radiological Monitoring Stations ......................

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C-3 C-3 Map of Millstone 10 Mile Emergency Planning Zone ......................................................

.. C-4 C-4 :W.i'ariofMills-i?nne JO Mile Emergency' Planning Zo11e*.; .. , ... ... ;* .*. :, ..... ;-,:,;i, * .-** , .. **. ;.-;; **** ;;, ** ;;;:: *** :c .. 5 . -' "C-5 Map of Millstone Station Evacuation Routes .......................................................................

C-6 E-1 Millstone Emergency Equipment Summary .......................

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E-2 . F-1 Diagram ofTSC I OSC Layout .............................................................................................. F-2 F-2 Diagram of Emergency Operations Facility ..............

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F-3 F-3 Diagram of OSC Assembly Area Layout ....................................... _, ...................

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F-4 x Millstone Station Emergency Plan Revision 53

• April2016

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 50-mile planning zone for the Ingestion Exposure Pathway (IPZ). Millstone Station occupies approximately 500 acres and is located 3.2 miles west-soutl1west 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 50-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 ..agreed Massachusetts shci.11 be excluded frcr1T.* t:hr. . Millstone

.; * ':"'* '" ** *** *** . ,

• 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). In accordance with 10CFR50.82(a)(l)(i) and IOCFR50.82(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 53 April2016

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 focal 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 co_ntact 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 identify resources for each organization. Local radiological. emergency fil'c\t .. r.:o--vie.wed and, u::pi;r.o\:!ed* appropriate

• .. , ,*
• tocal programs training and pr,.:ciodk drills ot ex'!rdses;*
• 1.3 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 re$ponse 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, mid assessment of accident consequences. The licensee will classify the incident in accordance with federal guidelines and the State of Connecticut Nueiear Incident Classification Scheme. Tµe licensee will notify designated Connecticut and New York state and local officials and licensee personnel, as appropriate, within 15 minutes of an incident classificatfon. 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 York, 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. 1-2 Millstone Station Emergency Plan

• Revision 53 April2016 After initial classification, the licensee ensures that plant conditions are evaluated and updated information or event reclassification is completed as necessary.

1.4 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 :@. .. *T°l;fl:S program; as described in Se-2tion* for the meG.fa .. and provides .general radioiog:7_;ic;;,and*-

• • * ... emergency response infonnatio,;.1:
• ,
• 1-3 Millstone Station Emergency Plan Revision 53 April2016 . . '

Table 1-1 Off-Site Host Community and Reception Centers Local Community East Lyme Fishers Island, New York Groton, City of Groton, Town Ledyard Lyme Montville New London Old Lyme ,. :*. Host Community-Reception Facility New Haven -Southern Connecticut State University Moore Fieldhouse Windham -Windham High School Norwich-Norwich Technical High School Norwich -Norwich Technical High School Storrs - of Connecticut Fieldhouse New Haven -Southern Connecticut State University Moore Fieldhouse East Hartford -East Hartford High School Windham -Windham High School New Haven -Southern Connecticut State University Moore Fieldhouse

East Hartford,.

F.:;tst-Hartfot<l High Scfi.o.::>f. 1-4 Millstone Station Emergency Plan Revision 53 April2016 Figure 1-1 Emergency Response Organizations Responsibilities A. Licensee Responsibilities

1. Classification of event. 2. 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 ofNew 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 I. Activation of State EOC and Joint Media Center at SITE AREA EMERGENCY or higher level incident notification (standby at ALERT). 2. Notification of host comm.unities.

3. Notification of Rhode Island and New York (SO-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. Impler::J::ireio.f*

. *>1'

,>t;la '?r.tg.

<< fo::: ?*. r--:, ... \ . : ..... 1. Activation ofEOCs 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 IPZ States I. Activate EOCs at SITE AREA EMERGENCY (Standby at ALERT) level. 2. Monitor food pathways.

3. Implement ingestion pathway protective actions. 1-5 Millstone Station Emergency Plan Revision 53 April 2016

1-2 Responsibilities of State and Local Agencie'.i!. For The Various Incident Classifications i .* UNUSUAL EVENT* ' ALERT**

• All agencies acknowledge
  • All agencies Standby _ SITE AREA EMERGENCY 1 --GENERAL EMERGENCY J I Governor Direct actions of all State agencies.

Coordinate media releases. Declare a State of Emergency as necessary and assume overall command of State and local emergency response activities. I Department of Energy and Environmental Protection -Division of Radiation Conduct independent assessment of the incident and/or respond with assistance. Recommend public -protective actions, as necessary, I Deploy radiological monitoring teams to affected areas, as necessary, for radiation measurements. NOTE: In case of RADIOACTIVE MATERIALS INCIDENT OR GENERAL INTEREST EVENT only the Department of Energy and Environmental Protection will be notified per the State RERP. 1-6-,?, Divisi' on Erner Manage Homeland ger;.;c_ .. ::, . **:It menHf.!.n d rity Disseminate emergency data to local, State, and Federal agencies. Maintain communications with towns and respective DEMHS Area offices.

• Coordinate services, material support and manpower to the towns. Activate State EAS,_ necessary.

Provide radiatio.n monitoring support to the townsJ Notify and record "tr1'e actions of other State ag9_r;Gles. . ***/'\ :* ;* Activate host I Local Chief Executives Execute and direct emergency protective actions within their jurisdiction. Public Alert (siren) system activation. Further duties as defined in RERP. Millstone Station Emergency Plan * * * -:_ Revision 53 ik -: April 2016 -.:"{ . : I Department of Public Safety Serve as backup communications link between the site and State EOC. Provide traffic and access control. Assist local police in evacuation of residents in affected areas. Figure 1-3 Licensee Emergency Response Facility Responsibilities (ALERT or higher event classifications) Control Room

• Initial incident classification 2
• Implement mitigation actions
• Implement corrective actions
• Declare incident classification changes, as necessary
• Perform notifications, develop and transmit incident reports 2
• On-Shift Dose assessment
• , Initial 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 (P ARs) 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 * . , . fr. Provide !nput to Director of . . ,(h,. ,?i'i:r.;ritize TSC/OBC *assessment and repair activities in coordination
• ...
• o , 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 53 April2016

.*

2. Applicability and 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 1. State of Connecticut Radiological Emergency Response Plan 2. State Agency Procedures

3. New York State Radiological Emergency Preparedness Plan 4. State of Rhode Island Ingestion Exposure Pathway Emergency Response Plan 5. Local Community Procedures:

• Town ofEastLyme
• City of Groton " Town of Groton of :fishel,:* (NY) '"' Town of Ledyard o Town of Lyme " Town of Montville
• City ofNew London
• Town of Old Lyme
• Town, of Waterford

6. Host Community Procedures:

• Town of East Hartford
• UCONN I Storrs
• City ofNew Haven
• City ofNorwich
• TownofWindham

7. Lawrence and Memorial Hospital Master Emergency Preparedness Manual, Section II, Part K, Radiation Accident Plan 8. Treatment and Decontamination of Radioactively Contaminated Patient( s) at Middlesex Hospital 9. Manual of Protective Action Guides and Protective Actions for Nuclear Incidents Source State of Connecticut Division of Emergency Management and Homeland Security, State .Anllory Hartford, Connecticut State of Connecticut Division of Emergency Management and Homeland Security, State Armory Hartford, Connecticut New York State Disaster Preparedness Commission Albany, New York Rhode Island Emergency Management Agency Cranston, RI Local Community Emergency Management Agencies Local Host Community Emergency Management Lawrence and Memorial Hospital New London, Connecticut

• Middlesex Hospital Middletown, Connecticut EPA-400-R-92-001 U.S. Environmental Protection Agency 2-1 Millstone Station Emergency Plan Revision 53 April 2016 '1':-***

3. Section Intentionally Left Blank 3-1 . . '**-:l '-'* .. ( Millstone Station Emergency Plan Revision 53 April2016

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 mcidents be assigned a state posture code at the time of classification. The state plan also defmes 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 ate 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 L The emergency classificati9n_ nnd action level ' . . °i' .;'\

• -o; A '" ,.;. '.,\: < LJ '* . . . * . . . ,., . . . . , * .t'(.::> *,'-I: -'l.iD){ >>J requlremeut8;

.. _ . . . *.. ... . --.. 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 in 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. 4-1 Millstone Station Emergency Plan Revision 53 April2016

• Table 4-1 Unusual Event -Licensee Actions Class Description 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. No releases of radioactive material requiring 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 Corpo:i;ate 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.

8. A close-out 1erYorH2 provided with verbal summary to off-site authorities, foli:owed:by a -written summary to the NRC as required by 10 CFR 50.73, as appropriate.

4-2 Millstone Station Emergency Plan Revision 53 April2016 Table4-2 Alert -Licensee Actions Class Description ALERT (State Posture Code: CHARLIE-ONE): Events are in process or have occurred which an actual or potential substantial degradation of*the level of safety of the plant. 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 Innsbrook 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 pltime exposure EPZ. s.* Activation ofthe Station Emergency Response Organization (SERO) and appropriate emergency response facilities (ERFs) 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

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 slll111ilary to the NRC as required by 10 CFR 50. 73, as appropriate.

4-3 Millstone Station Emergency Plan. Revision 53 April2016 Table4-3 Site Area Emergency -Licensee Actions . Class Description 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. 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 Connectjcut and New York state agencies and local communities (responsible locatofficial) within the plume exposure EPZ. . 6. Activation of the Station Emergency Response Organization (SERO) anq ,PRFs . ' . *-* .* .. --*

! -.**i -: 7. 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* provided to off-site authorities.

12.

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 IO CFR 50.73, as appropriate.

'1 .** -;*_,. 4-4 Millstone Station Emergency Plan Revision 53 April2016

• • .*.:...

_.,._, Table 4-4 General Emergency -Licensee Actions Class Description GENERAL EMERGENCY (State Posture Code: ALPHA [significant radiation release] or BRA VO): Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. 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, l:!-S_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.-. ., '.' Establisr:tconnnunications with the SEOC iri Hartford, when activated.

--.. *.. 8: Notification of the NRC. 9. DepIOyment 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.

-.. ' 4-5 Millstone Station Emergency Plan Revision 53 April2016

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 CFR 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 anaiysis 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 'n Table 5-1. The DSEO has the discretion to relieve the activatiJn with :less. than, minimum staffing when the necessary specified positions are in accordance with NUREG-0654, Pianning '3tti.ndmi:t 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 hours. 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 staf.f, may be activated, as 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 m Appendix D, as applicable. This section also includes brief descriptions of the state, local and other organizations that would provide assistance upon request. 5-1 Millstone Station Emergency Plan Revision 53 April2016 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: e Shift 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
• FiJ;e Brigade .
• First Aid Team The minimum staffing management positions include the following:

s Director of Station Emergency Operations (JI. Assistant Director, Techtricctl St:tiV.ort fuhit i;-3) '*

• Manager of Technical Support Center
• Manager of Radiological Consequence Assessment
• Manager of Radiological Dose Assessment
• Manager of Communications (Unit 2, 3) *
• Manager of Operational Support Center (2 Positions)
• Chief Technical Spokesperson
• Nuclear News Manager
• Manager of Resources
• Emergency Information Specialist
• Corporate Support Director 5-2 :r, *, * . ,:.-:: ' Millstone Station Emergency Plan Revision 53 April2016

' .1 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 After being relieved .. by aIJ.9ther qualified, ........... , .. . the Shift Manager becomes the .{iontrof Rc-0n:i.. . 'Ope.rations (MCRO). The following CRDSEO .responsibilities cannot be*

• Event classification 4
• 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.

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 1. 5-3 Millstone Station Emergency Plan Revision 53 April2016 For a Umt 1 event, the Unit 2 SM/CFH functions as the CRDSEO. 5.1.2 Shift Technical Advisor (STA) The STA is responsible for the analysis of operational data 5. 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 The Emergency Communicator 1s 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 relate.cl fimctions in a;*'3c-rdance v1itL unit

• procedures, and as direcfod l'ij

* ** The PEOs

• provide . 'basic on-shift mechanical and 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 SMIMCRO. The Security Shift Operations Supervisor is assisted by security personnel in providing site access control and accountability. 5 This position is not reqllired for a pennanently 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 53 April2016

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 injuries.

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 to respond to the specific -; ... ,,* .. >_,.*, ....

• % minu:tes of facility activation*.

The following DSEO u;t\-: **2'-"<'1 1'-f 4elegated:

• 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.' 5-5 Millstone Station Emergency Plan Revision 53 April2016 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 8 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
• Evaluating conditions for directing entry into Severe Accident Management Guidelines

5.2.3 Manager

of Technical Support Center (MTSC) The MTSC reports to the ADTS. The MTSC analyzes operating data and provides support to the ADTS, MSRO, and the M.Of:C. .. .. ,.,*> ;:taff and Management Yearn report to the MTSCand

's

;;:U-ffifirlli';'

.* ,;: *;"* * *.

• assessment functions.

The MTSC is assisted by a mechanical engineei*, 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 assi.st 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 5-6 Millstone Station Emergency Plan Revision 53 April2016
• Approving Potassium Iodide (Kl) issue to emergency personnel assigned totheADEOF
• Developing, recommending and updating off-site P ARs 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 Kl 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 Radi?logical Communicators (RAD COM). ". : ,,, .,, .. ,. . , ._,; .... ;; .. ,: .. ,. , , .

• I:_<&u1:ag*'!'t-Qf Dose Asse.ssment . : -,,,' .. ** ,_;;.<: :,:y.:* *>-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 Radiologic;al 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. 5-7 Millstone Station Emergency Plan Revision 53 April2016

• 1., "'i, _,. ..

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) riTt::.1;E;:i!G to DSEO. The EIS assists the .. fogging &nd provides other administrative assisknr.*.,.:;. as * * ' * * .:' * . * .: needed. 5.2.15 Chief Technical Spokesperson (CTS) The CTS 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 CTS 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 CTS 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 53 April 2016 5.2.18 Technical Support 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, I&C Technician -.. : .,.. *: .. Th h . 1 . . d )'&rt T 1..-. * ' .. "' 1*. ... C"' <.\ ;{ e mec amc, e ectrician, an J: -' . ecrn11c1ru1 repmt 1.0

• ' .: .. *; *:*
• are responsible for assessment, rej_)air, and cortective
• **

5.2.23 Corporate Support Director 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 c:Roc 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 CTS and provides the CTS with technical information as required. 5-9 Millstone Station Emergency Plan Revision 53 April2016

' *.. .,\

5 .3 .3 Meteorological The Meteorological Assistant reports to the MRDA and provides meteorological data interpretation, calculations and long term meteorological. information to support dose assessment activities.

5.3.4 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 CHETS Operator reports to the MRCA. to the and assists the radiological assessment te'anr-in dose calculations.

5.3.8 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. 5-10 Millstone Station Emergency Plan Revision 53 April2016 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. 'i. ?., 7--0* T,.*,::hnical Rri(?>fer (TB) The TB reports to the Media Center Liaison and is responsible for providing technical, 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 briefmgs. 5.3.17 Offsite Monitoring Facility (OMF) 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. 5-11 Millstone Station Emergency Plan Revision 53 April2016 5.3.19 Station'Emergency Planning Liaison (SEPL) The SEPL reports to the CTS and is responsible for providing support to SERO and state personnel in the SEOC. 5 .4 Corporate Support .. 5.4.1 Corporate Support Coordinator

• 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
• Monitors the Operations Network and OFIS
• Provides the Innsbrook Corporate Support Center (ICSC) with technical . perspective

.1) . 5.4.3 *Corporate External Affairs Manager

• 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
• Provides assistance with facility operations and interpretation of the Millstone Emergency Plan 5-12 Millstone Station Emergency Plan
• Revision 53 April2016

5.4.5 Corporate

Executive Spokesperson (CES)

• Assumes responsibility as spokesperson from the CTS. If it is determined that a CBS 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 agenciesJ 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

• of

&gerc.cit:s may also be .Details of the expected are cmitained in lett-ers uf * ,

• agreement.

The letters are updated annually cir 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 tci an accident.

The licensee maintains work centers for both FEMA and the NRC at the 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. 5-13 Millstone Station Emergency Plan Revision 53 April 2016 Major Function-al Ar.ea Major Tasks Unit Operations and Responsible for safe operation assess. of operational of the unit including the aspects, assessment of implementation of normal & off-normal operational emergency operating aspects procedures Emergency Direction and Assume command and control Control, Support of of Station Emergency Operational Accident Event 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 Technical Spokesperson 5-14 Table 5-1 Station Emergency Response Organization Normal Position/Title<n> Emergency Position/Title Shift Manager (SM)/CFH Manager of Control Room Operations<q) Shift Technical Advisor, Station Duty Officer Security Supervision Shift Technical Advisor Shift Technical Advisor (STA) Unit Supervisor (US) us Control Operator (CO) co Plant Equipment PEO Operator (PEO) (Unit 2,3) Unit 2 Operator (Unit 1 responder and Unit 2 PEO Appendix R responder) Manager, Nuclear Director of Station Operations, Shift Emergency Operations Managers/CFH Directors, Managers Directors, Managers, Chief Technical Nuclear Specialist Spokesperson Licensing, Technical Assistant Engineers/Process Leadership, Maintenance Millstone Station Emergency Plan Revision 53 April 2016 Emergency Location Affected Unit CR Affected Unit CR Affected Unit CR Affected Unit CR . Affected Unit CR Affected Unit CR Unit2 CR Affected Unit Control Room<m> EOF SEOC/Joint Media Center SEOC/Joint Media Center On-Minimum StaffinQ *

• Full Training Rad Resp Shift 30-60 60 Staffing (b) Summary Worker Qua I Minutes Minutes (Refer to App K) 1 (d, i) 1,4,6,9, 14 YES YES 1 (a) 1,4 YES YES 1 ca. i) 1,4 YES YES 1 (i) 1,4,6,9,14 YES YES 2(i) 1 YES YES 2(i) 1 YES YES 1(i) 1 YES YES 1lffiJ 1,4,6,9, 14 YES YES 1 1 toJ 1, 4, 9, 14 1 1,2, 9 Major Functional Area Major Tasks Public Information Supervise public information activities.

Disseminate 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. Support coordination with CT Public Information Staff. Support public _information effort with 1eqhnical info(mation. Support public information effort with radiol.oaical information. Radiological Calculations Assume command and control and Event of internal/external Communications communications, radiological 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 Radiation Controls EOF, supervise Decon Facility Notification and Notify licensee, corporate, Communications federal, state and local officials. Communicate with CR. Activate EROS Notification and Coordinate technical data Communications communication between EOF, (Technical) CR, TSC/OSC, and qovernment aqencies. Technical Information Obtain plant data for Communications Emergency Response Facilities and Technical Assistant at SEOC as required. 5-15 Table 5-1 Station Emergency Response Organization Normal Position/Title<nJ Emergency Position/Title Various Nuclear News Manager Senior Executive Corporate Support Director Various Media Center Liaison Various Technical Briefer Various Radiological Briefer Managers, Supervisors Assistant Director Emergency Operations Facility HP Tech EOF HP Tech Work Control SRO Emergency Communicator STA/Security Supervision SDO Work Control SRO Emergency Communicator SRO TSC-Shift Manager/CFH Work Control SRO Emerqencv Communicator Operator Training Staff Manager of Communications Unit Personnel, Operator Technical Information Training Staff Coordinator Millstone Station Emergency Plan Revision 53 April 2016 Emergency Location SEOC/Joint Media Center ICSC SEOC/Joint Media Center SEOC/Joint Media Center SEOC/Joint Media Center EOF EOF Unit CR Unit CR EOF TSC/OSC Unit CR EOF EOF On-Minimum Staffinq *

• Full Training Rad Resp Shift 30-60 60 Staffing (bJ Summary
• Worker Qua I Minutes Minutes . (Refer to App K) 1 tn)(o) I 1, 4, 9 1 (h) 1, 4, 9 1 1, 4, 9 1 1, 4, 9 1 1, 4, 9 -. 1 1,4, 7, 9, 14 1 1 YES YES 1 \CJ 1,3,4, 9 YES YES 1 1, 4, 9 YES YES 1 1,3,4,9 YES YES 1 (9) 1, 4 YES YES 1,3,4,9 YES YES 1(9) 1 1,2,4,9 ' 1 (9) 1 1, 2, 4, 6 or 7, 9 Major Functional Area Major Tasks Administrative Support Provide administrative support to the DSEO. Maintain log for the DSEO. Facilitate information exchange with other emergency facilities.

Technical Data Ensure needs for plant data Communications and information are met. On-Site Radiological Direct On-site RMTs, sampling Accident Assessment program and radiation protection program. Perform dose assessment calculations. Radiological Surveys HP coverage and station surveys for repair, corrective actions, Search and Rescue, and fire-fighting. Personnel monitoring; and dosimetry . issue .. **

• Radiological Protection Radio Chemistry Assessments I Initial Dose Ass*essment Access control* Off-site Radiological Dose Coordinate off-site sampling Assessment program, dose assessment and core damaqe assessment Dose Calculations Dose Assessment,*

Radiological Calculations Radiological Control Within Provide radiological controls the OSCAA within the TSC/OSC, OSC AA and provides radiological support for emergency teams dispatched from the OSC AA Radiological Radio Deploy RMTs, collect data. Communications Radiological Surveys Off-site Surveys Meteorological Services Provide meteorological data interpretation, calculations, long term meteoroloqical information Environmental Services Plume and Ingestion Pathway and/or Health Physics Sampling 5-16 Table 5-1 Station Emergency Response Organization Normal Positionrritle<n) Emergency Position/Title Various Emergency Information Specialist Operator Training Staff Control Room Data Coordinator Radiological Protection Manager of Radiological and Waste Services Consequence Assessment HP Ops Support HP Ops HP Supervisors HP Technician RMT#1 Chemistry Technicians Chemistry Technicians HP Technician RMT#2 (A,B,C,D) Engineers/Manager-Manager of Radiological Chemistry Supervisors Dose Assessment Engineers/Analysts/ Radiological Assessment Specialists Engineer Chemistry Supervisors, Assistant Manager of Chemistry Training Radiological Dose Assessment Engineers/Analysts/ Specialists HP Assistant Radiological Protection Supervisor Site Services, HP Services Field Team Data Coordinator HPNarious RMT #3-4-5 and Drivers Environmental Specialists Meteorological Assistant Environmental/HP RMT #3-4-5 and Drivers Personnel and/or HP REMP Tech Millstone Station Emergency Plan Revision 53 April2016 Emergency Location EOF Affected Unit CR TSC/OSC Affected Unit CR CR, OSCAA NAP/SAP EOF EOF EOF OSCAA EOF EOF EOF EOF On-Minimum Staffing** Full Training Rad Resp Shift 30-60 60 Staffing (b} Summary Worker Qua I Minutes Minutes (Refer to App K) 1 : 1, 4, 9 2\9) 1, 2, 4, 9 YES 1 1, 4, 9 YES 1 (d} 1 1, 4 YES YES 2<d.f) 1, 15 YES YES *'. 4 1, 4 YES YES 1 1, 4, 5, 7, 9, 11, 12, 13, 14 2 1, 4, 5, 9, 11, . 12, 13 2* 1, 4, 5, 7, 9, 11, 12, 13, 14 1 1, 4 YES YES 1 . 1, 4, 5, 9 2 4 1, 4 YES YES 1 1, 4, 10 2ui YES Major Functional Area Major Tasks Contingency Offsite Set up and operate Offsite Contamination Monitoring Monitoring Facility for Station Staff Accident Assessment Assume command and control Management and of the station operating, Consequence Mitigation technical assessment and repair staff. Recommends chanqes to classifications Unit System Engineering Responsible for analysis of operations data, development of procedures, *recommend repair, and corrective actions Assist Manager of Technical Support Plant System Engineer Assist of.Technical Repair and Corrective Support.Provide accident Action analysis

• Repair and Corrective Evaluation, repair, and Actions corrective actions Operational Support Coordinate on-site activities and personnel Resource Acquisition

& Coordinates requests for 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 5-17 Table 5-1
• Station Emergency Response Organization Normal Pos'ition/Title<n>

Emergency Position/Title Radioactive Material OMF Staff Technician Manager-Operations, Assistant Director, Supervisor Nuclear Shift Technical Support Operations, Supervisor-Operator Training Manager-Engineering/ Manager of Technical Supervisors, Engineers Support Center Manager-Site Services Mechanical Engineer TSC-ME Electrical Engineer TSC-EE Reactor Engineer TSC-RE Nuclear Instrument Generation Test Services Technician (GTS) Specialist Safety Analysis, Nuclear Accident Management Fuel Engineering Team-Leader Safety Analysis, Nuclear AMT-Thermal-Hydraulic Fuel Engineering Engineer (T-H) Manager-Maintenance Manager of Operational Supervisor Support Center Mechanic Mechanic Electrician Electrician l&C Technician l&C Technician Supervisor-Maintenance OSC Assistant Supervisor-Maintenance OSC Assistant Various Manager of Resources IT Personnel None Millstone Station Emergency Plan Revision 53 April2016 Emergency Location EOF TSC/OSC TSC/OSC TSC/OSC TSC/OSC TSC/OSC OSCAA TSC/OSC TSC/OSC TSC/OSC, OSC AA OSCAA OSCAA OSCAA TSC/OSC, OSC AA TSC/OSC, OSC AA EOF Millstone Station On-Minimum Staffing** Full Training Rad Resp Shift 30-60 60 Staffing (bl Summary Worker Qua I Minutes Minutes (Refer to App K) 5tPJ. 4 YES 1(9) 1 1,4,6, 8,9 YES 1 1 1,4, 7,9 YES 1 1 1, 2, 4 YES 1 1 1,2,4 YES 1 1, 2, 4 YES 1 1 YES 1 1,2,4, 8 YES 1 1, 2, 4 YES 1 1 1, 4, 9 YES 1 1 1 *YES YES 1 1 1 YES YES 1 1 1 YES YES 2 1, 4, 9 YES 2 1, 4, 9 YES 1 1, 4, 9 (i) Major Functional Area Major Tasks Firefighting Firefighting and communicate and strategize with Control Room Search and Rescue Search and rescue operations Operations External Response Provide logistics support for Logistics external response personnel. Liaison with NRC Site Response team. Backup SERO Communications with Notifications ADTS/DSEO. Backup SERO Notification System Communications HP Communications Exposure Control Exposure Monitoring First Aid Emergency Medical Services -Site Access Control and Establish EOF security. Directs Personnel Accountability Security Personnel in support of emergency operations (firefighting communications, personnel accountability) assist in personnel accountability Establish station security, Support emergency operations and perform personnel accountability Supervise on-site security operations Support Provide support to SEOC staff Provide support to EOF staff 5-18 Table 5-1 *Station Emergency Response Organization Normal Position/Title(n) Emergency Position/Title Fire Brigade Fire Brigade Security Personnel I Security Personnel I Station Station Personnel, as Personnel required Licensing, Engineering Regulatory Liaison Security Personnel Security Person -HP Staff RAD Communicator HP Staff CBETS Operator First Aid Team First Aid Team Security Personnel Manager of Security Security Personnel Security Personnel Security Shift Operations Security Shift Operations Supervisor Supervisor EP Narious State Emergency Planning Liaison EP Staff Station Emergency Preparedness Representative Millstone Station Emergency Plan Revision 53 April2016 Emergency Location As Required As Required EOF CAS/SAS EOF, TSC/OSC OSCAA As required TSC/OSC SEOC/Joint Media Center EOF Totals Unit 1 Unit 2/Unit 3 On-Shift Minimum StaffinQ *

• Full Training Rad Resp 30-60 60 Staffing (bl Summary Worker Qua I Minutes Minutes (Refer to App K) Per Local 1 YES YES TRM<al Comm and Support FPER(al Per Sec. 1 YES YES Plan 1 1, 4 1 1 YES YES 2 1, 4 YES 1 1, 4 YES 2 (a) Local 1 YES Comm Support 1 1, 4, 7, 9 YES Per 1 YES YES Security Plan 1(a) 1, 7 YES 1 1,4,9 1 1,4,9 10<1<. 0 11 3o<eJ 38 15(k, I) 11 30(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 hours. c Station position (Counted as affected unit resource).

d One for Unit 1/Unit 2; one for Unit 3; (for Chemistry and Health Physics, two each per site) e Assigned, affected unit resources, addltional 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-l)perating 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. On-Shift total reflects Shift Manager I Affected Unit Control Room DSEO as one position. m For a Unit 1 event the Unit 2 SM/CFH becomes the CRDSEO; after_ responsibilities to the ADTS and EOF DSEO, the Unit 2 CRDSEO becomes the n Higher level personnel may be used to fill these roles as necessary. o A 90-minute goal has been established for the Chief Technical Spokesperson 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 from.the-time of notification to report to emergency assignments. 5-19 Millstone Station Emergency Plan Revision 53 April2016 Figure 5-1 Organization of Station Emergency Management Personnel (Page 1 of3) Senior SERO Management Structure ADTS (Onsite Response) I ADEOF .(Offsite Response) Public Information SERO Structure .;/. .. -CTS-(Public Information) _ --. I Tech Assistant State EP Liaison II Indicates positions necessary for facility activation. D Indicates fully augmented organization positions .. 5-20 *Millstone Station Emergency Plan Revision 53 April 2016 Onsite SERO Structure .F1s:are 5-1 Organization of Station Management Personnel 2 of3) )ADTS ------------..-------......,...

• ,j;,,W"'*""*

"'4-------1------------------ MTSC Electrical Eng Mechanical Eng Indicates on shift positions. II Indicates positions necessary for facility activation. D Indicates fully augmented organization positions. 5-21 -.. .:. MRCA MOS .... **-*::.:.:;,:.:,:;:-*

• _.:,* ;:::,. *:::-;*(_::*:.:=;

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

... * .... ** .....,..-'-'-'.-.....-------------.\;1y;g .....,._ _____ __.)/X? .*. :.-...>,*' ....... . . * .... ** . * .. *:. ****: .. : .. : ***** .... . *,.:,., .** . ....-.... = .-:=.* ... '.*,1:.i.'.:; ...

• :* ... *.' ',*:* .. ::*:*.: ..... :** ' ' . . Millstone Station Emergency Plan .,_, * . *:* ** . Revision 53 *-<" ;r* . April 2016
• ._.

,--' -\\*;* .,., 5 1 -Organization and Location of Emergency Management Personnel (Page 3 of3) Offsite SERO Structure II D MRDA Rad Com Met Assistant Indicates positions necessary for facility activation. Indicates fully augmented organization positions.

• I I Station EP Rep Reg Liaison --.J

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 proteetive 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, the NRC and initiating immediate actions necessruy to limit the consequences of the emergency reside with the Shift Manager (SM), who is on site 24 hours 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 terrr.iinated. After relief by the EOF DSEO, the SM assumes responsibility as Manager of Control Room Operations (MCRO). The CRDSEO /DSEO 1s responsible for ensunng that timely and appropriate notifications are made. .. . . "** ' *' J;n:f:.fJ be transferred during a normal shift rbta:iior. when a qualjfied. Teliefre.ports 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. 6-1 Millstone Station Emergency Plan .Revision 53 April2016 . ..... * .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 commurucate 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 o_:fficials aclmowledge 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) The ill.itial or reclassification messages are received by off-site officials calling the dedicated telephone numbers provided to each responder.

The information above is repeated and additional information is provided as follows: e Date and time of event classification ];'.farf:l.e ind Title of communicator

• _.-;,* .* ' ;i. .. Verbal summary of incident details (major and ininor 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 o:ffsite 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. 6-2 Millstone Station Emergency Plan Revision 53 April2016 The Chief Technical Spokesperson, 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 co111Iliunication 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 InitialAssessment Event classification is based on EALs. The EAL tables. provide. an incident '

• based on instrument v3:;\q;l:J I.ti; fr1

.. . . . .The NRC incident classi:fi\'::a:tlo.tt e.m.il pbsture codes are transmitte.d to state and local

• • :.:* :::. On-Shift dose calculations are conducted, when appropriate, and used to validate the incident classification and any PAR if applicab,le.
• The Shift Technical Advisor (STA) provides independent assessment of emergency actions. When activated, the T$C 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. P ARs requiring evacuation: are to be initiated only for GENERAL EMERGENCY events. Millstone Station Emergency Plan Revision 53 April2016 P ARs 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 P ARs are warranted from the Control Room before activation of the station response organization, the appropriate P ARs 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 action 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 associated with the GENERAL EMERGENCY posture codes. When emergency response facilities are activated, the State DEEP wiil collect and process information to independently verify and recommend changes, if necessary, to the licensee provided P ARs. 6.2.3 Dose Assessment

• : *I ",;:*. ***' ** ** * *. *, ;"-'* " Radiologj.G11.1 .asi:>es;tm,.i:nt:;*.
• by* fhe SERO include -dk.l't'.JJ.'n:,Gnaiit1!Jl 0 t)f :rs.ditkiO:tr*
• exposure rat.tl!s*

by both analytic.* ancl direct* measmement

• 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 IvlRCA. Off-site RMT activities are coordinated by the FTDC under the direction of the MRDA. Field data and projected dose information is transmitted to the State DEEP, as necessary. The emergency plan procedures contain methods for relating the var10us 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. 6-4 Millstone Station Emergency Plan Revision 53 April2016

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 containrp.ent of radioactive materials if 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 vfilues 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 I gaseous effluent releases are-continuously monitored . for radioactive gases by a Spent Fuel Pool Island (SFPI) radiation monitoring Gaseous effluent is sa1npk;k for . continuous sampling system which collects fer: ani:tlJsjs, . 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. 6-5 Millstone Station Emergency Plan Revision 53 April2016

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 rates. The high-range radiation monitor.readings . are tu r03:ease rate using C;.

f1ctor. Gi:ab

, .7::* * . * , * **"" {,::: results, if available, may be more accurate than .rcadiag-3.

• * *. ,,*.
• 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 detennine the quantity ofKr-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 predetennined noble gas ratio (depending on the plant conditions) to obtain the iodine release rate. 6-6 Millstone Station Emergency Plan Revision 53 April2016

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.

e 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 The assessment methodologies used* by l'v'.lillstone Station are intended to provide a rapid best estimate of core damage which, when evaluated together, help to develop ail 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. 6-7 Millstone Station Emergency Plan Revision 53 April 2016

• Containment and Main Steam Line Radiation Levels: An indirect 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. Sam nl1e Anailvs1s -,ii, .. ........ <>fuod . ___ .... ... .. .... . *.* -* .

• • * .. : .. ** 1 . .:Vhi.ch yield:JtP..,e

t.nost accurate* . * :(:or all types of ac,iidents.

Requires swifp-leci system( s) be in a'

• steaqy 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. 6-8 Millstone Station Emergency Plan Revision 53 April2016

f. Committed Dose Equivalent (CDE)-Thyroid 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.

g. 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 t"'"('}n*<, ... o;:.fu:u 0ff-*sit*"'

• . . .. ** )!'.,. '*'"J..".:.I.
• '-.'lb *L ,.,_,,

..... :,. ,t<* _ 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 Thermo luminescent Dosimeters (TLDs) 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.

6-9 Millstone Station Emergency Plan Revision 53 April2016 . -_, ...

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 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. . -" . -' . -l',..,,:-*; -* T'he followillg additiOnal corrective. actions a.re implemented

' ,. 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 assista,nce is needed, the Waterford Fire Service is called. 6.3.2 pamage 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. 6-10 Millstone Station Emergency Plan Revision 53 *April 2016

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 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 briefmg process unless immediate access is authorized by the ADTS to facilitate emergency repairs. a. Notification ' .... , ,*'* . *'\ The actuation. of radiafam station . ¢metgency .. . . alarm, fire alarms, and public. address 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 53 April2016 A precautionary dismissal directs all non-essential Millstone employees, contractors, and visitors to leave the site. d. 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.

Eyacuation 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 . J?-f!rt of evacuation, may be to a fot:.*m-onitorh1g and de<X'l;n;tamination. 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 units for the imme4iate 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. 6-12 Millstone Station Emergency Plan Revision 53 April2016

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 involvt1d 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 mi,ssing.

Accountability is required to be completed within 45 minutes of its initiation (the names of any missing persons identified to the DSEO orADTS and announced over the PA). If precautionary dismissal or evacuation could endanger plant personnel, h . b d r.* d .. 1 ,., .. 1*. h -.;. ' 1 *,a* ., .. t ese ac*t-1ons may e e :4rr1"'* *

• .-'i:*o<':*.
• *

.. :,*: ,; ""' f..1 ... ' p;;... i,,_ (,.,f...,I.:.' . .., *** .-,,..u .a..'Y . * . -. conditions warrant; dismissal, evacuatkm. and accountability will be* .. performed, as appropriate.

1. 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 monito;ring personnel.

An off-site monitoring location will be established if radiological conditions on site prohibit adequate monitoring. Each ERF has radiation detection equipment. The MR.CA 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). 6-13 Millstone Station Emergency Plan Revision 53 April2016 . . ' *'.t, 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 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 " f th "t *11 i**r.1. -*,.. ...

... ,.-...

• • -.e*-*.:.'!..'i" "f ..... , *,:.._., ..
• *. . .' _., .. ac"-ecs areufl 0 Sl e Wli .;.,.,. 1.i{)b:z.O,* .
  • :,.,;: * .;;:

.a

** * * .* e. Radiological waste material will be 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 hours 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) and permanent recording dosimeters (TLDs) 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. 6-14 Millstone Station Emergency Plan Revision 53 April2016 TLDs 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 TLD results become available. The TLD 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.l 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 will be

• evah:at.:'<l for administration to i:,'.ff."'i!ff.
• * * * *'". I ** I ;'t* **** I.,

.... J * .,,,....._ .-.. "l * * ** '\vith emergency. procedures. Exposwces are 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 site responders in accordance with the RPM. 6-15 Millstone Station Emergency Plan Revision 53 April2016 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 (Le., TLD and pocket dosimeter). 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 decontamination are provided. If on-sitc are not usable because of irwmn:ID!.\.i.* 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 hours per day. If necessary, a physician may be requested 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. If 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. 6-16 Millstone Station Emergency Plan Revision 53 April2016

6.5.6 Medical

Treatment Anangements for the primary care of injured, or radioactively contaminated injured personnel are made with the 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 Informat'ion 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 Chief Technical Spokesperson (CTS), 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 F AXed logs from the DSEO/EIS, and plant monitoring systems (OFIS).

• The NNM reports to the Chief Technical Spokesperson at the Hartford Armory. The NNM interacts with the State and Federal media staff at the Joint Media Center and provides feeaback including identified rumor trends to the .ICSC. The Cqrporate
• *(. * . .. * *' *. * ' , . . * * '. ; * ' ' '-I* *,

  nhn&'ge:t tepo . .:<ts

_Support Diiecto:::; the

• -Die fJo'rporate External Affairs Manager devek*:pE and. distributes news 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 Chief Technical Spokesperson represents the licensee in communications with state decision makers at the SEOC and represents* Dominion in media briefs. The CTS may be relieved by a CES at which time the CTS assists the CES in an advisory role and manages the Dominion staff at the Hartford Armory. 6-17 Millstone Station Emergency Plan Revision 53 April2016 Table 6-1 Emergency Exposure Limits Category TEDE Annual Part 20 5.0 Rem(I) Mission to protect valuable property 10.0 RemC 2) Mission to save a life or prevent/mitigate a severe accident Voluntary mission to save a life or prevent/mitigate a severe accident 25.0 RemC 3) >25.0 RemC 4) 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 CFR 50.47(b).11 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 IO Rem TEDE for operations necessary to protect valuable property ..

• on station radiological
• .;*, ex;osures up to*a job/mission-specific designated nut
• ( 4) . Exposures above 25 Rem may be received for life saving activities on a volunteer basis and with full awareness of the risk involved.

e 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 CFR 20 requirements following termination of the event.
• Total Effective Dose Equivalent is defined as part of the station health physics program. 6-18 Millstone Station Emergency Plan Revision 53 April2016
• ' I*,. ,:, . ..'

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 site emergency response facilities (ERFs) are indicated in Table 7-1. The various facilities and equipment are controlled and -surveilled, using MP-26-EPA-F AP05, "Emergency Planning Facility Manl,lal," 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 a Programmable Logic Controller (PLC), two control stations in "monitor mode" only (they can be reconfigured to the . control mode), and an alarm printer. No control functions are available in the "monitor mode." The Unit 2 control room contains 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 and the other ERFs concerning system problems .-as* ...... ,wti:1frL.::is 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 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 applicaple to Unit 1 's decommissioned condition, including the Spent Fuel Pool Island. 7-1 Millstone Station Emergency Plan Revision 53 April2016 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:

• Reactor coolant and Auxiliary systems
• 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 p.0rs.:-rn_r1d transmit notifi.eation Si:'.;l,ff'.

• loe.al emergency

-. 1 1 1 d th t" .c . . . . . . ac mow e ge e nD'

• Cf.ill
• r*E:e1ve a yo1ce-:'.ecorded summary report describing the nature of the incident and the plant status. 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 Millstone Station Emergency Plan Revision 53 April2016 . / ' ...

7.2 Emergency

Operations Facility 7.2. l 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-::;ite data sources and off-site organizations. Emergency radiological monitoring and decontamination equipment and supplies, protective clothing, and respiratory 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 statio.n.t,?.-rotected area, {:refeHo* Appendix F, Figure .. f,,2);,* An alternate EOF is located in the Unit 3 Control Room Tagging Area 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 i power. 7 .2.4 Layout The EOF functional areas are indicated in Appendix F, Figure F-2. 7-3 Millstone Station Emergency Plan Revision 53 April2016 . . 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

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 d * *

• d
• h pr.r Tl..*
• r. *
• l DOF
• proce ures is mamtame mt . p;;,:;

.s* 'l't0!ief/.at.

t1e;*;e .** m. hard copy or electronic form. 7.3 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. 7-4 Millstone Station Emergency Plan Revision 53 April2016 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 con;nnunications with the NRC senior representative on site. J 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 10CFR50 Appendix A, General Design Criteria
• 19 guidelines and the NRC Standard Review Plan for Control

,> .;* *.. ..:," '<'. _ .. Thyroid . Whole body gamma Beta skin dose 30Rem 5Rem 30Rem The HV AC 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 HV AC 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 aisplays. 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. 7-5* Millstone Station Emergency Plan Revision 53

• April2016

7.3.5 Communications

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.

7.3.6 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 ..... *.* The OSC is *a protected area facility, co-located withiii 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. 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/QSC (see Figure F-3). "' 7-6 Millstone Station Emergency Plan Revision 53 April2016

7.4.3 Structure

and Habitability The OSC has the same habitability as the TSC. The OSC Assembly Area has no specific habitability criteria.

7.4.4 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 0 Portable Radios 11 Protective Clothing
• Respiratory Protection A:cceE:s to c%:i;ditioual HP and maintenance equipment is readiJy spc'Cif:fo materials requifod to-perform OSC functio:1;1s. , ' The OSC AA contains the following equipment:
• Dosimetry issue equipment
• Portable radios
• Hotlines and fax machines 7.5 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-EP A-F AP05. 7-7 Millstone Station Emergency Plan Revision 53 April2016 7 .5 .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.

• 7.6 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 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.

7.7 Joint

Media Center .. , .. : .. Joint Media Center is located within thtd}iJ:JC* Trri*'JoiliF**

• . . Media Center is activated by the State DErv.tliS

.. principal rneclia contact poin,tfor 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 .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. 7-8 Millstone Station Emergency Plan ' Revision 53 April2016 7 .9 Communication Systems 7.10 7.11 The communication links between emergency response centers and off-site agencies are shown in Figures 7-1 a through 7-lc. These systems provide* reliable communications and consist of a combination of the station PA system, emergency alarm, intra,plant telephones, computer terminals, dedicated hotlines, commercial and utility (tie-line) telephones, satellite phones, facsimile machines, an4 two-way radios including utility, State Police, Waterford Police, a,nd 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 corrimunication between.the EOF * . I and RMTs. Police and utility radio communication are used by the Control Room in event of the failure of the telephone system for communications. Backup power is for selected communication links in the protected area and the EOF. Ambulances are equipped with radios and can communicate with the hospital. Nornial 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 contacte<l; through the Connecticut DEMHS and. State Police as described in the State RERP. Fishers Island and Plum Island, New York, .. ::i:r-e witbint}l.e plume e4posure ... EP Z m.id ard notified of emerge11e;y . .,:... *'* ,,,;.:: . * * .. ,.

• ':;:,,,,,.::

<'" . ... . . ..

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 IvfRCA 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. 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. 7-9 Millstone Station Emergency Plan Revision 53 April2016 7.12 Damage Control Equipment Damage control equipment consisting 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 i450-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 10-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 of i;neteorological data t:ly tht.** .:: . . system, an electronic data acquisition network. If EDAJ\Y-:iS-,

.1ritical d::tta may be obtained over *the telephone from operators reading Unit 3 Plant Process. Computer data. If the prinurry 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 obtain . 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.

7-10 Millstone Station Emergency Plan Revision 53 April 2016 Table 7-1 Locations Of Emergency Response Centers On-site 1. . Control Room 2. OSC Assembly Area (OSC AA) 3. Technical Support Center/Operational Support Center (TSC/OSC)

4. Alternate TSC . 5. Alternate EOF Off-site 1. Emergency Operations Facility 2. . Assembly Area 3. Joint Media Center 4. State Emergency Operations Center Location Unit 2 and 3 Control Room Cafeteria, Bldg 475 Adjacent to and below Unit 3 Control Bldg. EOF Unit 3 CR Tagging Area Location 18 Stott Avenue, Norwich, CT Simulator Foyer in the Training Building Connecticut State Armory (Hartford)

Connecticut State Armory (Hartford)

5.

Community Emergency Operatiu:!1&:

• ..

Radioiogical

• , *, Centers Response Procedtires*
  • ...... :w .. *-<w,;'.;"-').*

6. Alternate Location 7. Remote Mustering Area 8. Offsite Location Corporate

1.

Corporate Support Center . (ICSC) . State EOC (Armory) Hartford, CT EOF, Norwich, CT EOF, Norwich, CT Location

• Richmond, VA (Innsbrook) 7-11 Millstone Station Emergency Plan Revision 53 April2016 ON-SITE RESPONSE CENTERS T CONTROL ROOM UNITS2AND3 EN T EOF* EN T TSC/OSC/OSC AA EN STATION ON-CALL EMERGENCY RESPONSE ORGANIZATION EN *Located offsite Notification ofEmerge:u;icy Response Organizations T T EN 7-12 T EN EN T EN T COMMUNITY EMERGEN,CY RESPONSE CENTERS CONTIGUOUS T STATES OEM (RI) (NY) Sf/\TE DEEP ... S1'i(TE POLICE. TRQOP EAND F STA1E 1DEPT OF PUBLIC SAFE1tr' COMM CENTER *

... .. STATEDEMHS T : . AFFECTED RESPONSIBLE. OFFICIAL East Lyme. Montville Rshers Island (NY) NewLondon . G-otonCity Old Lyme G-oton To\Nl1 Plum Island (NY) Ledyard ': Waterford Lyme . ':* * :Millstone Station Emergency Plan ., Revision 53 * . .** April 2016 Leg -end: T_ Corrmercjal Telephone Lines EN Bectronic Jlbtification -/ MPEPLAN6.PPT

• Located offsite EYru-.re 7-lb -;*: NRC Emergency Notification System (ENS)

Physics Network (HPN) Millstone Station

• ON-SITE EMERGENCY RESPONSE CENTERS Control Room Units 2 and 3 Emergency Operations Facility* . Technical Support Center
• NRC EOF Command Post NRC Resident's Office 7-13 E E J:. { . Q . . ; ; FEDERAL GOVERNMENT EMERGENCY RESPONSE CENTERS ,___o_e_d""'"ic_at_e_d_li_ne....,s are bridged between NRC and Utilityfacilitie NRC NRC Emergency 11111( E --..i,_ Region 1 Operations Emergency Center H --Response Center* ;,_. H I J Legend: E __:.:_ .. -------r,: -E --ENS -Emergency Notification System, dedicated hottines.

E --H --* HPN -Health Physics Network normal long distance.

• Mill,stone Station Emergency Plan * *Revision 53 April2016

-* ii'i9"'.;;re 7-lc . .,.,_,11.(*r.r::..;:;....:....::;..;;. Lines of Communications Between Emergency Response Centers Millstone Station On-Site Emergency Response Centers . *. State and Local Community Emergency Response Centers --R-' Dominion I Corporate . Executive .I . I . 0 -T-* I Control Room -Unit 2 and 3 -,..:--I I I I -T-I I --I -T-I I I I I -,.. ,. --R-. I I I TSC/OscctJ OSCM Operations Facility.Center* RadiC?lOQical Morntonng Teams ---i--R-. I " " . -: : I ': ---I * -I --. I Innsbrook -* Corporate I --Support Center . I ' I -I I --I I -.... -_. _' --* -----""'""" """ . I -R-"' Legend: .. -T -Commercial -.t!!J. Telephone

• -* Telephones

-R-Radio (U2/3only) FAX Machine --,r Oata Line -Information Line to 06minlon Energy * -T-Contiguous ,___ States (RI) (NY) Affected -T--T-Community EOG Affected -(Waterford) Community EOC -R-I -T State DEEP Desk -R-State EOC I State Armory - -T-Dominion StateEOC --Corporate Joint Media Cir. Nuclear Public Information state Police -T-Troop"F" --R-State Police i:I: . . . Troop"E" Dept of Public Safety -T-Comm. Center *Located offsite 7-14 .. ::, Millstone Station Emergency Plan * -1 Revision 53 April 2016 *-* ;.-. Maintaining Emergency Preparedness Station management is responsible for the staffmg 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) . ., Preparation and conduct of emergency plan drills and exercises.
• Training off-site emergency response personnel.
• Providing input to SERO training.
• Coordination of licensee, state and local emergency plans and procedures.
• 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-jC'b . tr2itth1g

.. nn 1:1 superv.ised kdministration and management 0f . is detal.led in - Emergency Preparedness*implementing -* , * * ...... * .. *:-.. *<' ""';* .,. *** * ... :*. 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. 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-MP-TPG-2400 and MP-26-EPA-FAPOl. 8-1 Millstone Station Emergency Plan Revision 53 April2016 8.1.2 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 inf01mation. 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. In 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 em:ergency organizations are trained in radiation monitoring and protection, activation and operation of evacuee reception centers . . 8.1.3 Additional Emergency Preparedness Training a. Plant Access Training (PAD Employees obtaining unescorted access to the station. for frrst time .. receive ... part. 6-f plMt *,_ * : *access traiillng. This *

J:* wvfow.

<of. -***

• planning, the emergenc)!

-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.

Initial 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 mirllmum.

8-2 Millstone Station Emergency Plan Revision 53 April 2016 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 performance. 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. 82. l 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. s The site emergency alarms and emergency responder notification . . system;:; tests montl;ily. . . . , . ., .. _. . * ....... -.** ' . e

• Communications wiili *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 *RMrs 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.

8-3 Millstone Station Emergency Plan Revision 53 April2016

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-EP A-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 the unit technical requirements manuals. The Station Fire Marshall is responsible for the review and approval of all fire drill scenarios, in advance of their use. The Station Fire Marshall shall evaluate and take appropriate actions for observed fire drill discrepancies. The Station Fire Marshall shall also review and disposition, as necessary, comments from fire drill critiques.

b. Medical Emergency Drills The-Manager, Emergency lO:r:/son<lucting

_ .* o: ,. ' annual medical drills. ArrangeJ.Uents for and drills are . made -through the Lawrence and Memorial Hospital Middlesex Hospital Emergency Departinents,

• 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 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 conduded 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 53 April2016

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 plume exposure pathway EPZ. The level of participation shall be as follows: J:i 6 .

• The State of Connecticut shall fully participate in at least one 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 . . mam exercise.

8-5 Millstone Station Emergency Plan Revision 53 April2016 ._ .. ,*_.

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 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 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 elements not properly d1:iriB.g previous exercise. . .. *< ,, g. Post-Exercise Critique An in-house, post-exercise critique will be conducted, An off-site post-exercise critique will be scheduled at the conclusion of each exercise by FEMA to allow offidal 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. 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. 8-6 Millstone Station Emergency Plan . Revision 53 April2016

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 CPR 50.54(Q) Change Evaluation, for 10 CPR 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 CPR 50.54(q). Evacuation time (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 I 0 CPR 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, te$thrg, <::q;?iipmenr;; 2111 -.:rvaluation.r cf the adequacy.

Of interfaces with state and loca1 g0ve1m'1.trmt and the of dfills and exercises.

The , .. reviewer completes a written report fb&tdetailS" 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 fmdings. 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. 8-7 Millstone Station Emergency Plan Revision 53 April2016 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 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 media with emergency plans, information concerning radiation, and points of contact for release of public information in an emergency. Am::-,dia manual, developed t,.0 meet the ni;;;cds of

media, in.J:110.1&.fon ai1d general information coaceming

• planning, nuclear power* and -. :radiation.

The manual is distributed to the local media v:nd is available for issue at* the Joint Media Center at the time of an emergency. 8-8 Millstone Station Emergency Plan Revision 53 April2016

9. Recovery 9. I 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. Recovery actions are described in emergency plan procedures. 9 .2 Recovery Organization The ORO is in Figure 9-1. 9 .2.1 Site Vice President -.Millstone The Site Vice President -Millstone is responsible for coordinating the station ..... :"*'"**** ... , ...

9.2.2 Director

of Recovery

• .. , .. _. The Director of Recovery Operations (DRO) is responsible for overall direction of recovery operations and reports to the Site Vice

-Millstone. The Director of Recovery Operations (DRO), as well, as those managers reporting directly to him, are chosen by station mari.agement. They possess competep.t 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 co1lecting, retaining, and retrieving data.
• Providing post accident data analysis timeline for the accident.

9-1 Millstone Station Emergency Plan Revision 53 April2016

• 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 sUi.tion support staff during the recovery operation.
• Maintaining an effective station security program.
• Implementing maintenance and repair operations with station staff.
• 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 Ell .Assisting. the fi't'iYJ* DEEP' .. off..:site-*recpvery .. *phase***:\ . .-*.

• v*. sampling, survey .tneasuremer-.tts*

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 proviqing 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.
• Developmg decontamination plans.
• Assisting the State DEEP in determining total integrated population doses by using various inputs. 9-2 Millstone Station Emergency Plan Revision 53 April2016

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.

e general administrative support. e Scheduling and expediting recove1y operations.

• Assisting the DRO in planning activities.
• Coordination of recovery staff meetings.

c, TG;hl>latmg, expediting and closbg out commitment lists in su5f)p0rt 0£ 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.

9-3 Millstone Station Emergency Plan Revision 53 April2016 I Manager, Technical Support *System Analysis *Core Physics *Data Reductions (Post-Accident . Analysis Data) Licensing

• NRC/state licensing I Manager, Plant Operations
• Affected unit staff plus other station staff as applicable 9-4 Figmre 9-1 Recovery' Organization Site Vice President -Millstone I Director of Recovery Operations I I Manager,
• Radiation Centro!

.. *Waste Design *.\

• f >: --*ALARA
• Waste
• . ,S¥;J;!(i;:'YUre Evaluations
  • * "i.
• Specialized

'

• Dosimetry

, ;. *Field Su rve'y an<l Environ mental Sam pie Teams *Off-site and On-site surveys, sampling for recovery/reeqhy . decision maki;ng.

L

' . *'* 1-----1 Advisory Support I Manager, Engineering

• Engineering
• Vendors *AIE *NSSS *Resources
• Construction
• Purchasing
• *Legal
• Insurance
• Project Management
• Schedules
• Cost Control Millstone Station Emergency Plan * . Revisfon 53 . * * :*,. April f016 Millstone Station Representatives in the State EOG and Joint Media Center *Millstone Liaison with the state EOC and official media spokesperson.
• Support State response to FEMA questions*.
• Support local responses to questions and evaluate needs.

Appendix.A APPENDIX A DEFINITIONS, ABBREVIATIONS AND ACRONYMS A-1 Millstone Station Emergency Plan Revision 53 April2016 Appendix A This section provides definitions of commonly used terms that are applicable to this Emergency Plan. ' DEFINITIONS Absorbed Dose The quantify 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 meastires. Corrective Actions Those emergency measures taken to improve or terminate an emergency situation. Actions taken as a result of reaching an Errrergertcy* 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. A-2 Millstone Station Emergency Plan Revision 53 April2016 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 (RCA) An area of the Station where dosimetry is required. 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. Monitoring: Station The Unit 1 facility from which indications and a1mms 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 ari 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. Contamination (Radioactive) The deposition of radioactive material in any place where it is unwanted (e.g., on persons, products or equipment). A-3 Millstone Station Emergency Plan Revision 53 April2016 Appendix A 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. The unit of radioactivity which is equivalent to 3. 7 x

• 10 10 disintegrations per second; millicurie (mCi) = one-thousandth curie; microcurie

(µCi) = one-millionth curie; picocurie (pCi) = millionth micrpcurie. 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. Thresholds for _initiating aotil611ri !tu.ch as d:esignathig ,lJ:Particular class of emergency,.

• . * ( ..... --*.* . :illitiating 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, BRA VO/ ALPHA) Emergency Operations Facility (EOF) A facility located 15 miles north of Millstone from which station activities related to an emergency will be carried out and from which information will be provided to the corporate, federal, state officials and focal community chief executive officers.
• A-4 Millstone Station Emergency Plan Revision 53 April2016 Appendix A 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 ill internal exposure. Ingestion Exposure Pathway The-pathway by which could-b& ". contaminated water or as milk or. whlch 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 hours of SERO activation. Personnel assigned to fill these positions are drawn from a pool of qualified individuals .. 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 no_t 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). A-5 Millstone Station Emergency Plan Revision 53 April2016 Appendix A 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 OSFSD 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 Personne.l assigned to :fulfill a specific SERO position and who report to the station in accordance with Table 5-1. . . :.. .-1 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. Operational Support Center (OSQ 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 .. A-6 Millstone Station Emergency Plan Revision 53 April2016 Appendix A Procedures Emergency Operating Procedures (EOP) Procedures which provide specific actions to mitigate the consequences of and terminate an emergency situation. Emergency Plan Implementing Procedures (EPls) 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 Projected Dose The estimated potential* dose that could be received by affected individuals if no

• protective actions are taken. Protective Action Guides (PAGs) Prqjected absorbed dose to individuals in the general population which warrants protective

' . . , . . M.;ct:ion, ... -:' .... * ...... * ***' : ' 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 ele'ctrically charged ion pairs directly or indirectly in its passage through the medium.

• 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. .A-7 . Millstone Station Emergency Plan Revision 53 Apri12016 / Appendix A Station Emergency Response Organization The organization responsible for station operations under emergency conditions. The State of Connecticut. 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 in the Control Ro9in (or reported to : ..

l. 1 ) h .

• 1 ,. ., ' ... .. -. ;, . ,;, " , L .. 1 . th" . I . .. . . . . . . . .

.. ,.,:. tue Centro Room t at 1s -r ie t.1.zesimKr. a ):(ID1f-"* il74t p.i:ai;;es* ifiP ant. m a* grv.e:Q: ... /';., .. ";:::n emergency classification. A }a,e aH -UJ;Ztrt.mttt.nt tt:imii1'.lg, equipment status fodiCaior., ci. .*. 1" measurable parameter (on-site or ), a discrete observable event, or the results of Technical Support Center (TSC) A center located where technical support personnel monitor station conditions and provide data interpretation. A-8 Millstone Station Emergency Plan Revision 53 April2016 Appendix A ABBREVIATIONS AND ACRONYMS ADTS ALARA AMRDA AMT ARMS ARPS BWR CBETS CCorCM 3 CEDE CES CFH CDE CFR Ci CMS co CONVEX CPM CR CRDC CRDSEO CT CTNG CTS DEMHS DEEP DRS DSEO DOE DOT dpm/100 cm 2 DRO EAL EAS EC ECCS EDAN EIS ENRS ENS Assistant Director Technical Support As Low As Reasonably Achievable Assistant Manager Radiological Dose Assessment Accident Management Team Area Radiation Monitoring System Assistant Radiation Protection Supervisor Boiling Water Reactor Computer Based ExposureTracking System Cubic Centimeter Committed Effective Dose Equivalent Corporate Executive Spokesperson Certified Fuel Handler Committed Dose Equivalent Code of Federal Regulations Curie (Unit of Radioactivity) Central Monitoring Station . Control Operator Connecticut Valley Exchange Counts per minute Control Room ..

• . ... Conti:o} Roam Direetor.

of Station Emergency Operations Connecticut Connecticut National Guard Chief Technical Spokesperson Division of Emergency Management and Homeland Security Department of Energy and Environmental Protection Department of Health Services (formerly DREW) Director of Station Emergency Operations U.S. Department of Energy Department of Transportation Disintegrations per minute per 100 square centimeter area Director of Recovery Operations Emergency Action Level Emergency Alert System Emergency Communicator Emergency Core Cooling System Environmental Data Acquisition Network Emergency Information Specialist Emergency Notification and Response System NRC Emergency Notification System telephone A-9 Millstone Station Emergency Plan Revision 53 April2016 EOC EOP EOF EPA EPAP EPC EPI EPZ ERF ETS FDA FEMA FSRC FTDC GM gpd gpm HAB HP HPN HVAC iCSC INPO IPZ ISFSI JMC KI LCO LOCA MA MAX MCL MCRO Met MOC MOR MOS MPC Appendix A Emergency Operations Center (State, local, or Site) Emergency Operating Procedure Emergency Operations Facility Environmental Protection Agency Emergency Plan Administrative Procedure Emergency Planning Coordinator Emergency Plan Implementing Procedure Emergency Planning Zone Emergency Response Facility Environmental Technical Specification . Food and Drug Administration Federal Emergency Management Agency .

• FacilitY Safety Review Committee Field Team Data Coordmator Geiger-Mueller detector Gallons per day Gallon per minute Hostile Action Based Health Physics NRC Health Physics Network Telephone Heating Ventilation and Air Conditioning System .. . .:.*r:-:::.

';*:. **'. / . .l--. :*. "" , ** *1c.rl1'*.,,,,.

• * *W l,>:.JV . " . . Inilsbrook:'Corporate Support Center Institute of Nuclear Power Operations Ingestion Pathway Zone Independent Spent Fuel Storage Installation Joint Media Center Potassium Iodide Limiting condition for operation Loss of coolant accident Massachusetts Maximum Media Center Liaison Manager of Control Room Operations " Meteorological Manager of Communications Manager of Resources Manager of Security Maximum permissible concentration A-10 Millstone Station Emergency Plan Revision 53 April2016 MPS MRCA MRDA mRern/hr *MSRC MTSC NAP NFSA NG NRC NNM NY OFIS OMF ORO osc OS CAA PA PAO PAR PAT ' . *PEO PF PIO PWR Q QA R rad RAE RCA RCP RCS REM RERP RHR RIEMA RL RMS RMT RO RP Appendix A Millstone Power Station Manager of Radiological Consequence Assessment Matl3:ger of Radiological Dose Assessment 1/1000 Rem per hour Management Safety Review Committee Manager of Technical Support Center North Access Point Nuclear Fueland Safety AnalysiS (formerly RES) National.Guard,.

U.S. Nuclear Regulatory Commission Nuclear News Manager New York Off-site Facilities Information System Offsite Monitoring Facility-EOF Organization for Recovery Operations Operational Support Center Operational Support Center Assembly Area Public address system Protective Action Guide Protective Action Recommendation Plant Access Training Plf"int

• .

factor*.* Public Infmmation Office;;: Pressurized water reactor Reiease rate Quality Assurance ,' Roentgen. A unit of radiation exposure Unit of.radiation dose Radiological Assessment Engineer Radiological Control Area Reactor Coolant Pump Reactor Coolant System Unit of radiation dose Radiological Emergency Response Plan Residual Heat Removal Rhode Island Emergency Management Agency Regulatory Liaison Radiation Monitoring System Radiological Monitoring Team Reactor Operator Radio Pager \ ... ;** A-11 Millstone Station Emergency Plan Revision 53 April20i6 RMP RWP SAP .scBA SDO SEOC SERO SIS SRO SM SPDS STA State TA TEDE TIC TLD. TSC TSCEE TSCSM us USCG u µCi X (chi) X/Q Appendix A Radiation Protection Manual Radiation Work Permit South Access Point Self-contained breathing apparatus Station Duty Officer State Emergency Operations Center Station Emergency Response Organization Safety injection system Senior Reactor Operator Shift Manager Safety Parameter Display System Shift Technical Advisor State of Connecticut Technical Assistant Total Effective Dose Equivalent Technical Information Coordinator Thermoluminescent Dosimeter Technical Support Center Technical Support Center Electrical Engineer Technical Support Center Shift Manager Unit Supervisor .. Gua.sd -vVindspeed "Mitrocuries

• Concentration Relative Concentration A-12 Millstone Station Emergency Plan Revision 53 April2016 AppendixB APPENDIXB LETTERS OF AGREEMENT B-1 Millstone Station Emergency Plan Revision 53 April2016 AppendixB Page Organization B-3 Amtrak B-4 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 Public Safety-Division of State Police B-10 Teledyne Brown Engineering B-13 Town of Waterford Ambulance Service B-14 Town of Waterford Fire Service B-15 Town of Waterford Police Department B-16 Accu Weather I B-17 GEL B-18 Norwich Fire Depmt.m0xrt
• .. . ' -. -**-.. . ..-1 ....

... ... , ,*.-. .. *-.-;._' . ' *-B-19 Salem Volunteer Htit

• ,, , .. .. .. ,. .. . .

.* ,.,, ..... *-*.,. Note: The letters of agreement are reviewed annually and verified to be current. Only letters with significant changes require reissue. B-2 Millstone Station Emergency Plan Revision 53 April2016 4:29PM HP Fax November 17, 2015 Mr. John Daugherty Site Vice President Dominion Nuclear Connecticut Rope Ferry Road Waterford, CT 06385

Dear Mr. Daugherty:

AppendixB . . . . '

• I page 1 This letter ls to confirm that the National Railroad Passenger Corporation will, when requested respond* in the event of an emergency at the Millstone Power Station on Long Island Sound, in the following areas: Implementation Criteria/Authorities.

Responsibilities 7;Jw i.'lll)" understanding that, In the eve;nt of ::,n .. t\co>}

• Site Emergency Operations may rnquost otif'*at."Si::.t&r.t.:e.

A<>sistc;r:cz

• should be rnquestad by calling the Chief Train Dispatcher of the a .. ,s.to;; Cl.ITC Office at 61/345-**

7474. Indicate the nature of the incident, the location, and the type of assistance required. Measures to be Provided/Limits of Actions Our commitment for assistance is to direct train traffic away from any areas that may be affected by the emergency. Information Exchange /Point of Contact at Site Verification communications to the nuclear facility will be by telephone to the Director of Site Emergency Operations al Bf}0/892-5600. Information exchange can be by using the Chief Tran Dispatcher's number.

• Training and Dfills Please notify us of your plant drills so that we may have the opportunity to observe your emergency response actions and meet your emergency operations personnel.

Please coordinate by contacting my offiee at 617/345-7406.

• • .'..** B-3 Millstone Station Emergency.Plan Revision 53 April2016 AppendixB l-Nov 19 2015 4:29PM HP Fax page 2 NATIONAL RAILROAD PASSENGER CORPORATION Mr. John Daugherty November 17, 2015 Page Two Two South Station, 5th Floor, Boston, MA 02110 AMTRAK This letter of agreement shall remain in effect until cancellation by either party, provided on ninety (90) days prior written notice, and shall be reviewed and certified as needed. Sincerely, . Fe{E' Deputy General Manager Northeast SubDivision Cc: P. O'Mara, Amtrak Superintendent

-Operations W. B. Moore, Deputy Chief -Amtrak Police S. Pugs le)!, Amtr::'l!<

• .. Davra. [..;qi-n
• B-3a I..'*. Millstone Station Emergency Plan Revision 53 April2016 AppendixB LETTER OF AGREEMENT BIETWEEN ELECTRIC BOAT CORPORATION AND DOMINION NUCLEAR CONNECTICUT RADIOLOGICAL ASSISTANCE Enclosure (1) to 438-37497 Page 1 of2 It is understood that the Electric Boat Corporation will, upon request, respond with personnel and equipment In the event of an emergency et the Miiistone 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 Radlologlcal 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 s/iipyard Security is *contacted, request that RAD CON Management be notified. for assistance includes. provldi!Jg r<!diologicc;Leoritrcl pereonnel and .eqvipment 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). B-4 Millstone Station Emergency Plan Revision 53 April2016 AppendixB Enclosure (1) to 438-37497 Page2 of2 It Is understood that should the Electric Boat shipyard be affected by a radioactive release from another facility, Electric Boat resources wlll 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 <<:1xchange can be provided by using the same telephone number. It is understood that Miiistone Station wlll train representatives of Electric Boat Corporation's Radiologlcal Training Section annually on the use of Station equipment and procedures. These Radlologlcal Training Section Individuals, in tum, will train selected Electric Boat Corporation personnel on this equipment and procedures. It is understood that this training wlll 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 effect until cancellation by either party, provided on ninety<90) . wrltt.en and shall bo rc*.rieVH3d e.:f, Dominion Nuclear i::Onnectlcut By: / , -:'ffejz4;/JU&& Jk-Name: J. Alan Prjce B-4a . Electric Boat CorporaUori . L2;n<5Z1* M. Toner President Millstone Station Emergency Plan Revision 53 April2016 AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 Nuciear Power Plant Emergency Response Assistance Agreement This Nuclear Power Plant Emergency Response Assistance Agreement (hereinafter "Agreement") has been entered into by and among lNPO and electric utilities that have responsibility for tlie construction or operation of commercial nuclear power plants under a license issued by the U.S. Nuclear Regulatory Commission pursuant to Title 10 of the Code of Federal Regulations (hereinafter "nuclear power plants") and that have subscnbed counterpart signature pages in the form attached hereto (hereinafter "Parties"). 'nte 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 a:p.d obligations that will be incurred.in -responding to r'.!qp.ests for A. "C.oordil:].ation on Sharing Emergency Infon11ation N&. Vtilities" *

• describes the responsibilities and expected NOW, THEREFORE, agreed, that: 1. Assistance rendered by a Party as described hereunder

µiaybe 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 tet:II1$ and conditions herein. 2. The Party that requests assistance shall be known as the "Requesting Company and the Party :furnishing assistance 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 efilail, fax, or phone request (followed with documentation) in emergency circumstances that lists the requested, offered and. agreed upo:µ. Assistance, that references this Agreement, and that is agreed to by both the Requesting and Responding Parties. 1 B-5 Millstone Station Emergency Plan Revision 53 April2016 AppendixB AGREEMENrBETWEENPARTIES November 8, 2013 5. (a) 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 01* the :furnishing of assistance pursuant to this Agreement.

Requesting Company shall notify Responding when its assistance is no longer needed. (b) The :furnishing of assistance hereunder shall be deemed to have commenced when persorinel 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) , - .. aLh1rrangemi;;nt.Bf{{<i* transportatiQit of itS _f:i.:om an.ct to their working baf).e 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 Respondllig Company shall be those of the Re8ponding 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 .. *. B-5a Millstone Station Emergency Plan Revision 53 April2016 AppendixB. AGREEMENT BETWEEN PARTIES November 8, 2013 7. (a) Responding Company shall furnish the requested personnel and equipnieilt to the extent that the Responding Company may determine to do so in its sole judgment and discretioIL (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 known to, or readily ascertainable by, the public without fault or omission of either party or its employees or agents; or (2) was already known 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) vvas

• r,;;;; E**n4 *$.\ther directJy, os indirectly, ac(.'est.tl'.'.

t'l'.it\tow!a:dg<: of other party. .,.,, ** .. ,, . ._, .. :. (c) Responding Compi,i.ny 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 worltjng 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 hours in advance to Requesting Company of the permanent withdrawal of personnel or equipment

furnished.

Responding Company's withdrawal of personnel or equipn;ient shall not affect any obligations which . may bave 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 fumishirig of assistance to the Requesting Company, which statement shall be paid by Requesting Company within thirty (30) days after receipt. 3 B-5b Millstone Station Emergency Plan. Revision 53 April2016

• Appendix.B AGREEMENT BETWEEN PARTIES November 8, f013 9. The Requesting Company shall reimburse Responding Company for all direct and indirect costs and expenses, not including a profit, incurred by Responding Company in giving assistance pursuant to this Agreement, including but not limited to costs and expen8es related to or resulting from compliance with governmental requirements such as Title 10 of1he Code ofFederal Regulations Part 20. Such costs and ex.penses shall be computed in accordance wi1h Responding Company's standard rates and accounting practices, including such overheads as are detennined by Responding Company to be applicable to such direet 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 1 O(b) hereof: Requesting Company shall indemnify and hol9. 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 fro:m fumishlng 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 byR:0sponding Company or its insurers to Responding
• oi:'" . -*' ,,_ -*._._.,.,,,

Company's officers, directors, or employees or their benefiCiaries for bodily injuzy 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 descnoed in this paragraph l O(b) which such insurer may make on behalf of Responding Company because of Responding Company's fumis-hing of assistance pursuant to this Agreement. 4 B-5c Millstone Station Emergency Plan Revision 53 April 2016 AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 ' Responding Company makes no warranty with respect to any goods or seJAT:ices provided to Requesting Company and NOW ARRANTY, EITHER EXPRESS OR IMPLIED, ORAL OR WRITTEN, SHALL APPLY TO THE GOODS OR SERVICES PROVIDED, INCLUDING, WITHOUT LIMITATION, THE WARRANTIES OF . MERCHANT ABILITY AND OF FITNESS FOR SPECIFIED OR lNTENDED PURPOSE. All equipment and services furnished by Responding Company pursuant to

• this Agreement are furnished as is. (d) Jn the event any claim or demand is made or suit, action, or proceeding is filed against Respondmg 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 iii its sole discretion deems necessary or prudent Responding Company shall cooperate with Requesting Company in the resolution ofany such matter. If a Reqoesting Company settles a liability suit with a 3rd party that involves a Responding Company, Requesting Company will eµsure the Responding Compnay is released from liability.

' (e) Each Party to this Agreement agrees to carry the amount of :financial proteetion required by the Atomic Energy Act of 1954, as amended, and self-insurance or comprehensive liability insurauce, including in'Jemnification: and defense obligations set forth herein, sub,1ect;to $;'..:tcli1cypen and-amounts of self-* insurance, retentions, or deductibles as 2.re con."listentwithstandard business practice in-** * *

• the industry. (t) Jn the event a Responding Company provides assistance pursuant to this Agreement through an affiliate or subsidiary, the indemnification provided in this 10 to the officers, directors, and employees of that Responding Company shall apply with equal
• force to the officers, directors, and employees of that aftiliate or subsidiary.

11. Each Party shall provide the Institute ofNuclear Power Operations (hereinafter "INPO") with an executed counterpart 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 B-5d Millstone Station Emergency Plan Revision 53 April 2016 . . ' -. -,.

AppendixB AGREEMENT BETWEEN PARTIES November 8,,2013 12. (a) INPO may provide certain administrative and emergency response support services in furtherance of this Agreement, such as maintaillin.g and distributing to the Parties a roster of the signatories to this Agreement; providing copies of the Agreement and any amendments thereto to all Parties; and preparing and disttibuting to the Parties other documents, such as a list of sources of emergency manpower and equipment. lNPO may provide such other services as may be requested of INPO from time to time by the Parties. The Parties recognize that JNPO shall not be responsible for implementing, enforcing, or interpreting this Agreement. (b) The Parties shall defend, indemnify, and hold harmless 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 ofINPO'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 JNPO, its officers, directors, or employees arising out of its or their performance of INPO's functions described in paragraphs 12( a) and l2(c). (c) Following an emergency at a nuclear power plant the Requesting Company may contact INPO for help in locating and coordinating delivery ofrequested 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 ... -:; ff:.i.:e .. .:tillg'

latfie*S'**.,:. (Responcling Cirrop@lic3J ihr assistance.

hl ca6e file Assistance Agreements will be csmblishd hetweer.. fol* Company mid Responding Companies. (d) If INPO furnishes assistance and unless otherwise agreed by INPO and the Requesting Company, the Requesting Company and INPO 11hall have the same rigl1ts and obligations as ifINPO were a Responding Company (including but not limited to the Requesting Company's ob1igations to INPO, its officers, directors, and employees under paragraph 10 hereof), except that paragraphs 8 and 9 and 10( e) shall not apply to INP.O. 13. This Agreement will.not create any rights or defenses in of any entity or person not a signatory to this Agreement-except to the extent provided in this paragraph and in paragraphs IO and 12 of this Agreement. This agreement shall be binning upon and inure to the benefit of each signatory to this Agreement and the subsidiaries and affiliates of each such signatory. 6 * .... **. B-5e Millstone Station Emergency Plan Revision 53 April2016 "**** : i* . \. i AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 14. Except as otherwise provided in paragraph 15, any Party may withdraw from this Agreeinent 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 arise out of events occurring prior. to the date. No Party may withdraw from this Agreement while it is receivillg 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 bi:iiding upon all Parties thirty (30) days after INPO has received signature pages for the amendment executed by at least a majority of the Parties to the Agreement.

JNPO 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. Notwithstanrung the first sentence of paragraph 14, any Party may withdraw from this Agreement by submitting written notice to INPO 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 0perated on Qf .l!. Party, or an event associated with transportation of nuclear Party; (jj) assistance is issueffto.,.,,_,

to :illch-emergen.cy; and (iii) such assistance is provided, this Agreemcilf stall he 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 B-5f Millstone Station Emergency Plan Revision 53 April2016 AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 EXHIBIT COUNTERPART SIGNATURE PAGE The undersigned comp(llly hereby agrees to become a Party to the Nuclear Power Plant Emergency Response Assistance Agreement and its attachments. Company "))QM V" ()..; Printed Name: J::>ev \.D /\, \-h-.""YX CD cq;; (Corporate OJ;ficer Signature) 8 B-5g Millstone Station Emergency Plan Revision 53 April2016 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 infonnaticin regarding emergencies at nuclear power stations and to maxhnize their assistance roles to their utility members and the industry, the Electric Power Research Institute (EPRI), the 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 purpose 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: I. 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 inforination regarding the emergency.
• NEI will develop and issue, in coordination with the affected utility, appropriate pµblic st_atements to the news media, as necessary.

ci. :r.:IBI-will associated press releases'-to its ., ::nembers and other fr:i<l,:r;.sl.rJ

• • *:ix
• 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.

• JNPO 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 B-5h Millstone Station Emergency Plan Revision 53
• April2016 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 own databases.

• INPO will maintain information on industry assistance capabilities including:

o Personnel with specialized plant or emergency response knowledge o 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 lNPO 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 B-5i Millstone Station Emergency Plan Revision 53 April 2016 ;: ,_ ... -,*. AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 EXHIBIT 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 January 3, 2014 Company Institute ofNuclear Power Operations By C:. -(Corporate Officer Signature) Printed Name: William E. Webster, Executive Vice President B-5j Millstone Station Emergency Plan Revision 53 April2016 LAWRENCE +MEMORIAL November 23, 20i5 AppendixB BRUCE D. CUMMINGS President & Chief Exe cut Ive Ofiicer John Daugherty, Station Vice President Dominion Nuclear Connect.icut Inc. PO Box128 Waterford, CT 06385.

Dear Mr. Daugherty,

ema.ih bcummlngslmhosp.org 365 Montmrk Avenue I New LondQn, CT 06320 860.442.0711, Ext. 4645 I FAX 860.271.4474 This lett;er* is :to confirm that + Memorial Hospital will respond in the eve qt of a radiological emergency at.Millstone Power Station. Implementation Criteria (Authorities. Responsibilities [tis our understanding that in the event otan emergency, the nuclear facility may request medical assistqnce. The Hospital EmergencyDepartment is to be contacted at calling (860)442-0711 ext. 2261 and requesting to speak to Emergency Department Charge Nurse to acti.vate om: 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 inc 1;:u:t!*1d a

mr

who are *ne*:d r;f medical treatment at Lawr2ncc.+

Ho.qJit?.l, . 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, _.,..-*'_.' <-* 'Bruce 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 *

• Gregory M. Olexy, Emergency Preparedness Specialist,.., Dominion Nuclear Connecticut, Inc.
• D. Smith, Emergency Planning Service ,.., Dominion Nuclear Connecticut, Inc. B-6 Millstone Station Emergency Plan Revision 53 April2016 AppendixB ADMINISTRATION November 19, 2015 Mr. John Daugherty Vice President

& Senior Nuclear Executive Dominion Nuclear Com1ecticut, Jnc. Millstone Power Station Rope Ferry Road Waterford, CT 06385

Dear Mr. Daugherty:

HOSPITAL 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 suppmt for Lawre11ce and Memorial Hospital, acting as the secondary medical treatment facility fo1* the Millstone Station, Any expenses incurred as a result of providing these services will be the l'esponsibility of Millstone Power Station. In case of an emergency situation, we would follow the plan for "Decontamination and Treatment of the Radioactively Contaminated Patient at Middlesex Hospital," currently in effect between om* institution . m1c' tlm TiciEll.y If you iiave ::my qtlci*tlnns coi1cei11ing om* for contaminated patients, please cont&ct i.r;.;* Gary vican Vice President Strategic Planning & Ambulatory Operations GH:aac c: David A. .smith, Manager, Preparedness, Millstone A member of the Middlesex Health System 28 Crescent Street Midclletown, Connecticut 06457-3650 tel 860 344-6000 fax 860 346-5485 ';_'. '* *.' B-7 Millstone Station Emergency Plan Revision 53 April2016 AppendixB SHIPMAN'S FIRE EQUIPMENT CO., INC. 172 CROSS ROAD WATERFORD, CONNECTICUT 06385-0257 (860) 442-0676 .December 6, 2010 Mi:. Skip Jordan Site Vice President Dominion Nuclear Connecticut Millstone Station Rope Ferry Road Waterford, CT .06385 .Dear Mr. Jordan: This letter is to con:.fum that Sb,ipman's Fire Equipment Co., will, when requested, respond in the event of an emergency at the Millstone Power Station, in the following areas: Implementation Criteria/ Authorities, Res,ponsibilities It is our understanding that, in the of an .emergency, the nuclear facility Director of Site Emergency Operations may request services to assist in the emergency effort. Assistance should be requested by calling 860-442-0678:.611. Measures to be Provided/Limits of Actions for in t,Jw e::irent of an

• Power.
• Infonn.nifo:ti Exchange/Point of Contact at Site *Verification communications to the nuclear facility will be by telephone to the Director of Site Emergency Operations.

The telephone.number is unlisted. Infonnation exchange can be provided.by usirig the same telephone number. Training and Drills Since our a8sistance is limited to providing equipment and service, we feel that we do not need to participate in your training drills, However, we would appreciate being invited to your plant drills to Observe your emergency response actions, and to meet your emergency

• 'This letter of agreement shall remain in effect until cancellation by either party, provided on ninety (90) days prior written notice, and shall be reviewed and certified as needed. President cc: David A. Smith. Emergency Preparedness Planning Services Department, Millstone FIRE & SAFETY EQUIPMENT'

... ,; "

• ... -; .. , r .'-'"*r "t.* . '1.' * * . FAX (860) 444-7395 www.shipmans.com Email lnfo@shipniatis.com B-8 Millstone Station Emergency Plan Revision 53 April2016

.. ,; .t. AppendixB STATE OF CONNECTICUT DEPARTMENT OF EMERGENCY SERVICES & PUBLIC PROTECTION O"FACE 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:

Th.is lettP-r. is ta r.or;ifirm that personnel and equipment from the Depart.ment of Emp.rgency .... yvheri requested, respond in the event

i.£.: the Mi11$:0n'e

• *
• This response is submitted in accordance with the State of Connecticut Radiological Emergency Response Plan. Sincerely, \

.. A...-.. .. D COMMISSIONER cc: William P. Shea, Deputy Commissioner* Col. Brian Meravlglla, Deputy Commissioner 111 L Country Club .Road Middletown, CT 06457 Phone: (860) 685-8000 I Fax: {860) 685-8354 .Jl.n .'Affirmative .:Action/'Equa(Oyyortunity '.Emy(oyer B-9 Millstone Station Emergency Plan Revision 53 April2016 AppendixB November 5, 2014 Mr. Stephen E. Scace Site Vice president Millstone Power Station Dominion Nuclear CT PO Box 128 Rope Ferry Road Waterford, CT 06385 2508 Quality Lane Knoxville, TN 37931 865 690-6819

Reference:

Emergency Services Letter of Agreement D.ear Mr. Scace, This letter serves as our Letter of Agreen:ient to provide assistance in the event of an emergency. We have 16 gamma detectors and 40 gross alpha/beta proportional counters which are used for gross alpha/beta, 1-131 and Sr-89 and Sr-90 counting. During an accident 'v'."e could dedicate a large portion of these detectors to provide fast turnaround analysis. Table 1 lists the types of analyses; number of each analysis which can be performed on a one-day, two-day or three-day b!'lsis; sample and detection Table 2 liSl!:s typi!::a! .. ,

• We could be contacted at any time in the l'Nti;it*of an emergency.

The !Q;ecfpe!'Solis ahd telephone numbers can be called in the order listed:* Teledyne Brown Engineering Keith Jeter Marty Webb Rebecca Charles (8Q5) 690-6819 (865) 934-0373, (865) 621-9118 (cell) (865) 934-0375, (865) 776-0573 {cell) (865) 934-0379, (865) 924-6041 (cell) This agreement letter shall remain in effect until cancellation by either party, provided on a ninety (90) days prior written notice, and shall be reviewed and certified as needed. If you need additional Information, you may contact me at the above numller. Sincerely K;ik rrot Keith Jeter Operations Manager Enclosure B-10 Millstone Station Emergency Plan Revision 53 April2016 .. -:.. AppendixB BROWN ENBINEERING, INC * .AToTodyrta Tablel Emergency Analytical Services Days for Analysis Matrix Analysis Gamma.scan 1-131 in Charcoal 1 Milk, Water 1 Other 1 Tritium Water 1 1-131 Miik, Water 3 vegetation 3 Gross Beta Air Particulate 1 Total Strontium Milk, Water 2

• Based on a volume of200 Cubic Meters B-11 Detection Level .04 pCi/Cu.M"' (Cs-137) 5 pCi/L (Cs-137) .05 200pCi/L 1.0 pCl/L .05 pCi/g .01 pO/Cu.M* 1.0 pCi/L Quantity 20 20 30 20 80 20 ...... :. "" -:-*-.. .. *:--*---"'" 'l .-.1 __
• Millstone Station Emergency Plan Revision 53 April 2016 AppendixB Emergency Analytical Services Table2 Analysis Medium Gamma WaterorMUk 41lters Milk 4 liters Soil SOD grams veaetation 500grams Tritium Water 100ml 1*131 Milk 4 llters Ve!le!ation 500!lrams Gross Beta. Air particulate As sampled Water 1 liter Soll 50 grams Total Strontium Water or Milk 1 liter If the above volumes are not available, samples can be run at lower volumes. Detection levels may be elevated or turnaround times increased with reduced sample volumes. ' B-12 Millstone Station Emergency Plan Revision 53 April 2016 I. AppendixB
• . .

Arnhulanc.e Servke, lnco:rponded , 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 wi.*.h Waterford Fire Service and with the Waterford Police Department in accordance with standad ,;, ; Information h\":c'.rng'!/Poin1s of Verification of communication to the site may be by telephone to the Control Room or emergency operatibns Training and Drills We would appreciate and welcome notificalion of the plant drills or addilional training which you feel would be advantageous to us. Please do not hesitate to contact me should you have any question or concerns Sincerely, Steueu'D. President, Waterford Ambulance Service Coples distributed David Smith, Manager, Miiistone Emergency Preparedness Department Daniel Steward, First Selectman, Town of Waterford U. Stephan Bellas, Waterford Police Department/ Emergency Management Director 204 lluslon l'osl 1{011<1, l),O. Uox 137, Wnte1:fol'd 06385 B-13 Millstone Station Emergency Plan Revision 53 April2016 ,,- AppendixB August 6, 2015 Mr. Jolin Dougherty Millstone Power Station Dominion Nuclear Connecticut Rope Ferry Road Waterford CT 06385 Dear Mr. Daugherty Thi$ letter i$ lo con!irn1 that personnel end equipment for the Waterford !'Ire service will, whe11 requested, respond in the event of an emergency at Millstone !lower Station. Implcmcntalion Criteria/Authorities. Responsibilities It is our understanding that, in tho event of au emergency, the Millstone SWft Manager//Jircctor of Slallon Emergency Operations I d<isignco may request pcrsom1cl and equipment to lmndlo the omctgcncy. Assistance sho11I1l be rcquoslccl by calling the Waterford E11iergcncyCom1miniealions Center (91 J), or by other 111eans that 11111y be provided. Aclions 0111* commitment for osslsronce is to 1*espo11d to the best of our ability with perso11nel and equipment ht the event of a tire emergency or a rescue at Miiistone Power Statlo11 Complex and attempt to control the sltuation with the resources that may be available. We will request tho assistance of regional amt sla\o assets as needed.* i:n Ibo event 11f a large s1:nle incident 01* host lie action based event, we will coordinate establishment l)f Incident Command with 1::1e '"O::i:<ot*. t;:..-,J)afrnei.1*, l'ei/Olt* ., s\;\>:; a:"i,:\.f< V.ss: .<g;

• Information ofContnct Veriflcntlo11 of co111111u11ic*111ion to the nuclear facility will be by telephone to the Control Room or Director of Station limergency Operntions/Designee.

Training and Drllls \Ve would appreciate advanced notification of the plant drills or additional lnlining which you feel would be advantageous to us. This notification should also Include any additional security requirements tl1iit are being implemented nt rho Millstone nuclear facility. This letter ofngrcemcnt shall remnin in effe1:t until cancelln1ion by either party, provided on 90 days prior to wrillen notice, and shall be reviewed nnd .eertlf1ed llS needed. Sincerely, .Bruce A. Miller Director of Fire Services co: Dnvld Smith, Mnnuget; Mll'8tone Emergency l?repnredness Depar1me111 Dmlicl Steward, First SelectlllM, Tow1\ of\Vnterford Lt. Stephan Bellos, Waterford Police Depattment/ l:lmcricncy Management Director President Sloven Garvh1, Waterford Ambulunce Service B-14 Millstone Station Emergency Plan Revision 53 April2016 Brett Mahoney Ch ie.f 01' Policu Sept em bcl' 14. '.1.0 I 5 Mr. John Dougherty AppendixB WATERFORD POLICE DEPARTMENT 41 AVERY LANE WATERFORD, CT 06385-2819 Dominion Nuclcm* CT, Millslone Power S!ation P. 0. Box 128 W11terford, CT 06385 .Deur Mr. Douglu:rly: (8l50) 442*9451 TEL bmahoncraP\VL\tcrfordct.org This feller is to confil*m Iha! personnel from tile Walcrforcl Polic;e Department sh11ll scrw us t'he primary inw e11lbrcement ngeney which, when requested, will respond lo !he Millstone Pllwer Station. ln the event of 1111 emergency; the Millstone Shill Mmiager/Dircctor of Station Emergency Operations I dcsignec mny request personnel and equipment from the.Wate1ford Police Ocpar1111cin1 by utilizing tht:' established hot lines wilhin the Wat.crford Emergency Con1111unication Center, calling lite Wnterford Emergcncy Communications Ccnter(9l l ), Of' by o!hcr means that may be pmvickcL The Wi1tcrfonl Police J)cparonent's commitment for assisiance to prc1vidc personnel and equipment may include, but not be limited fo, lrnlTic control, secul'ity and/or tactical assistm1.ce. Whcnnssistnocc inform::ticn wil:. be verified by tbe Waterford ()zp u!ilh:ing !i .. vcrill-;;Hion met ho;!, which be coi\duc(cd Ly the mnking Executive Ofliccr cm duly. ln m1 event sllch <!Sa ho:ililc nction based event !ho Waterford mny establish

• com111m1d, request regional.

stalt: mid federal assiswnce and be the initial Singing area tbr ineidcllls involving outside law c11force111cnl agencies. The Waterford Police Department shall be notified of all noteworthy plnnt drills or additional training that would b.e 11dvnntagcous lo law enforcement Tltis response is i11 accordance with criteria as set lh11h in the Fcdcml Rcgulutiom;, HJ CFR, l)m1 73.55, Rcqui1:eme1its for Physical Protection oFt.icenscc Activilics in Nuclear 1>owcr R<:nctors Against* Radiological Sabotogc" and 10 Cl'R. [>mt 37. *'Phyfiical Pmtcc(lon ofCategmy l and Category 2 Quantities or Radioactive Material." lli*cu Malioney Chief or Police cc: Dnvid Smith. Manugc1', Millstone Emergency Deparlmcllt Daniel Steward. First Selcc1111an, Town of Waterford Lt. Stcpheil Bellas. Waterford l'olice Dcpm1ment/ Emergency Mnimgcmcnt Director B-15 Millstone Station Emergency Plan Revision 53 April 2016 ***' . \ -. ' -, >.--... :. . -, *1." * . * -::\ '? d AccuWeather ENTERPRISE SOLUTIONS'* Dominion Nuclear Connect.icut Inc. Millstone Power Station Good Morning: AppendixB November 20, 2015 In accordance with the purchase order on file the service provided includes the following: Telephone consultation is available 24 hours a day 7 days per week with AccuWeather meteorologists as needed in accordance with the letter of statement. The service includes:

• Millstone site specific forecasts as needed during incidents, alerts, and emergencies at the Millstone Power Station. The forecasts will be delivered via Phone call to the station. *AccuWeather will provide Meteorological support for Drills and exercises at the Station. *AccuWeather will supply Meteorological support for Hurricanes severe weather and other significant events potentially effecting the Millstone Power Station.
• AccuWeather will participate in parodic weather forecast simulations with the Millstone environmental staff. The fee per consultation request is $450.00 per request: . We look forward t.o of continued-support wit\"1.t'1e.Millt?.fone Power Station ..

Lou Louis S Seidel Director Business Development AccuWeather Enterprise Solutions 814 2358608 3$5 Science Park Road, State College, PA 16803-2215 P 814.237.0309 f 814.238.1339 E salesClccuweather.c:om __ ...... B-16 Millstone Station Emergency Plan Revision 53 April2016 . . AppendixB I LalJoratoriesLLC I y '** ... a member of Tiie GEL Group 1rm Ni ti \:ha1!ir;tvn. f;G 29*\ 17 20,H) R!A"'!tJ Char iu;;i;JH. SC 2Mfl7 r r,.12.$!\!\.e1i'1 r November 16, 2015 Mr. John Daugherty Vice President Millstone Power Station Dominion Nuclear Connecticut PO Box 128 Waterford, er 06385 Re: Emergency Plan

Dear Mr. Daugherty:

GEL Laboratories, LLC (GEL) is providing this letter to Dominion as a commitment lo provide emergency response radiochemical analysis of environmental samples to assist your organization in the event of an emergency situation or emergency drill. Please note that in the event of an emergency, Dominion will gel.com* be responsible for the SWJ?le analysis costs as well as the sample disposal costs: * * ,*.;, .;, ,; . ?f'!;;<,;:db:.<

cqi

• restcd analysis will be established at the time servicec ;ir} * ,-* ** ;***'l*"*h;,::icf};

aad analysis will be based on GEL's Standard Operating stm1dard tem1s and conditions, which are enclosed, will apply to tbtr .. analysis as well.

• Should you have any questions or need additional information, please call me at 843-556-8171.

probl<!rn solvecl B-17 Anna K. Contract Manager Millstone Station Emergency Plan Revision 53 April2016 City of Norwich Fire Depl 10 North 'l'hames Norwich, Connoctiout 06360 December 1, 2010 Mr. Skip Jordan Site Vice President Millstone Power Station Dominion Nuclear CT

• Rope Ferry Rd. Wi:iterford, CT 06385

Dear Mr. Jordan:

AppendixB Kenneth J. &;!andariato Fire Chief (860) 892-6080 taX-"(866) 886-25?5 .. This letter is to oon:firm. that the Norwich Fire Dcparbnent will, to the best of its ability during a station emergency, fill breathing bottles brought to the Norwich Fire Deparbnent by Dominion Nuclear Connecticut upon telephone request by its Emergency Response Operations. . . *.\ * .. _.,. ....... : Tha Emergency Planning Se-iVices at Sfu.tfon iS .* ',", .. *.:.:. "".-*:*. ""':s;*'til:

.. questions to this agre<;'Jnen?. (Contact Tom .Dlfilibek at 860-440-4,21'3}

• **. * *. * ; ,-,;_,.. ** : :,.";.\i This agreement shall remain in effect until revised, as agreed upon by both parties, or cancelled by either party with 90 clays written notice. KJSljs cc: David A. Smith, Manager Emerg_em:y

Dept, B-18 Millstone Station Emergency Plan Revision 53 April2016

.. AppendixB SOleM. VOLUNTeeR FIRe co. INC. 424 H!lRTFORD ROllD SOLeM, CT. 06420 November 15. 2001 Mr. William R. Matthews Vice President & Sr. Nuclear Executive Dominion Nuclear Connecti,cut P.O. Box 128 Waterford, CT ,06385

Dear Mr. Matthews:

This letter is to confirm that the Town of Salem and the Salem Volunteer Fire Department will, to the best of its ability, during a station emergency, fill breathing bottles brought to the Salem Volunteer Fire Station by Dominion Nuclear Connecticut upon telephone request by its Emergency Response Operations. The Emergency Planning Services Department at Millstone Station is responsible for any questions pertaining to this agreement. (Contact Tom Dembek at 440-4223) Sincerely, Fire Chief Salem Volunteer Fire Department cc: Paul A. Blasioli, Emergency Planning Services Department.

• Millstone StotiotL 'J'l,ot.e 800-850-0042 StotiotL Fill< 800-850-2901 o* ! , B-19 Millstone Station Emergency Plan Revision 53 April2016 AppendixC APPENDIXC MAPS OF PLUME EXPOSURE AND INGESTION EXPOSURE EPZ, LOCATIONS OF ON-SITE AND OFF-SITE RADIOLOGICAL MONITORING STATIONS, STATION EVACUATION ROUTES C-1 Millstone Station Emergency Plan Revision 53 April2016 EMERGENCY PLANNING ZONE EVACUATION ROUTES waterford to East Hartford:

Rte. 85 Nortll tone. 82 Wesl to n .. 1 1 N orth to rte. 2 W est. to ex/I SA (Main Sl) Rig hi *t llght on1o Brewer St 1o In te rsection w ith Forbes SL Len OnlO Forbes SL 10 East H ig h School. OR 1-95 SOU(b to Rt 9 North to North to Exit 25-26 (ne. 3 Nortll). T*k* Exit 25 , cross over Putnam Bridg e to rte. 2 West to Exit SA (Moln SL) Right at light onto Brewer St. to lnt.ersedlon with Forbes SL Left omo Forbes Sl East Lyme , Lyme & Old Lyme to New Haven: South lo Exit 45 to rte. 10 N to Southern Connectiout Sloltl University field house. " Montville to East Hartfctd: Rte. 85 Nol1h lo rte. 82 We st torte.11 Nonh ID rte, 2 w .. t 1D Exit 5A (Main SL). Right at llgh1 omo Brewer St. to lnten;ectlon wfth Fortes St.. Lett onto Forbes st. to East Hartford H.S. OR lymeEPZ North to rte. 2 West IO E x tt 5A (Mai n S t). Rjght at l i g ht onto Br ei.'ler St. lo w ltfl Fo r bes SL Left. on t o fcrbe.s St. to East Hartfo r d H}9h School. New London to Windham: Rio. 32 N ID Frog Bridgt, ne.615. Right 011erbridge , s1ay 11181ght on Jackson St. to left on VaUey st. Twn Oghl onto Htgh SL up hm to Wlndh1m High School. AU areas U<Jt of rte. 1 56 a n d south of Beaver Brook Rd. Island Sound Mon t v i:!.::. " PZ Fishers Island, NY Ledyard EPZ All a r ea.a . _ Hill Rd., Chesterfield Rd .. rt'!. ic3 an ,: t:ep ot Rd. to the-Waterford All areas southolHurlbUU Rd., 11lt Radiological Emerpency Prop1redn.n Ofllfslon offhe COMtctkc.d Department of ErMrgrmcy Management .nd Hometend Secun"ty

• Groton City & Groton Town to Norwich: Rt e. 12 North to rte. 2A West t o 1-31>5 N to E><lt 81 E (n*..2E) to rte. 169 N orth {Har1and Rd.). Right on O* Hil Rd., nt><t right onto Mehan Drtve to Norwich Technlcol High School. OR Rte. 3<19 Nonh (CB Sharp Hwy) tol-95N10rtt

.117Norlhto rte. 2 Wgt to rte. 169 North (Hortand Rd.). Right on Ox t-al Rd. T*ke next right onto M*Mn Orive to NOIWich Technical High Sdloo l. OR Rte. 1 84 E 1o ne. 201 Norih 10 ne. 2W1o rte. 169 N (Harland Rd.). R i ghi at OK H I H Rd., lum right on1o Mah a n Drive to Nor\Jri'lch Technical Hig h Schoo l Fishers Island to Windham: To New London or Ston i ngton Harbor. S tate prov i ded bus transporta U on to W111dltam High School. 6 N 10 and E9. t 1 'fl . .!: : , n lin es l nd l.l d l ng those. Whalehead Rd. and Sandy Ho l ow Rd. l o rte.1 17. Current for 2011 '--------------------------------' --.. 20 Miles N ! 0 = = 0 rl:> ..... ("'.) 0 s s = = .... ..... .... rl:> = Q., M < r') = ..... .... 0 = 0 = ..... rl:> 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) .. '. : *. . C-3 ,; .. :.* .. Millstone Station Emergency Plan Revision 53 April2016 '*; .

• Figure C-3 Map of Millstone 10 Mile Emergency Planning Zone '" .... Distance (0-2m.i) (2-5 mi) (5-10 mi) Zone l Community A l Waterford (A-1) l East Lyme (A-2) B I East Lyme (B-1) I Waterford (B-2)
• iNew London (B-3) .C l East Lyme (C-1) I Montville (C-2)

.. ................... -......................... , ........ D Lyme (D-1) --. ! .. .. ___ , .......... _. _____ .......................... E ! Ledyard (E-1) . .. .. . .......... _ F I Fishers NI A ................ _ ........ _ ... _ ...................... C-4 Millstone Station Emergency Plan Revision 53

• April 2016 Figure C-4 Map Of Millstone 50-Mile Emergency Planning Zones I \.,.,j Connecticut *[Hartford

\ . I l l L ... -, !., 10-Mile Planning Zone\. -..., \ ...... C-5 BLOCK ISi.AN (} 50-Mile Ingestion Pathway Planning Zone Millstone Station Emergency Plan Revision 53 April2016 ALiEttNATE ROUTE VIA BAi..LFlEiO ACCESS ROAD P!U MARY ACC£SS ROUTE . MH.LSTONE ACCESS ROAD * ... _ *c *i'.i -5 Map of Millstolie. Evacuation Routes C-6. . '*:,_._. Station Emergency Plan* ' * ' Revision 53 April2016 ALTERNATE .ROUTE VIA OLD MILLSTONE ROAD AppendixD APPENDIXD SUPPORTING PROCEDURES LIST D-1 '. '*. Mmstone Station Emergency Plan Revision 53 April 2016 AppendixD Procedure Number Emergency Plan Implementing Procedures (EPls) MP-26-EPl-FAP01 CR Emergency Operations MP-26-EPl-FAP02 MP-26-EPl-FAP03 MP-26-EPl-FAP04 MP-26-EPl-FAP05 MP-26-EPl-FAP06. MP-26-EPl-FAP07 MP-26-EPl-FAP08 MP-26-EPl-FAP09 . MP-26-EPl-FAP10 MP-26-EPl-FAP12

MP-26-EPl-FAP14 TSC Activation and Operation OSC Activation and Operation EOF Activation and Operation State Emergency Operation Center (EOC) Activation and

• Operation
• Classification and PARs Notification and Communications Evacuation and Assembly
• Radiation Exposure Control Dose Assessment Core Damage Assessment Thermal Hydraulic Evaluation Recovery Emergency Plan Section(s) 5.1 5.2, 5.3, 7.3* 5.2, 5.3, 7.4_ 5.2, 5.2.14, 5.2.16, 5.3, 7.2 . 5.2, 5.2.1.4, 5.2.1.6, 5.3 4, 5.2.1, 6.2, 5.2.5 5.1, 6.1 6.4.1 6.4, 6.5 6.2.1, 6.2.3 6.2.4 5.2.18, 5.3.13 -9.0 .. : MP-26-EPl-FAP18 Innsbrook Corporate Support Center 5.4* Offsite Incident Command Post (ICP) Activation and Operation NIA Emergency Pl.an Procedures MP-26-EPA-FAP01 Management Program for Maintaining Emergency Preparedness MP-26-EPA-FAP05 MP-26-EPA-FAP07 MP-26-EPA-FAP08 MP'-26-EPA-FAP09 MP-26-EPA-FAP10 MP-2ff-EPA-FAP11 MP-26-EPA-FAP12 MP-26-EPA-GDL02 MP-26-EPA-GDL03 MP-26-EPA-GDL05 MP-26-EPA-GDL06 Emergency Planning Facility Maintenance Emergency Preparedness Departmental Staff Qualifications Public Ale.rting System Administration Public Alerting .system Test and Maintenance Public Alerting System Siren Test and Repair Public Alerting System Siren Acousticcil Performance Testing Public Alerting System Field Acoustical Measurement (Community Test) Document Maintenance and Storage Station Emergency Response Organization Qualification Maintenance Emergency Response Data System (EROS) Change Process OFIS 7.0,8.0. 7.0, 7.5 NIA 8.2 8.2 8.2 *8.2. 8.2 NIA NIA NIA 7.1, 7.2, 7.3 D-2. Millstone Station Emergency Plan Revision 53 April2016 Procedure Number MP-26-EPA-GDL07 MP-26-EPA-REF01 MP-26-EPA-REF02 MP-26-EPA-REF03 MP-26-EPA-REF04 MP-26-EPA-REF08B Fleet Procedures EP-AA-101 EP-AA-102 EP-AA-103 EP-AA-104 EP-AA-303 EP-AA-400 EP-AA-505 EP-AA-600

- \, .* ,H*,< AppendixD Title SERO Database and ENRS System Modifications Millstone Unit 1 Defueled Emergency Action Level {EAL) Basis Document Millstone Unit 2 Emergency Action Level (EAL) Basis Document Millstone Unit 3 Emergency Action Level {EAL) Basis Document Off-Site Programs Millstone Emergency Planning Resource Book 10 CFR 50.54(q) Change Evaluation Revision and Control of Emergency Plan, Emergency Action Levels (Technical Basis and Matrix), and Reference Manual Emergency Preparedness Performance Indicators Emergency Preparedness Steering Committee Equipment Important to Emergency Response Drill and Exercise Program B.5.b Program Emergency Plan Offsite Interfaces Emergency .Press Releases * *, Cyclic and Prompted Emergency Preparedness Tasks Emergency Plan Section(s) N/A N/A N/A N/A 8.0 8.2.1 N/A N/A N/A N/A Various 8.2 N/A f\l!f\. Nuclear Training Procedures TR-MP-TPG-2300 Millstone Fire Protection Program, Training Program Guide 8.1.3 TR-MP-TPG-2400 Emergency Plan Training Program Guide 8.1.1 Radiation Protection/Radiation Monitoring RPM Section 2.3.4 Inspection Maintenance Process for Respiratory Protection Equipment Various RP-AA-163 REMP Section 2.1 REMP Section 2.6 REMP Section 2.4 REMP Section 2.7 RPM Section 4.8.5 REMO DCM Inspection and Inventory of Respiratory Protection Equipment Various Sample Identification and Transmittal to the Contractor

6.2.4 Analyses

Terrestrial Biota Sampling 6.2.4 Soil Sampling 6.2.4 Terrestrial Water Sampling 6.2.4 Emergency Radiological Equipment Maintenance and Various Inspection Radiological Effluent Monitoring and Off-Site Dose Calculation Figure C-2, Manual Appendix H D-3 Table H-2 Millstone Station Emergency Plan Revision 53 April2016 iAppendixD Procedure Number Millstone Unit-2 Severe Accident Management Guidelines (SAMG) SAMG 4211 Phase 1 Initial Diagnosis SAMG 4212 Phase 2 Verification of Diagnosis SAMG4213 Phase 3 CHLA Implementation SAMG4214 Phase 4 Restorative Actions SAMG 4215 Calculational Aids E:DMG 2.01 MP2 B.5.b Event Initial Response EDMG 2.02 MP2 B.5.b Event TSC Response Millstone Unit-3 Severe Accident Management Guidelines (SAMG) SACRG-1 Severe Accident CR Guideline Initial Response SACRG-2 $ACRS-$ SAG-1 SAG-2 SAG-3 SAG-4 SAG-5 **SAG-6 SAG-7 SAG-8 SAG-9 SCG-1 SCG-2 SCG-3 SCG-4 SAEG-1 Severe Accident CR bi::* Activated

• *,: Severe Accident CR Response Injection into the Steam Generators Depressurize the RCS Inject into RCS Inject into Containment
• Reduce Fission Product Releases Control Containment Conditions Reduce Containment Hydrogen Flood Containment Severe Accident CR Guideline for MP3 :B.5.B TSC Event Response
• Mitigate Fission Product Release Depressurize Containment Control Hydrogen Flammability Control Containment Vacuum TSC Long Term Monitoring

' Emergency Plan Section(s) 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 . 5.2.2, 5.1.3, 5.3.12 . ' 5.3.12'. ' . 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5:a.12 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 D-4 Millstone Station Emergency Plan Revision 53 April2016

• Procedure Number SAEG-2 CA-1 CA-2 CA-3 CA-4 CA-5 CA-6 CA-7 DFC SCST AppendixD Title SAMG Termination RCS Injection to Recover Core Injection Rate for Long-Term Decay Heat Removal Hydrogen Flammability in Containment Volumetric Release Rate from Vent Containment Water Level and Volume RWST Gravity Drain Hydrogen Impact when Depressurizing Containment TSC Diagnostic Flow Chart Severe Challenge Status Tree Common Operating Procedures COP 200.2 C OP 200.2AIR COP 200.3 CSP 600.1 CSP 600.2 CSP 600.re *: ..
• CSP 600.4 CSP 600.20 Response to Security Events Airborne Threat Response to Medical Emergencies Paging Evacuation Alarm System Operability Test Communications-ENRS/ARCOS and Callback Monthly Test .. **.

Felice and Waterford Police Radio Systems OpernoiUty

• ' °1-"1'"Sl Communication-Radiopaging and ENRS/ARCOS Practice Test Communications-Emergency Response Data System EROS Operability Test Chemistry Department Procedures CP 3804K PASS RCS/RSS Sample (Unit 3) CP 3804AC CP 3804L. CP 3804M CP 2804L CP 2804M Liquid Waste Sample Sink (Unit 3) . PASS Containment Air Sample (Unit 3) PASS Ventilation Samples (Unit 3) Unit 2 Reactor Coolanf and Liquid Waste PASS Unit 2 Vent and Containment Air PASS Emergency Plan *
• Section(s) 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 6.4.1 6.4.1 6.5.4, 6.5.5 8.2.1 8.2.1 : . ' ' * * * ****

_..,. ' *,* j>,' ,:" .". 8.2.1 8.2.1 N/A N/A N/A N/A N/A N/A D-5 Millstone Station Emergency Plan Revision 53 April2016 AppendixE APPENDIXE MILLSTONE EMERGENCY EQUIPMENT E-1 Millstone Station Emergency Plan Revision 53 April2016 AppendixE Figure E-1 Millstone Emergency Equipment Summary<6> Emergency Item Control TSC/ NAP/ Ambulance EOF RMT RMT Room osc SAP Kit Kit 1 Kit2 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-110 vac x x* x<?> Air Sampler-12 vdc x x<7l x Area Radiation Monitor x x L-2241-2/HP-210 (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<2> (5) (5) Emergency Dosimetry x x (5) x x x x Protective Equipment I Materials 3 : Respirators x x x. .x (5) (5) SCBA x x Fire Fae Clothing_ __ ._ ___ x x x x x : De<;o!l5m:.natk>n );4ai:iCJric:}.!;

• x t-_r __ ,_ ,---.

.. -,{ * .... -'.*.:..-.--*--* .. -< -* L .Ool")trcl l Decon Matarit1I __ x .. .

<.. .. .. Potassium*

Iodide Tablets U2,U3 x x x x x Communications Eauioment 3 : Dedicated Telephone Lines U2,U3 x x Emergency Radios x x x Satellite Phones U2,U3 x x Emergency Suoolies I Materials 3 : Emergency Preparedness Procedures x x x x x x RMT Vehicles x<2> 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-FAP05, EP Facility Maintenance.) (7) 11 Ov -RMT1 (U2,3 CR) TSC/OSC 12v -NAP/SAP over water E-2 Millstone Station Emergency Plan Revision 53 Aprll2016. AppendixF APPENDIXF DIAGRAMS AND ARRANGEMENT OF EMERGENCY FACILITIES ., '* **'J"* . ,,, *

• ',* ***o ; * *

.* .,_ ... '*; *r.o .. -.,.,.

• 1 * ,_._., *.. ->' ** F-1 Millstone Station Emergency Plan
• Revision 53 April 2016 Figure F-1 Diagram of TSC I OSC Layout NRC Work Area TSC Entrance from Unit3 Technical Support Center
• H\fft,;J.

Not to Scale-Typical

• Layout F-2 Electrical EqptRoom Lavatory Operational Support Center . .

...... I"*,

• Millstone Station Emergency Plan Revision 53 April2016
• ',::

Figure F-2 Diagram of Emergency Operations Facility Boifer Mechanical Switchgear UPS Roo Computer Room Alternate TSC/OSC RL NRC EOC F-3 RMTStorage Muster Are ill IRMT .Garage Entrance Millstone Station Emergency Plan Revision 53 April2016 Office Areas Drawing not to scale-Figure F-3

• Diagram of OSC Assembly Area Layout Building475 Walkway Walkway Cafeteria Kitchen Area OSC Assembly
• Area-Conference Room-102 ';,-,. Millstone Station Emergency Plan Revision 53 April 2016 * ,. '.,.,.:.*.,.17;.

>'. <:, AppendixG APPENDIXG CROSS-REFERENCE TO NUREG-0654 CRITERIA G-1 ::"-* Millstone Station Emergency Plan RevisiOn 53 April2016 Planning Standard AppendixG Summary of Planning Standard A. ASSIGNMENT OF RESPONSIBILITY (ORGANIZATION CONTROL) A.1.a A.1.b A.1.c A.1.d" A.1.e Identify State, Local, Federal and private organizations who are part of emergency plans. . Each organization !?hall specify its concept of operations and relationship to total effort.

• Illustrate relationships by block diagram. Title of individual in charge of emergency operations.

Provide for 24 hr./day emergency response and manning of communications. A.2.a Specify functions and responsibilities for major elements and key individuals by A.2.b Each plan shall contain the legal basis for such authorities. A.3 Include written letters of agreement. Include concept of operations, emergency measures to be provided, criteria for implementation and exchange of information. A.4 Title of individual responsible fOr assuring continuity of resources. B. ON-SITE EMERGENCY ORGANIZATION Plan Cross Reference (Section or Item) 1.1, 1.2, Table 1-1, Figure 1-1, Appendix B, Table 2-1 Sections 1, 5, 6, 9 Figures 1-2, 5-1, 7-1a, b,c 5.2.1, Figure 5-1 Section 5.0 N/A-State and Local requirement only. NIA-State and Local requirement 5.4.1, 5.4.2, Appendix 8 5,2.17, 5.4".3 .. 's_it_e_e_m_e-rg-. .. 8.2 coordinato*r 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. . 8.4 B.5 B.6 B.7 B.7a B.7b B.7d Specify functional responsibilities of emergency coordinator; Specify responsibilities which cannot be delegated (e.g., may not delegate the decision to notify and to recommend protective actions to authorities).

• Specify title and corresponding qualifications of emergency personnel.

lnelude 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. Specify interfaces between on-site and off-site organizations. Illustrate in block diagram. Specify corporate organization. Provide a t8:ble similar to B-1. Logistics support for emergency personnel Technical support for planning, reentry, recovery Management interface with government authorities Release of information to news media 5.1.1, 5.2.1 Table 5-1 1.2, Figures 1-1, 1-2, 1-3, 5-1 5.0, Table 5-1, Figure 5-1 5.2.17 Section9 6.1, Figures 7-1a, c 5.2.14, 5.2.16 G-2 Millstone Station Emergency Plan Revision 53 April2016 Appendix.G Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) 8.8 Specify private organizations and contractors who would provide 5.4 assistance.

8.9 Specify

services _to be provided by local agencies. Include 6.3.1, 6.4.1.b, 6.5.5, transportation and treatment of injured personnel who may be 6.5.6 contaminated.

8.9 Append

letters of agreement with contractor, local, and private 7 .10, Appendix 8 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. C.1.a C.1.b C.1.c C.2.b C.3 C.4 Specify persons by title authorized to request federal assistance. Specify federal resources expected, including expected times of arrival at specific nuclear facility sites. Specify resources available to support the federal response. Licensee may dispatch a representative to principal off-site governmental EOCs. Identify radiological laboratories, capabilities, and expected availability. Identify facilities, organizations, and individuals which can be relied upon in an emergency

• 1.2, 1.4 1.4, 5.4.3 1.4, 5.4.3 1.41 5.4.3 5.2.15, 5.2.16 7.10, Table H-2, Appendix 8, Table H-1 Table H-2, Appendix 8 D. EMERGENCY CLASSIFICATION SYSTEM -* ***' * -***-C*---'*

.. ****: *** .* . -----,,....------:---*-------------------. .._ .. ***. '?*. , *. ,

• -

.. '?-**"'.--*. { 1 ** **Establish EAL scheme per Appendix *1. * * -:_-_

• r;,,.-I . . ' . \'
• 2, 4-3 4-4, f
• 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 consistent with Appendix 1. Provide verification of messages.

1.3, 6.1 E.2 E.3 Establish procedures for notifying, alerting, and mobilizing emergency response personnel. Initial emergency message shall include: class of emergency, whether a release .is taking place, potentially affected areas, whether protective measures may be .necessary: 6.1 6.1 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. G-3 Millstone Station Emergency Plan Revision 53 April2016 '* AppendixG Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) F. EMERGENCY COMMUNICATIONS F.1 Identify organizational titles and alternates for communications 1.3, 6.1, Figures 7-1a, links. Establish primary and backup communications. 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, Figure 7-1a 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 field assessment teams. 7-1a, 7-tc F.1.e Provide for alerting and activating emergency personnel. 6.1 F.1.f Provide communications to NRC Headquarters, NRC Regional Figure 7-1b, 7-1c Office EOC, 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. '**" .. r---*** . -'!"'"- .. '-* ,. .. "'"\ -** l.

• must reach population wiWn
• f. ):'

. . . *. **r f

t:i.,(i . J irlclu<ie

\<tritten material that would likely be availa'!Jle

• . * . . emergency.

Updated information should be dissemb9ted . 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 TSC and OSC 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 for 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 G-4 Millstone Station Emergency Plan Revision 53 April2016 AppendixG Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) H.5.b Radiological 6.2.3, Table H-1, Figure C-2 H.5.c Process 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 . Estc;1blish central point for receipt anc;f, of fiiz!d

• *

' .. :u. W:data associated with EOFl a{Ki

$, H-2* ;;.,,;, * :::;>;,,,;.: . t !--->--. f* media. I ... **

• h:: I. ACCIDENT ASSESSMENT i.1 1.2 Cont'd Cont'd Cont'd Cont'd 1.3 1.3.a 1.3.b 1.4 Provide EALs and corresponding .emergency ,class. Section 4, Tables 4-1, 4-2, 4-3, 4-4 and Appendix I On-site capabilities to provide initial values and continuing N/A assessment (per NUREG-0578 and NRG letter of 10/30/79) including:

' Post-accident sampling capability AppendixD Radiation and effluent monitors Table H-1 In-plant iodine instrumentation Table H-1 *containment radiation monitors Table H-1 ' I Establish methods and techniques for determining: ' NIA Source term (e.g., relation of containment radiation monitors and 6.2.3, Appendix D m.aterial available for release.) Magnitude of release based on plant parameters and effluent monitors. Establish relationship between effluent monitor readings and exposures and contamination for meteorological conditions. G-5 6.2.3, Appendix D 6.2.3, Appendix D, 6.2.4.c Millstone Station Emergency Plan Revision 53 April2016 Planning Standard AppendixG Summary of Planning Standard 1.5 Acquire meteorological information per Appendix 2. Provide meteorological data to EOF, TSC, CR, and off-site NRC center. Make available to the State suitable meteorological data processing interconnections.

1.6 Determine

release rate/projected doses if instruments are scale or inoperable. I. 7 Field monitoring within plume EPZ. 1.8 Provide for rapid assessment of radiological hazards. For field teams include: activation, notification, composition, transportation communication, monitoring equipment.and deployment times. 1.9 Have capability to detect radio-iodine in air as low as 10-7 µCi/cc. 1.10 Relate measured parameters to dose rates. Estimate integrated dose from dose rates and compare to PAGs. J. PROTECTIVE RESPONSE J.1 Establish means and time to warn individuals in owner-controlled J.2 J.3 areas. Provide evacuation routes and transportation for on-site individuals to off-site locations, including alternatives. Provide radiological monitoring for people evacuated from the site. Plan Cross Reference (Section or Item) 6.2.3, 6.2.4.d, 7.13 6.2.3, 6.2.4 6.2.3, 6.2.4.h 6.2.3, 6.2.4.h, Appendix D 6.2.3, 6.2.4.h.4 6.2.3, 6.2.4.c, 6.2.4.e 6.4.1 6.4.1 6.4.1.i J.4 Provide evacuation of on-site non-essential personnel in Site 6.4.1.d, 6.4.1 .. . . . Area Emergency. PrQvide ... . * . .. .. * .-* * ** *

• f ** :*" ......

.. individuals ..... 6 .... .4 ..... =.1."""h"""'._... ... +* """***'----'--u t -t* J.6 J.7 Cont'd J.8 J.10 J.10.a J.10.b J.10.c J.10.m individuals within 30 minutes. Account for all individuals

• continuously thereafter.

Provide for individuals remaining or arriving on-site, Tespiratory

• protection, protective clothing, radioprotective drugs. Establish a mechanism for recommending protective actions to state/local authorities per EALs of Appendix 1 and Tables 2.1 and 2.2ofthe EPA PAGs. Provide prompt notification to off-site authorities .in plume EPZ as specified in NUREG-0654, Appendix 1. Time estimates for evacuation in plume EPZ in accordance with Appendix4.

Plans for protective measures to include: Maps Population distribution Means for notifying population Public protective strategies from plume exposure. 6.4.3, 6.4.4, 5.2.2, 5.2.5 1.3, 6.2.1, 6.2.2, 6.2.3, Figure 1-1, Table4-4 Section 4, Tables 4-1, 4-2, 4-3, 4-4, 6.1, Figures 7-1a; b, c Appendix J Appendix C AppendixJ 1.5, 6.1 6.2.1 G-6 Millstone Station Emergency Plan

• Revision 53 April2016 AppendixG Planning Summary of Planning Standard Plan Cross Referen standard (Section or Item) K. RADIOLOGICAL EXPOSURE CONTROL K1 Establish on-site exposure guidelines for: K.1.a Removal of injured persons 6.5 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 J 5.2.1 J 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 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.p Establish means for radiological decontamination of personnel, 6.4.3. 1 . . :r_supplies, equiprnept, and waste dis12osal. .);, K.6* .. eontrol'; including: ... .*. .... **,**:*:*** '-*-.. -**-,. _.,._ . ..,,. ___ $;;_,.,...-:--"" __ . . . . K.6.a : Area access* control 5.2.2, s*.2.5, 6.4.1, 6.4.3 K.6.b Drinking water and food supplies 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 personnel, 6.5.3 including extra clothing and decontaminates (particularly for radio-iodine contamination) .. L. MEDICAL AND PUBLIC HEAL TH SUPPORT L.1 Describe hospital and medical services, including preparations to 6.5.4, 6.5.5, 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. G-7 Millstone Station Emergency Plan Revision 53 April 2016 ' *, ** ... :. "'\ ... ... .. h AppendixG Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) 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. Section 9 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 N.1.b N.2 N.2.a N.2.b N.2.c Conduct an exercise as set forth in NRC and FEMA rules. Include mobilization of state and local resources. Provide for critique by Federal and State evaluators Conduct drills, in addition to the annual exercise, at the frequencies indicated. Communication drills (Quarterly), FEMA -IP State Fire drills -per technical specifications Medical drills -annually to include contaminated individual, ambulance, and off-site medical help. (Off-site portions may be part of annual exercise). 8.2.2.f 8.2.2 8.2 8.2 8.2 8.2 N.2.d Radiologica1*monitoring -annually (include collection and analysis 8.2 . of sample media). . * . . * . * , * . ..-. :*. .* ,. . .. . . *. ,, .. .. .. _1* *. Physics -*semi-annually to

• ' * * '*<environmental samRles; analyze actual
• J*--. . * . .-*;, * * .... -* N.3 N.4 N.5 with elevated radiation levels. . Describe the conduct of drills and exercises.

Official observers from Federal/State/Local governments critique exercises. Hold critiques. For:mal evaluation based on critiques. Establish means and management control for incorporating observer's comments into plan and implementing corrective actions. ** ' 8.2 8.2.2.g, 8.2.2 0. RADIOLOGICAL EMERGENCY RESPONSE TRAINING 0.1 0.1.a 0.2 Make provisions for training appropriate individuals. Provide training to off-site organizations Training for on-site organization to include drills in which individuals demonstrate abilities. On-the-spot corrections to be made and instructor to show proper performance .. 8.1 8.1.2 8.2 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 OA.b Personnel responsible for accident assessment 0.4.c Radiological monitoring teams G-8 8.1.1 8:1.1 8.1.1, 8.1.2 Millstone Station Emergency Plan Revision 53 April2016 AppendixG Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) 0.4.d Police, security, and fire-fighting personnel 8.1.2 0.4.e On-site repair and damage control/corrective action teams 8.1.1 0.4.f First aid and rescue personnel 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 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 P.2 P.3 P.4 P.5 P.6 .. \' P.7 P.8 Cont'd P.9 Cont'd Cont'd Cont'd P.10 Train individuals responsible

• for planning effort. Section 8 Identify by title, individual with overall authority responsibility
• Section 8 for radiological emergency response planning.

Designate Emergency Planning Coordinator. Section 8 Review and certify plan annually. Update plans as needed. 8.3 Incorporate changes identified by drills and exercises. 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. Each plan shall contain a detailed list of s1Jpporting plans their somce . '* .'."""10" ,,,,, ,*,;**

• , " , , ,

... J""!) ..... In appendix, list, by title,

il*nt!:'!et:r.et'fHtre Appendb(D. " plan, including

• sections of the plan to be implemented by procedures.

Include specific table of contents and index. Table of Contents Cross reference to NUREG-01;)54 criteria AppendixG Conduct independent reviews at least every 12 months and 8.3 include: Plan, procedures, practices, training, readiness, testing; 8.3 equipment.and interfaces with State and Local governments. Include management controls for implementation and correction 8.3 of audit findings. Document reports to management and involved Federal, State 8.3 and Local organizations. Retain for 5 years .. Provide for updating telephone numbers in emergency 8.2.1.a procedures at least quarterly. G-9 Millstone Station Emergency Plan Revision 53 April2016

• *-*** .

AppendixH APPENDIXH RADIOLOGICAL ASSESSMENT EQUIPMENT AND FACILITIES H-1 _:;-,, . ,, Millstone Station Emergency Plan Revision 53 April2016 TableH-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector 1. 1. Monitors Meteorological Tower 4 Wind speed indicators 4 Wind direction indicators 3 Delta temp. sensors Meteorological Mast 1 Wind speed indication 1 Wind direction indicator Time History Containment base slab (Unit 2) Accelerographs Auxiliary building Intake structure Free field Peak Accelerographs Containment base slab Steam generator support Pressurizer support . Safety injection tank support Seismic Trigger Containment base slab Response Spectrum Containment base slab Recorder Radiological Monitors Unit 1 Process Monitors RM-SFPl-02 Unit 2 Process Monitors RM8123A Containment recirculation air particulate RM8123B Containment

• recirculation air gaseous RM8262A Containment . recirculation air particulate RM8262B Containment recirculation air gaseous . . RM8434A Radwaste ventilation particulate RM8434B Radwaste ventilation gaseous H-2 Individual Applicability Monitor wind speed at 33', 142', 374', and 447' elevations Monitor wind direction at 33', 142', 374', and 447' elevations Monitor temp. difference between . 33' and 142' 33' and 374' 33' and 447' Monitor wind speed at 33'. Monitor wind direction at 33'. Record ground accelerations with
• respect to time II II II II II II Record peak ground accelerations II II *" '* II ... Activate an annunciator Records ground accelerations Measure gaseous activity Monitor particulate activity Monitor gaseous activity Monitor particulate activity Monitor gaseous activity Monitor particulate activity Monitor gaseous activity Millstone Station Emergency Plan Revision 53
• April2016

','.,;:-' Table H-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

• M.easure 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 range RM8168B range RM5099 Steam jet air ejector RM9095 Waste gas storage tanks discharge gaseous RM4262 Steam generator blowdown RM6038 Reactor building closed cooling water . RM9049 Clean radwaste discharge RM9116 Aerated radwaste discharge RM9327 Condensate recovery tank 2CND-RE245 Condensate polishing neutralizing sump RM-8169 Wide Range Gas Monitor H-3 Monitor high level gaseous activity ' . . ' '

-.

• Monitor gaseous activity
• Monitor gaseous activity Monitor liquid activity Monitor liq.uid activity Monitor liquid activity Monitor liquid activity Monitor liquid activity Monitor liquid activity Monitors particulate and gaseous radioactivity Millstone Station Emergency Plan Revision 53 April2016 TableH-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector Unit 3 Process Monitors 3HVR-RE10 A & B Ventilation Vent 3HVR-RE11

&12 (A&B) Auxiliary Building (lower levels) 3HVR-RE13, 14 & 15(A&B) Auxiliary Building (upper levels) 3HVR-RE16 (A&B) Charging Pump Cubicle 3HVR-RE17 (A&B) Fuel-Building 3HVR-RE18 (A&B) Waste Building 3HVR-RE19 (A&B) SLCRS 3HVR-RE91 (A&B) Control Room ** 3HVQ-RE49 ESF Building 3CMS-RE22 A&B Containment Atmosphere Individual Applicability Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous activity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous activity

• Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity

-, 3HVZ\:.REO$F'A&.B Hyardt;;erJ;i'; Recombiner Cubicles 3HVC-RE16 A&B Control Monitors gaseous radioactivity Building Inlet ventilation 3MSS-RE75, 76, 77, 78 4 Main Monitors gaseous radioactivity Steam Relief lines 3ARC-RE21 Condenser Air .Ejector 3GWS-RE48 Hydrogenated Vent 3MSS-RE79 Turbine Driven Auxiliary Pump

• Discharge 3SSR-RE08 Steam Generator Slowdown 3CCP-RE31 Reactor Plant Component Cooling 3CNA-RE47 Auxiliary Condensate 3LWS-RE70 Liquid Waste H-4 Monitors gaseous radioactivity Monitors gaseous radioactivity Monitors gaseous radioactivity Monitors liquid radioa 1 ctivity Monitors liquid radioactivity Monitors liquid radioactivity Monitors liquid radioactivity Millstone Station Emergency Plan Revision 53 April2016 ;.$;:

TableH ... 1 On-Site Assessment Equipment and Facilities Functional System Unit 3 Process Monitors (Cont'd) Unit 1 Area Radiation Monitors Unit 2 Area Radiation Monitors Instrument Detector 30AS-RE50 Turbine Building Drains* 3LWC-RE65 Regenerant Evaporator RM-SFPl-01 RM-7892 Drumming and decontamination area Individual Applicability Monitors liquid radioactivity Monitors liquid radioactivity Monitor Radiation Levels Measure radiation levels RM-7894 Engineered Measure radiation levels safeguards systems area RM-7895 Sampling area Measure radiation leyels 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) HM-8157
• *.'
• wall) RM-8240 Containment High Radiation RM-8241 Containment High Radiation 2-RMS-9813 Drumming area 2-RMS-9799A Control Room ventilation air supply 2.;RMS-97998 Control Room Ventilation air supply 2-RMS-04 (not in use) solid waste 2-RMS-05 (not in use) Condensate demineralizers 2-RMS-06 (not in use) Access area 2-RMS-08 (not in use) Evaporator H-5 Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Millstone Station Emergency Plan Revision 53 April 2016 Functional System Unit 3 Area Radiation Monitors TableH-1 On-Site Assessment Equipment and Facilities Instrument Detector Individual Applicability 3RMS-RE01 Manipulator Crane Measure radiation levels 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 Measure radiation levels PiUHoist 52'4" Fuel Bldg . . 3RMS-RE09 Aux. Bldg. General Measure radiation levels 18'6" Aux. Bldg. 3HMS-RE1 o Aux. Bldg. General rt1dlafiJn '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. Measl!re radiation levels 3RMS-RE18 Waste Disp. Bldg. . radiation levels 4'6" Waste Bldg. 4RMS-RE19 Solid Waste Measure radiation levels Storage 24'6" Waste Bldg. 3RMS-RE20 Sample Room Measure radiation levels 43'6" Aux. Bldg. H-6 Millstone Station Emergency Plan Revision 53

• April2016 TableH-1
• On-Site Assessment Equipment and Facilities Functional System Unit 3 Area Radiation Monitors (Cont'd) 2. Radiation Monitors and Sampling Equipment Instrument Detector 3RMS-RE21 Service Bldg. Laboratory 24'6" Service Bldg. 3RMS-RE22 Control Room Monitor 47'6" Control 131dg. Individual Applicability Measure radiation levels Measure radiation levels 3RMS-RE24 Waste 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" (Normal Range) 4'6" ESF Bldg. 3RMS RE34 R ,_,I:'.'.

f"', .. : . . -1 r .. f,.f:,\f" . (Normal Range*) 4'6"ESFB,fitJfi: .. Measure 3RMS-RE35 ln-Cor1C*{nst:

• .. * ,, * *-Measure radiation levels Thimble Area 3'8" Containment 3RMS-RE36 Fuel Pool Monitor Measure radiation levels 52'4" Fuel Bldg. ; 3RMS-RE37 Condensate . Measure radiation levels Demin. Area 14'6" Cond. Polishing Bldg. 3RMS-RE38 Area Measure radiation levels 38'6" Cond. Polishing Bldg. 3RMS-RE41 Fuel Drop Monitor Measure radiation levels 51'4"

• 3RMS-RE42 Fuel Drop Monitor Measure radiation levels 51'4" Containment 3RMS-RE52 Recombiner Measure radiation levels Control Room 24'6" Recombine Bldg. Gamma spectrometers Isotopic identification and analysis Geiger-Mueller survey Measure gamma and beta radiation instruments R/hr range) dose rate H-7 Millstone Station Emergency Plan Revision 53 April2016 TableH-1 On-Site Assessment Equipment and Facilities Functional System Radiation Monitors and Sampling Equipment . (Cont'd) 3. Fire Detection

4. Facilities Instrument Detector Individual Applicability Ionization chamber (0-1,000 R/hr Measure gamma and beta radiation range) dose rate Contamination survey Air sampling equipment Neutron survey instrument TLD Direct reading pocket ion chamber Smoke detectors Rate of rise heat detector Fixed heat detector Chemistry la.boratory 9 radiation monitoring stations 4 Fixed air sampling stations Health Ptiys!:cs Lahorcto!j' H-8 Count samples for gross alpha and beta Sample for airborne radionuclides (particulate, iodine, gaseous, and tritium) Measure neutron radiation dose rate Measure personnel radiation dose Measure personnel gamma radiation dose Detects products of combustion Detects quick rise of temperature Detects a set temperature Equipped for chemical and radiological analysis Measure gamma radiation dose Sample particulates and iodines Equipped .for rqdjologicql_ . . ;:*_ --. ' . . , *: Millstone Station Emergency Plan Revision 53 April 2016 Functional System 1. Geophysical Monitors Meteorological Seismic 2. Radiological Monitors Environ mental Monitoring

3. Laboratory Facilities Radiochemistry laboratory AppendixH TableH-2 Off-Site Assessment Equipment and Facilities Instrument Detector Meteorological forecasting contractor for full weather forecast service Individual Applicability Provide current and forecast weather for Millstone area United States Geological Survey Record ground accelerations (USGS) for Strong motion recorder As specified by REMODCM Teledyne Brown Engineering Environmental Services GEL Environmental Laboratory Gamma radiation dose and sample particulates and iodines Equipped for chemical and radiological analysis Equipped for chemical and radiological*analysis , :

• Emergency
• Equipped for limited radiological analyses.

H-9 Millstone Station Emergency Plan Revision 53 April2016 Appendix I APPENDIX I EMERGENCY ACTION LEVEL SCHEME . r_ . NOTE: 'fhe EAL* s-.cheme provides an e)u'lnple of of 50.47(b) and requirements of Appendix-B: Emergency Assessment procedure MP-26-EPI-FAP06fue usedto classify event I-1 Millstone Station Emergency Plan Revision 53 April2016 M illstone Unit 1 Emer g ency Action Levels D UNUSUAL EVENT DELTA ONE n UNUSUAL EVENT DEL TA TWO n ALERT CHARLIE ONE IN-PLAN T RADIATION SECURITY THREAT/ DESTRUCTIVE P HENOMENA FIRE/GASES '--__ __ N_T ____________ __.ll RADIATION (D-AA2) ,-(D-HAl) . 1. Area radiation monitor reading in Reactor Building or survey results indicate an UNCONTROLLED increase in radiation levels by 100 mR/hr that is not the result of a planned evolution AND impedes operation of systems needed to maintain spent fuel integrity.

2. Valid radiation monitor reading or survey results indicate greater than 15 mR/hr in areas required to be occupied 24 hours a day. 1. Any on-going or imminent security compromise to the safety of the plant. I TA2 DESTRUCTIVE PHENOMENA

_ (N I A) An event that damages systems, structures , or components needed to maintain spent fuel integrity that may result in overexposure of site personnel or results in an uncontrolle d decrease in the spent fuel pool water level or damage to spent fuel. .l R_u __ i __ RE_A_c_T_o_R __ B_UIL __ D_IN __ G __ Jll TUl ,-RADIATION (D-AU2) . SECURITY EVENT (D-HUl) Area radiation monitor reading in Reactor Building or survey results indicate an UNCONTROLLED increase in radiation levels by 25 mR/hr that is not the result of a planned evolution. l,

• Security events as determined for Station Safeguards Contingency Plan and reported by Secuiity Shift Supervision.

2. A credible site-specific security threat notification.

setpoin ts are contained in EPI-FAP06 , "C la ssification and PARs." l l GUI FIRE (D-HU3) I. Life threatening toxic gases OR flammable gas concentrations as identified in C-OP 200.5, "Oil , Hazardous Material , Hazardous Waste and Mixed Waste Contingency Plan ," affecting activities in areas needed to maintain spent fuel integrity.

2. Notification of a near-site release that may require evacuation of MPI. FUEL POOL EQUIPMENT FAILURE FUEL POOL LEVEL (D-SUI) Uncontrolled decrease in fuel pool level indicated by a low level alarm actuation with all spent fuel assemblies remaining covered by water. UNPLANNED OFFSITE RELEASES .TUDGEMENT I OAl OFFSITE DOSE (D-AAl) 11 JAI JUDGEMENT . (D-HA2) 1. Unplanned release of 3.42E-l Any condition for whichjudgment

µCi/cc to the environment indicates that the level of safety times REMODCM for the Reactor Building or other release limit) for minutes. areas important for maintaining

2. Grab sample analyses indicate unplanned gaseous release rate 3.42E-l µCi/cc times the REMODCM limit) for minutes. 1 1 OUl UNPLANNED RELEASES (D-AUI) I. Gaseous eftluen t monito r*-* 3.42E-3 µCi/cc (2: 2 times REMODCM limits) 60 minutes. 2. Grab sample analyses indicate unplanned gaseous release 3.42E-3 2 times the REMODCM limit) for minutes. the integrity of the spent fuel is substantially degraded and which requires Station Emergency Response Organization (SERO) staffing.

JUDGEMENT (D-HU2) Any condition for which judgement indicates the potential or actual degradation in the level of safety of the Reactor Building or other areas important to maintaining the integrity of the spent fuel. AREAS NEEDED TO MAINTAIN SPENT FUEL INTEGRITY

• Reactor Building -4th and 5th Floors
• Reactor Building , Fuel Pool Pump Mezzanine

-2nd floor

• H& V Room -Lower Level (DHR)
• H& V Room -Roof -Coolers 11 11 CLASSIFICATION ALE R T CHARLIE ONE Events are in progress or have occurred which indicate an actual or potential substantial degradation of the level of safety of the plant, to plant personnel, or to the safe storage of fuel in the spent fuel p o ol. UNUSUAL EVENT OR DELTA ONE Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. 1 Millstone Millstone Emergency Plan Revision 53 April 2016 Page I-2 of8 MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS I] GENERAL EMERGENCY ALPHA SITE AREA EMERGENCY D GENERAL EMERGENCY BRAVO D CHARLIE-TWO D ALERT CHARLIE-ONE BARRIER FAILURE .__ __ A_N_Y_TW_O_BA_R_R_l_ER_s

__ _.I I Mode 1 , 2 , 3, 4 See Barrier Failure Reference Table §] I FUEL CLAD OR RCS BARRIER I I Mode 1, 2, 3 , 4 See Barrier Failure Reference Table I BA2 j __ s_T_EA_M_L_JN_E_B_R_EA_K __ _.l I Mode 1, 2, 3, 4 Unisolable Steam Line Break Outside CTMT l.__ __ c_T_M_T_B_A_R_R_IE_R __ ___.l I Mode 1 , 2, 3, 4 See Barrier Fai l ure Reference Table ___ R_c_s_L_EA_KA_G_E __ __..I I Mode 1, 2, 3 , 4 1. Pressure Boundary Leakage > 1 O GPM 2. Unidentified Leakage > 1 O GPM 3. Identified Leakage > 25 GPM 4. Primary to Secondary Leakage >25 GPM I FUEL CLAD DEGRADATION I ._I __ M_od_e_A_L_L _ __. 1. RCS Activity> 60 µCi/gm 1-131 DEQ 2. Dose Rate at One Foot from Unpressurized RCS 2 mR/hr/ml LOSS OF POWER __ s_T_A_TJ_O_N_B_LA_C_K_O_UT __ _.I I Mode 1 , 2 , 3, 4 Loss of Voltage on Buses 24C AND 24D AND ANY of the Following: Restoration of Power to AT LEAST One Vital Bus is NOT Likely Within Four Hours Core Exit Thermocouple Readings Indicate Superheat Inadequate SG Heat Removal Capability as Indicated by SG Water 10% in BOTH SGs AND Inadequate Terry Turbine Feedwater Flow I Mode 1 , 2 , 3, 4 Loss of Voltage on Buses 24C AND 24D > 15 Minutes I LOSS OF DC I I Mode 1, 2, 3, 4 Loss of Voltage on DC Buses 201 A AND 201 B > 15 Minutes ._I __ S_T_A_T_IO_N_B_LA_C_K_O_U_T _ ___.I I Mode 5 , 6, 0 Loss of V o ltage on Buses 24C llli.Q 24D > 15 Minutes I PA2 I I SINGLE AC POWER SOURCE I I Mode 1, 2 , 3 , 4 Only One AC Power Source Available to Supply Buses 24C AND/OR 24D > 15 Minutes Such That Loss of That Power Source Would Result in a Station Blackout (Unit 3 Buses 34NB CANNOT be Credited unless already aligned to Unit 2 Bus 24C or 24D) I LOSS OF OFFSITE POWER I ._I _M_o_d_e_A_LL _ _, Loss of all OFFSITE power to buses 24C AND 24D for > 15 Minutes. ___ Lo_s_s_o_F_Dc ___ _.I _M_o_d_e_5_,6 _ _, Loss of Voltage on DC Buses 201A AND 201 B > 15 Minutes 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. EQUIPMENT FAILURE I ATWS/JNADEQUATE COOLING I _1 _ _. Functional Recovery of Reactivity Control Ineffective AND EITHER of the Following: RCS Heat Removal by Steam Generator Heat Removal SFSC Criteria Can NOT Be Satisfied Core Exit TC Temperature Readings> 800°F ._l ____ A_TW_s ___ __.I ..... Manual Reactor Trip Attempted At Panel C 04 AND Reactor Is NOT Shutdown .-I -1N_A_B_IL-ITY_T_O_M_A_INT_A_IN_H_O_T_S_/D---.I I Mode 1 , 2, 3, 4 1. No RCS Heat R em o val Via Steam Gene rators AND.On ce Through Coo ling NOT Effect ive AND Shutdow n Coo ling is NOT In Service 2. RCS Boration C apability Unable to Eliminate Inadvertent Criticality I IN-VESSEL FUEL UNCOVERY I I Mode 5 , 6 Shutdown Cooling Has Been Lost htlQ ANY of the Following Conditi ons Exist: Alternate Methods for Restoring RCS Inventory are NOT E ffective RVLMS Read ing = 0% with OPERABLE #8 string (NA if no OPERABLE #8 string) Core E xit TC Temperature Read in s Indicate Su;..pe_r_h_ea_t ____ oss OF ANNUNCIATORS{fRANSIEN I Mode 1 , 2, 3 , 4 Loss of Most (75%) MCB Annunciators AND BOTH of the Following Sign ificant Transient in Progress Loss of SPDS AND ICC Instrumentation I AUTOMATIC RX TRIP FAILURE I l.___M_o_d_e_1.;...., 2 _ _, Failure of Automatic Reactor Trip A.t:fil Manual Tr ip Was Successful I EA2 I j 1NABILITY TO MAINTAIN COLDS/DI I Mode 5, 6 1. Uncontrolled RCS Temperature Increase> 10°FThat R esults in RCS Temperature> 200°F 2. Inadvertent Cr iticality I EA3 I koss OF ANNUNCIATORSffRANSIEN) Mode 1 , 2, 3 , 4 Loss of Most (75%) MCB Annunciators > 15 Minutes AND EITHER of the Fo llowin g: Significant Transient in Progress Loss of SPDS AND ICC Instrumentation I LOSS OF COLD S/D FUNCTION I Mode 5, 6 1. Loss of Shutdo wn C ooling > 15 Minutes AND Refue l Pool Water Level < 35 Ft., 6 In. 2. Uncontrolled RCS Temperature Increase> 10°F 3. RCS Boron Concentration < Minimum Requ i red I REFUEL/SPENT FUEL POOL LEVELi .... I _M_o_d_e_6_, o _ _, 1. Unco ntrolled Sp en t Fue l Pool Water Le v el Decrease Causing Loss of Coo li ng Suction Flow 2. Uncontrolled Re fuel Pool Water Le v el Decrease Requiring Containment Evacuation AND All Spent F uel Assemb li es in Safe Storage Locat ions I LOSS OF ANNUNCIATORS I I Mode 1 , 2 , 3 , 4 I Los s of Most (75%) MCB Annunciators > 15 Minutes htlQ SPDS OR ICC Instrumentation Available I EU4 I I LOSS OF COMMUN ICATI ONS I l.....__M_o_d_e_A_LL _ _, 1. Loss of ALL Ons tte Elect ronic C ommunications Methods 2. Loss of ALL Electronic Communications Methods Wrth Government Agencies I SHUTDOWN LCO EXCEEDED I I Mode 1 , 2 , 3 , 4 I. Unit NOT Brought To Required Mode Wrthin App licable LCO Ac tion Statement Time Limits D UNUSUAL EVENT DELTA-TWO OFFSITE RELEASES I OG1 I I OFFSITE DOSE I I Mode ALL 1. MP2 Kaman Vent Monitor (RM-8168) Reading z 2 µCi/cc for > 15 Minutes 2. MP2 WRGM S i te Stack Effluent Activity (RM-8169) Reading z 30 µCl/cc for > 15 Minutes 3. MSL Monitor (RM-4299/A/B/C) Read i ng .!!._2 R/hr for > 15 Minutes 4. Measured Plume Dose Rate OnSitez 1,000 mR/hr for > 15 Minutes 5. Rad Assessment Determines Integrated Dose Offsite z 1 Rem TEDE OR z 5 Rem COE Thyroid .... I ___ o_FF_S_JT_E_D_O_S_E __ __,I I Mode ALL 1. MP2 Kaman Vent Monitor (RM-8168) Reading z 0.2 µCi/cc for> 15 Minutes 2. MP2 WRGM Site Stac k Effluent Activity (RM-8169) Reading z 10 µC i/cc for> 15 Minutes 3. MSL Monitor (RM-4299A/B /C) Reading z 0.3 R/hr for > 15 Minutes 4. Measured Plume Dose Rate Onsite z 50 mR/h r for > 15 Minutes 5. Rad Assessment Determines Integ r ated Dose Offsite .!!. 0.05 Rem TEDE OR.!!. 0.25 Rem COE Th yro id .... I ___ O_FF_S_IT_E_D_O_S_E __ __,j I Mode ALL 1. MP2 Kaman Vent Monitor (RM-8168) Reading z 0.02 µC i/c c for> 15 Minutes 2. MP2 WRGM Site Stack Effluent Activity (RM-8 169) Reading z 1 µCi/cc for > 1 5 Minutes 3. MSL Monitor (RM-4299NB /C) Reading.!!. 0.03 R/hr for> 15 Minutes 4. Measured P lum e Dose Rate.Onsit e z5 mR/hr for > 15 Minutes 5. Rad Assessment Dete rmines Integrated Do se Offsite z 0.005 Rem TEDE OR.!!. 0.025 Rem COE Thyroid D UNUSUAL EVENT DELTA-ONE CLASSIFICATION I GENERALEMERGENCY I I ALPHA -I OR BRAVO Events are In process or have occurred which inv olve 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 offsite for more than the immediate site area. SITE AREA EMERGENCY CHARLIE-TWO Events are in process or have occurred which involve an actual or likely major failure 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 exeed EPA Protective Action Guideline exposure levels beyond the site boundary. ALERT CHARLIE-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 Protect ive Action Guideline exposure level s. UNUSUAL EVENT DELTA...:fW9 OR DELTA-ONE Events are in process or have occurred which in d icate a potential degradation o f the level of safety of the plant or indicate a security ttfreat to facility protection. No releases of radioactive material requiring offsite response or monitoring are e x pected unless further degradation of safety systems occurs. 2 Millstone Millstone Emergency Plan Revision 53 April 2016 1-3 of 8 MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS ri GENERAL EMERGENCY ALPHA SITE AREA EMERGENCY D GENERAL EMERGENCY BRAVO D CHARLIE-TW O D ALERT CHARLIE-ONE IN -PLANT RADIATION SECURITY THREAT/ FIRE/GASES D F STRUC T TVE PHENOM ENA I MAJOR FUEL DAMAGE I I Mode ALL I I SECURITY EVENT I I Mode ALL I --' 1. RM-8240/8241 Rea.ding > 1 1 200 R/hr_ , A HOSTILE FORCE has taken control of plant equipment such that 2. At Least 20% Fuel Claq Damage As Determined By Core plant personnel are unable to operate equipment required to Damage Estimate ' --maintain safety functions. Any of the following meet this EAL: . 3. Spent F).1el is frorp *water from Operi 1. Loss of Control Room Cavit}r, Or SF Pool AND !i!OTH of the Following: _ * '* 2. Loss of Hot Shutdown Panel (C-21) (West 480v SWGR Room) 3. Loss of Cold Shutdown Panel (C-10) (Upper 4160v SWGR Room) !. Spent Fuel Has Decayed -S 30 Days -* 4. Security reports the loss or imm i nent loss of a Target Set -*

• CTMT l_ntegrity is Establisl]e

.d OR Expo5ed Spent OR Fuel is Outside CTMT -A HOSTILE ACTION has caused failure of Spent Fuel Cooling r -** . Systems and IMMINENT (for EA Ls) fuel damage is likely for a freshly .. -. ' ' . off-loaded reactor core in pool. -I SPENT FUEL DAMAGE I I Mode ALL I I SECURITY EVENT I I Mode ALL I I CONTROL ROOM EVACUATION I I Mode ALL Spent Fuel is E x pos ed from Op en Vessel or Ca vity AND BOTH A not ifi cat ion from the s ite security force that an armed attack , Uni t Con trol from Hot Shutdown Pane l C-1 O Or C-21 of the Follow in g: e xplosive attack , a irli ner impact , or other HOSTILE ACTION i s NOT Establi shed Within 15 Minutes A fter C ont r o l Room occu rr i ng or has occurred within the protected area. Evacuat io n . Sp ent Fuel Has D ecay ed < 30 Days . CTMT Integrity Es t ablish ed --§] I SPENT FUEL ASSEMBLY DAMAGE I I Mode ALL I I SECURITY EVENT I I Mode ALL I I CONTROL ROO M EVACUATION I I Mode ALL Spent Fue l is Exposed f rom Open Vessel , Ca vity, or SF Po o l 1. Security Events as de te rm ine d for St ation S afeguards Co ntingency Plan and reporte d by Security S hift S upervision. (Addre sses events Con trol Room E v acu atio n Initiated AND Sp ent Fuel Has D ec ayed.?!. 30 Days that involve Actual or Potential Substant ial degradation to the level of 2. Fue l Handling Accid en t Caus in g Damage to Sp e nt Fuel , safety of the plant.) I GA2 I I I I Ind ic ated by Fu e l Building OR C ontai nm en t Radiat io n Monitors 2. A not ificatio n from the site se c urity f orce that an armed attack, FIRE/E X PLOS I ON Mode ALL Increasing explosive att a ck, airliner impact, or o t her HOSTILE ACTION is I RA2 I I I I I occurring or h as occurred within the OCA. F ire or Explosio n Affecting Safe Shutdo w n Area AND Damage PLANT RADIATION Mode ALL 3. A validated notif ication from the NRC of an airliner attack threat less to Structures QB Saf e Shutdown Equipm ent In d icated. than 30 minutes away. 1. Rad iation Readings > 15 mR/hr in Contro l Room OR C entral I TA2 I I A la rm Station QB Se con dary Alarm Stat io n DESTRUCTIVE PHENOME NA I I Mo de ALL I I GA3 I I TO XIC/FLAMMABLE GASES I I Mode ALL 2. Radiat ion Reading > 5 R/hr in Ar ea s Requiring Access for 1. Seism ic Event > 0.09g ZPA Life Thre ate ning To x ic Gases QB F lammable Gas Concentrat io ns Safe Shutdown 2. Ons i te Sustained W indspeed > 90 MPH 3. Vis ible D amage to Stru ct u res or Equipment AND Affecting Saf e as Identified i n C-OP 200.5 , " Oil , Hazardous Material, Hazardous Shu tdown Waste and Mixed Waste Conti n gency Plan" Affecting Areas for 4. Vessel or Vehicle Co llision AND Affect in g Safe S hutdown Sa fe Sh utdown 5. M issiles Affect ing S afe S h utd own 6. Flood in g Affecting Sa le Sh utdown I RAD MONITORS I I Mode ALL I I SECURITY EVENT I I Mode ALL I I FIRE I I M ode ALL I 1. Security Cond ition as determined for Stat io n Safeguards Con tingency 1. Fire in Building OR Ar eas Ad jacen t to Areas Needed for S ale 1. Unc ontro ll ed R efuel P ool Water Level Decr ease AND Rad Plan and reported by S ecurity Shift S upervision. (Addresses events Shutdown NOT E xtinguished Wrthin 15 Minutes o f Notification QB Levels R equire Evacuat i on of CTMT or Sp ent F:uel Po ol Area that involve P otential degradat ion in the level of safety of the plant.) Verificat ion of Control Room Alarms 2. A credible site specific sec ur ity th reat n otification.

2. F ire Affect ing a Load e d ISFSI Confinement Bound a ry NOT 2. Une x pect e d Area Rad Monitor R e ading Offscal e High QB E xtin g uished Withi n 15 Minutes of Not ifi cat ion. > 1000 Times Normal Reading 3. A va lid a t ed no tification from the NRC prov i ding i nformation of an aircraft th reat. I Gu2 I I TOXIC/FLAMMABLE GASES I I I I I I I Mode ALL DESTRUCTIVE PHENOMENA Mode ALL 1. Life T hreatening To xic Gases QB F lammable Gas Concent rations as 1. S eismic Activity Detected Per AOP-2562 , Eart hquake Identified in C-OP 200.5, " Oil , Haza r dous Material , Hazard ous Waste 2. R eport by Plant Personne l of Tornado S triking Within P rot ected Area and Mixed Waste C ontingency P l an" Affecting Normal O peration 3. Visible Damage to Structures or Equipment Within the Protected Area 2. Notification of a Near-Site Re lea se That May Require E vacuation

4. Onsite Sustained Windspeed

> 75 MPH D UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE JUDGEMENT CLASSIFICATION I JUDGEMENT I I Mode ALL I I GENERAL EMERGENC Y I Other Conditions Exist For Which Judgement Indicates: I .ALPHA** I 1. Actual Or Imminent Substantial Core Degradation OR With Potential For Loss Of Containment, QB. BRAVO 2. Potential For Uncontrolled Radiological Releases . Events are In process or have occurred which These Releases Can Be Reasonably Expected To involve actual or Imm i nent substantial core degradation or melting with potential for loss of Exceed EPA PAG Plume Exposure Levels Outside containment integrity or security events that The Site Boundary result In an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Act i on Guideline exposure levels offsite for more than the immediate site area. I I JUDGEMENT I I Mode ALL I I S I TE AREA EMERGENCY I O ther Condi ti ons Ex i st For Which Judgem ent Indicates CHARLIE-TWO Actua l Or Likely Major Fa ilu res of P la n t Funct io ns Needed Events are In process or have occurred which For Protec ton Of The Pub lic inv o lve an actual or likely major failure of plant functions needed for protection of the public o_r security events that result In intenti on al 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. I I JUDGEMENT I I Mode ALL I I ALERT I Any Cond itio n Fo r Which Judgement Indicates That Saf ety CHARLIE-ONE Sys tem s May Be Degraded AND Which R e qu ire s Emergency E vents are in process or have occurred which I Respons e Organ ization Staffing involve an actual or potential substantial degradation of t he level of safety of the plant or a secu rity event that involves pr obable life threatening risk to site p ersonnel or damage to site equipment because of i nt entional malic ious ded icated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA I Pr otective Action Guide line exposure levels. I JUDGEMENT I I Mode ALL I I UNUSUAL EVENT I Any Condition For Wh ic h Judgement Indicat e s Potent i al Degradat ion in the Level ofSafety of the P lant I ]?_ DELTA-TWO ' .. I OR DELTA-ONE E vent s ar e in process or have occurred which indicate a potential degradat ion oftfi'e level of safety of the plant or in dicate a security threat to facility protection. No releases o f radioactive mater ial requi r ing offsite res po nse or monitoring are e xpect ed unless further degradat i on of sa fety systems occurs. 5. Explosion Within the Protected Area AREAS OF CONCERN FOR SAFE SHUTDOWN 2 6. Turbine Failure Causing Observ able Casing Damage Cont rol Ro om 7. Vessel or Vehicle Collision With Structures OR Equipment Requ ir ed Cable Vaults Sw i tchgear R oom s for Safe Shutdown or a lo ade d I SFS I Confinem en t Boundary Intake Structure Millstone

8. F lood Le ve l > 19 Feet Mean Sea L evel Turbine Build in g Switchgear Area Flood ing in Areas Containing Safe Shutdown Equ i pment Penetration Ar ea s Coolant Tanks Area 9. RBCCW Rooms Containment D i esel Generator Room DC Equipment and Batt ery R o oms Millstone Emergency Plan Charging Pump Cub icles S afety Injection Pump Rooms Revision 53 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 j Switchyard April 2016 I 4of 8 MILLSTONE 2 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE IMMINENT -N o Turnaround in Safety S ystem Performance is Expected AND Escalation to General Emergency Conditions Will Occur Within 2 Hours I INDICATORS FUEL CLAD BARRI E R RCS BARRI ER I FCB1 I I LOSS I I RCB1 I I LO SS I ::;AFETY FUNCTION Not Ap plicable Not Applicable STATUS/ I POTENTIAL LOSS I I I FUNCTIONAL POTENTIAL L OSS 0 Uncontrolled RCS Cooldown AND RCS Pressure-Temperature To RECOVERY the Left Of the PTS Limit 200° F S ubcool i ng Max i mum C urve 0 No RCS Heat R emoval Via S team Generators AND O nce Through Cooling NOT E ffective AND Shutdown Cooling 0 No RCS Heat Removal Via S team Generators

!lliQ Once Through System I s NOT In Serv i ce Cooling NOT Eff ective AND Sh utdown Cooling Sys te m Is NOT In Service I FCB2 I I LOSS I I RCB2 I I LOS S I CORE EXIT TC [IJ Core Exit Thermocouple Readings> 1200 °F ITJ RCS Subcool in g < 30°F TEMPERATURES I POTENTIAL LOSS I I I POTENT IA L LOSS 0 Core E xit Thermocouple Read ings> 700 °F Not Applicab le I RCB3 I I LOSS I Not Applicable I POTE NTIA L LOSS I PRESSURE 0 Uncontro lled RCS Pressure D ecrease and Increasing Conta i nment Rad i ation Monitors -I RCB4 I I LOSS I ITJ R eac tor Coolant Leak > CVCS Capacity A ND Entry Into EOP-2534, St eam Generator Tube R upture or EOP 2540, Funct ional Recovery , to Address S team Gen erato r Tube Rupture )OLA NT I POTE NTIA L LOSS I LEAKAGE 0 Reactor Coolant L eak > CVCS Capac i ty AND Entry Into EOP-2525 , Standard Post Trip Actions 0 Reactor Coolant Leak Rate..$_ CVCS Capacity AND EITHER of the following: . Entry Into EOP 2534, Steam Ge nerator Tube Rupt ur e . Entry Into EOP 2540 , Funct ional Recov ery, to Address Steam Generator Tube Rupture I FCB3 I I LOSS I I RCB5 I I LOSS I -[IJ R M-8 240/8241 Reading > 300 R/h r ITJ RM-8240/8241 Reading > 5 R/hr W ithout Fuel Clad [IJ RM-8240/8241 Reading> 5 R/hr Without RCS R elease Barrier Loss Inside CTMT *[IJ At L east 5% Fuel Clad Damage As Determined By Core Damage Estimate OR Samp le System D ose Rates Obta ined I POTENTIAL LOSS I Using CP 2802N, " Pr i mary System Samp li ng Analys i s" RADIATION [IJ Dose Rat e at One Foot from Unpre ssurized RCS Samp le Not Applicable z28 mR/hr/m l I POTENTIAL LOSS I Not Applicable I FCB4 I I LOSS I WATER Not App licable I I LEVEL POTENT IA L LOSS 0 RVLMS R eading = 0% with OPERABLE #8 string (NA if no OPERABLE #8 strinal I FCB5 I I RCB6 I Any Cond ition For Which Judgement Indi cates Loss or Potential Any Cond ition For Wh ich Judgement Ind i cates Lo ss or Potential Loss of Fuel Clad Barr ier Due to: Lo ss of RCS Barrier Due to: 1GEMEN T . Imminent Barr ier Degradation Based On Current Safety . Imm inent Barrier Degradation Based On Current Safety System Perform ance Sy stem Performance . Degraded Fission Barrier Monitoring Capability Making . Degraded F ission Barrier Monitoring Capability Making Bar rier Status Ind eterminat e Barrier Status I ndeterminate CTMT BARRIER I CNB1 I I LO SS I Not Applicable I POTE NTIAL LOSS I 0 Cor e ExitTC Temperature R eadings >1200°F AND Do NOT Decrease Within 15 M inutes I CNB2 I I LOSS I ITJ Rapid Une xplain ed CTMT Pressure Decrease Fo ll owing Initial Increase ITJ No CTMT Pressure Increase When Expectat i on Exists I POTE N T I AL LOSS I 0 CTMT Pressure > 10 PSIG !lliQ Inc reasing !lliQ No Conta i nment Spray Pump 0 CTM T H2 Concentration z 4% I C NB3 I I LOSS I [IJ Pr imary t o Secondary > Te ch Sp ec Limits and EITHER exists:

• Nonisolable Ste a m Re lease from A ffected S/G to environment . Prolonged R e l ease From Affected S/G to Env iron ment When Used for Coo l down (see basis for description of prolonged release) [IJ Leakage Through BOTH Isolation Valves AND a Pathway to the Env i ronment Exists Requiring Actions Outside the Contro l Room to I solate I POTENT IAL LOSS I 0 E ntry Into EOP-2532, Loss of Primary Coolant, AND Lea kage Exists Outside CTMT Requ iring Iso l ation From in s i de the C on trol Room I CNB4 I I LOSS I ITJ O ffsite Dose Plum e Rate z 1 o-6 Times RM-8240/8241 Read ing if R e lease is to CTMT I POTENTIAL LOSS I 0 RM-82 40/8241 Reading>1,200 A/h r [£] A t L east 20% Fuel Clad Dama ge A s Determined By Core D amage Estimate I CNB5 I I LOSS I [IJ No CTMT Sump Le vel Increase When Expectation E xists I POTENTIAL LOSS I Not Applicable I CNB6 I Any Cond iti on For Which Judgement Indicates Loss or Potent ial Loss of CTMT Barrier Due to: . I mminent Barrier Degradat io n Based On Cu rrent Safety System P erfor mance . Degraded Fission B arrier Monitoring Capability Mak i ng Barr ier Status Indeterm in ate THREE BARRIERS L p L p L p CLAD RCS CTMT 3/3 YES TWO BARRIERS L P L P L p CLAD RCS CTMT 2/3 MORE THAN ONE BARRIER AFFECTED EIYIERGENCY ALPHA --SITE AREA EMERGENCY TWO ONLY ONE BARRIER AFFECTED L p CLAD L p RCS 2 L p CTMT Millstone Millstone Emergency Plan Revision 53 April 2016 J-5 Of 8 ALERT ONE UNUSUAL EVENT DELTA-ONE MILLSTONE UNIT 3 EMERGENCY ACTION LEVELS D SITE AREA EMERGENCY D GENERAL EMERGENCY ALPHA D GENERAL EMERGENCY BRAVO CHARLIE-TWO D ALERT CHARLIE-ONE BARRIER FAILURE I ALL THREE BARRIERS See Barrier Failure Reference Table I FUEL CLAD OR RCS BARRIER I I Mode 1 , 2, 3 , 4 See Barrier Fa ilure Reference Tab le I BA2 I __

I Mode 1 , 2, 3, 4 Unisolable Steam Lin e Break Outside CTMT ___ c_T_M_T_B_A_R_Rl_E_R __ __.I I Mode 1 , 2 , 3 , 4 See Barrier Failure Reference Table ___ Rc_s_LE_A_KA_G_E __ ____.I ..... 1. Pressure Boundary Leakage > 1 O GPM 2. Unidentified Leakage > 1 o GPM 3. Identified Leakage > 25 GPM I FUEL CLAD DEGRADATION I ._I __ M_o_de_A_L_L _ _, 1. RCS Activity > 60 µCi/gm 1-131 DEQ 2. Dose Rate at One Foot from Unpressur ize d RCS Sample .?. 1 mR/hr/ml LOSS OF POWER §] ._I __ sT_A_T_IO_N_B_LA_C_K_o_u_T _ ___.I I Mode 1 , 2, 3, 4 Loss of Voltage on Buses 34C AND 34D (Station Blackout Diesel cannot be credited) AND ANY of the Following: Restoration of Power to AT LEAST One Bus is NOT Likely Within Four Hours Core Cooling -RED Heat Sink -RED AND Required Feedwater Flow Can NOT be Established Within 15 minutes LI __ s_T_A_T1_o_N_B_LA_c_K_o_u_T _ __.I I Mode 1 , 2 , 3, 4 Loss of Voltage on Buses 34C AND 34D > 15 Minutes (Stati on Blackout D ie sel cannot be credited) ..... I ___ Lo_s_s_o_F_Dc ___ _.I I Mode 1, 2 , 3 , 4 Loss of Voltage on DC Buses 1 , 2, 3 AND 4 > 15 Minutes / l...___s_T_A_T1_o_N_B_LA_C_K_o_UT __ _..I I Mode 5, 6 , o Loss of Voltage on Buses 34C 34D > 15 Minutes §] I SINGLE AC POWER SOURCE I I Mode 1, 2, 3, 4 Only One AC Power Source Ava ilable to Supply Buses 34C AND/OR 34D > 15 M in utes Such That Lo ss of That Power Source Would Result in a Station Blackout (Station Blackout Diesel CANNOT be Cred ite d) §] I LOSS OF OFFSITE POWER I ..... I __ Mo_d_e_A_L_L ___, Loss of all OFFSITE power to buses 34C AND 34D for> 15 Minutes ... l ___ Lo_s_s_o_F_Dc ___ __ _ _J Loss of Voltage on DC Buses 1, 2, 3 AND 4 > 15 Minutes NOTE: When two or more EAls apply , always choose the EAL of the highest incident classification; a l so always read from top to bottom in each category. EQUIPMENT FAILURE I ATWS/I NADEQUATE COOLING I ... I __ M_o_d_e_1 _ _.. Reactor Power> 5% Following Entry into FR-S.1 AND EITHER of the Following: Core Cooling -RED All SG Wide Range Levels < 21 % (24% Adverse CTMT) ____ A_TW_s ___ __.I ..... l __ M_o_d_e_1 _ _.. FR-S.1 is Enter ed Direct! From E-0 INABILITY TO MAINTAIN HOT S/D I Mode 1, 2 , 3, 4 1. Heat Sink* RED AND BOTH of the Following:

• Requ ired Feedwater F low Can NOT Be Es tablished With i n 15 Minutes
• RCS Bleed and Feed Can NOT Be Es tablished

2. RCS Boration Capability Unable to E liminate Inadvertent Criticality I IN-VESSEL FUEL UNCOVERY I I Mode 5, 6 AHR Has Been ANY of the Following Conditions E x ist: A l ternate Methods for Restoring RCS In ven tory Are NOT Effect ive RVLMS Reading Decreasing Toward 19% Level (Plenum) with OPERABLE 19% sensor (NA if no OPERABLE 19% sensor) CET Readin gs Ind icate Superheat Conditions

[}ill boss OF ANNUNCIATORS/TRAN SIENj I Mode 1, 2, 3, 4 Loss of Most (75%) MCB Annunciators AND BOTH of the Following:

• Significant Transient in Progress Loss of SPDS AN D ICC Instrumentation I AUTOMATIC RX TRIP FAILURE I ._I __ M_od_e_1_,_2 _ _, Failure of Automatic Reactor Manua l Trip Was Successful I EA2 I I INABILITY TO MAINTAIN COLDS/DI I Mode 5 , 6 1. Uncontrolled RCS Temperature Increase > 1 O ° F That Results in RCS Temperature

> 200 ° F 2. Inadvertent Criticality I EA 3 I boss OF ANNUNCIATORS/TRANSIENj Mode 1, 2 , 3, 4

• I Loss of Most (75%) MCB Annunciators

> 15 Minutes AND EITHER of the Fo llowing: S ignificant Transient in Progress L oss of SPDS AND ICC Instrumentation I LOSS OF COLD S/D FUNCTION I Mode 5 , 6 1. Loss of AHR Cooling > 15 Minutes Af!Q Valid PZR Water Level (LT 462) R eading < 40% 2. Uncontrolled RCS Temperature Increase> 10°F 3. RCS Boron Concentration < Minimum Required I CAVITY SEAL FAILURE II ..... _M_o_d_e_6_, 0--Refueling Cavity Seal Failure AND EITHER of the Following: Valid PZR Le vel (LT 462) Reading < 40% Valid SFP Le vel (LI 26) Reading = 0% Applies in Mode 0 when transfer gate is open. I LOSS OF ANNUNCATIROS II ..... _M_o_d_e-1,-2-, Loss of Most (75%) MCB AnntJnciators > 15 Minutes .tlliQ SPDS OR ICC Instruments Available I LOSS OF COMMUNICATIONS I ._l __ M_o_de_A_L_L _ _, 1. Loss of ALL Onsite E lectronic Communications Methods 2. Loss of ALL Electronic Communications Methods With Government Agencies I SHUTDOW N LCO EXCEEDED I I Mode 1 , 2 , 3, 4 Unit NOT Brought To Requ ire d Mode Within Applicable LCO Act ion Statement T ime Limits D UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE OFFSITE RELEASES loG1j ._l __ o_F_F_s_1T_E_D_o_sE __ L _M_o_de_A_L_L___.

1. MP3 Vent 0 MQnit()r O) Read_ing. _=::. 0.8 for >:*15 M l nutes . _ * * * * . * *. 2. MP3 SLCRS Monitor (3HVR*RE19)

Readin-g > 30 µCi/cc . fo'r > 15 Minutes * . *. * -:--** " -3. MP3 Safeties or Steam Dump Monito( . :. (3.MSS-RE75/76fn/78) Reading_=::.2bjiCiii:c for >15 MinUtes 4. Terry Monitor (3MSS-RE79) Reading.=::. 5 µCi/c c tor> 15 Minutes * * . . '

• 5. Plume c:iose Rate Onsite .:::.* 1,000 mR/hr
• for > 15 Min" utes * ' " 6. Rad Assessment Determi ne s Integrated Dose Offsite 2:. 1 TEDE m;i 2:. 5 Re" in COE Thyroid ... l __ o_F_F_s_IT_E_D_os_E

__ LI _M_o_de_A_L_L__.

1. MP3 Ventilation Vent Monitor (3HVR*R E 10) Read i ng_=::. 0.1 µCi/cc for > 15 Minutes 2. MP3 SLCRS Monitor (3HVR*RE 19) Re ading_=::.

10 µCi/cc for > 15 Minutes 3. MP3 Safeties or Steam Dump Monitor (3MSS-RE75/76m/78) Reading_=::. 0.8 µCi/cc for > 15 M i nutes 4. Terry Turbine Monitor (3MSS-RE79) Reading_=::. 1 µCi/cc for > 15 Minutes 5. Measured P l ume Dose Rate Ons it e _=::. 50 mR/hr for > 15 M in utes 6. Rad Assessment Determine s Integrated Dose Offsite .=::. 0.05 Rem TEDE OR_=::. 0.25 Rem CDE Th yroid loA1I Ll __ o_F_F_s_1T_E_D_os_E_. _ __.I LI _M_od_e_A_L_L__.

1. MP3 Ventilation Vent Monitor (3HVR*RE10)

Reading _=::. 0.01 µCi/cc for > 15 Minutes 2. . MP3 SLCRS Monitor (3HVR*RE 19) Reading_=::. 1 µCi/cc for > 15 Minutes 3. MP3 Safet i es or Steam Dump Monitor (3MSS-RE75/76m/78} Reading.=::. 0.0 8 µCi/cc for > 15 Minutes 4. Terry Turb in e Monitor (3MSS-RE79) Reading Of_=::. 0.1 µCi/cc for> 15 Minutes 5. Measured Plume Dos e Rate Onsite .=::. 5 mR/hr for > 15 Minutes 6. Rad Assessment Determ ines Integrated Dose Offsite _=::. 0.005 Rem TEDE OR_=::. 0.025 Rem CDE Thyroid CLASSIFICATION GENERAL EMERGENCY I ALPHA *I 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 offs l te for more than the . . SITE AREA EMERGENCY CHARLIE-TWO Events are in process or have occurred which involve an actual or likely major fa il ure 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 likelyfailure of or; (2) prevents effective access to equipment needed for the protection of the public. Any re l eases are not expected to result in exposure levels which exeed EPA Protect ive Act ion Gu i deline exposure levels beyond the site boundary. ALERT CHARLIE-ONE Events are in process or have occurred which involve an actual or potential substa ntial degradation of the le ve l of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equ i pment because of intentional ma l icious dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. UNUSUA L EVENT

• DELTA""" TWO -OR DELTA-ONE Events are in process or have occurred which ind i cate a potenti al degradat i on of the level of safety of the plant or indicate a segurity threat to facility protection.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. 3 Millstone Millstone Em erge ncy Plan Re vision 53 April 2016 1-6 of 8 MILLSTONE UNIT 3 EMERGENCY ACTION LEVELS G ENERAL EM ER GEN C Y AL P HA D S I TE AREA EMERGENCY 0 GENERAL EMERGENCY BRAV O CHARLIE-TW O D ALERT CHARLIE-O NE FI R E/GAS E S D UNUSUAL EVENT D ELTA-TW O JUDGEMENT D UNUSUAL EVENT-D ELTA-O NE I N -PLAN T RADIATION -I MAJOR FUEL DAMAGE I I Mode ALL 1. Sustained Valid .REo4 A/o5A Reading->

• R/hr. Read li'i g is Considered Sustaine*d Valid When the Effects of TIC -have dissipated. * * ' * -* 2. At t.:east *20% Fue i Clad Damage As Determined By Core D_amage Esti111ate

-, * , '. 3. Fuel.j s §Xpo , sed Wate r. t.:oss tr om Open Cavity; 9r SF Pool AND BOTH of the Following: -* -* 1' .. * }'

• Spent Fuel Has Decayed < 30 Days .l"
• Can Bypass C T MT . .,;.* *See Table 1 . _:>-r. __

S pent F uel is Expo s e d from O pe n V es s el, or C avity A N D BOT H of the F ollowing:

• Sp ent Fu el H as D ec a yed < 3 0 D ays
• C TM T I n t e gr i ty Estab lishe d I SP EN T F U EL AS SE MBLY DAM AG E I __ I S pent F uel is Ex p ose d from Op en Vessel, Cavity QB SF Po_ol AN D S pent Fu e l Has D ecayed,;::, 30 D ay s .!. F uel Handling A ccident Causing D amage to Spent Fu el , Indicated by Fu el Build i ng QB Co n tai n ment Radiatio n Mon i tors Inc r easin g I RA2 1 __ P_LA_N_T_RA_D l_AT_IO_N ___ I 1. Rad i a t i on R e ad i n g s > 1 5 mR/h r i n C o n trol R oom O R C entra l Al a rm S tatio n OR S ec on dary Al arm St atio n 2. Radi a t ion R e a din g > 5 R/hr in A r e as R e quir i n g Acc e ss f or Safe Shutd o wn ._l ___ RA_D_M_o_N_I T_O_R_s ___ I

1. Containment .QB F uel B uilding Area Rad Mon i tor Alarms I ndicate Cavity Seal Failure 2. Unexpected Ra d Monitor R eading O flscale H i gh OR > 1 000 Ti mes N o rm al R ea d i n g S E C U RI TY TH RE AT/ PH F NO MENA I SECURITY EVE N T I

___.I A HOSTILE FORCE has taken control of plant equipment such that plant personne l are unable to operate equipment required to ma itain safety functions. Any of the following meet this EAL: 1. Loss of Control Room 2. Loss of Remote Shutdown Panel 3. Security reports the loss or imminent loss of a Target Set OR A HOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT (for EALs) fuel damage is likely for a freshly off-loaded reactor core in pool. __ s_E_c_uR_ITY_E_V_E_ N T __ A n otification fro m t he s ite security force t h at an ar me d att ac k, ex p losive attack , airliner i mpact , or othe r HO S TIL E A C TI O N is oc c urring o r has occurred within the protected area. __ s_E_c_u_R_I TY_Ev_E_N_T ___ I __ I 1. Security E vents as determined for S tation S afeguards Contingency P lan and reported by S ecurity S hift S upervision. (Addresses events that involve Actual or P otential Substantial degradation to the level o f safety of the plant.) 2. A no@cation from the site security force that an armed attack , explosive attack, airliner impact, or othe r H OSTI L E AC T ION is occurring or has occurred within the OCA 3. A validated notification from the NRC of an airliner attack threat less than 30 minutes away. I TA2 I I DESTRUCTIVE PHEN O M E N A I I M ode A L L I 1. S eismic E vent > 0.09 g ZPA 2. O nsite S ustaine d Win d speed > 90 M PH 3. V isib l e D a m age to S tr u ctures or Eq uipment AN D Affecting Safe Shutdown 4. Vessel or V ehicle Collision AND Affec t in g Safe Shutdown -5. Missiles Affecting S afe Shutdown 6. F looding Affec t ing S afe Shutdown ._l __ s_E_c_u_R l_TY_E_V_E_N T __ _M_o_de_A_L_L___.I 1. S ecurity Conditio n as determined for S tation S afeguards Contingency P lan and reported by Security Shift Supervision. (Addresses events that involve P otential degradation in the level of safety of the plant.) 2. A cred i ble site specif i c security th r eat notification.

3. A val i dated not i f icatio n fro m the NRC p rovidi n g informa t ion o f an aircraft threa t. I D E S TRU CT IV E PH E N O M E NA I _M_o_d_e_A_LL __ j 1. S eismic Act ivity Detected Per AOP-3570, E arthquake

2. Report by P lant Personne l of Tornado Striking Wrth i n Protected Area 3. Visible Damage to Structures or Equipment Within the Protected Area 4. Onsite Sustained Windspeed

> 75 MPH 5. E xp los ion Within the Protected Area 6. Turb ine Failure Causing Observable Casing Damage 7. Vessel or Vehicle Collision With Structures or E quipment Required for S afe Shutdown or a Loaded ISFSI Confinement Boundary 8. F lood Level> 19.7 F eet Mean Sea Level 9. F looding in Areas Containing Safe Shutdown Equipment I NOTE: When two or more EALs apply , always choose the EAL of the highest incident classification; a lso always read from top to bottom i n each category. I l.__ __ _ __.ll _M_o_de_A_L_L___.I Other Conditions Exist For Which Judgemen t Indicates:

1. Actual Or Imminent Substantial Co r e Oegradation With Potential For Loss Of Containment, QR 2. Potential For Uncontrolled Radiological Releases.

These Releases Can Be Reasonably Expected To Exceed EPA PAG Plume Exposure Levels Outside The Site Bound a ry I C ON TROL ROO M E VA CUAT I O N I _M_o_de_A_L_L___.I l.__ __ J_UD_G_E_M_E_N_T_* _ __.I -M_o_de_A_L_L___.I U nit C ontrol fro m Auxiliary S hu td own P anel N OT Es ta b lished Within 15 Minutes After C ontrol Room Evacuation O the r C ondition s Exist F o r Which Judgeme nt Indica t e s Actu a l O r Likel y Major Fa ilures of P lant Func t ion s Nee d ed F or P rotecton Of T he P u b lic I C O N TRO L R OO M E V ACUA TI O N I ___ J_U_DG_E_M_E_N_T __ I Mo d eALL I C o n trol R oom E v a cua t ion Initiate d IG A2 1 ._l __ F_1R_E_IEX_PL_o_s_1 o_N __ _.ll __ I Fire o r Explosio n A ffecti n g S afe Shu td ow n Ar e a AN D D a mage to Str u ctures QB S a f e Shu t down E quipment Indicate d. I G A3 I I TO XI C FLA MM ABLE G A S E S I _M_o_d_e_A_LL __ j Li fe Th r e a tenin g To xic G a s e s QB Flamm able Gas Concent ratio ns as I de nti fied i n C-OP 2 0 0.5 , Oil , Haza r d o us M at eri a l, Hazard o us Was te a n d Mix ed Waste Cont in g e ncy P lan Affect i ng Areas for Sa f e S hut do wn A ny C ondition F or Which Judgement Ind i cate s Th at Sa fety S yste ms May B e D eg raded A n d W h ich R eq uir es Em e r ge n cy R es p o n se O r g an ization S taffing ____ F_IR_E ___ ___.I _M_o_d_e_A_LL __ I .._I ___ J_U_DG_E_M_E_N_T __ _M_o_d e_A_L_L___,I

1. F ire in Buildings O R A reas Adjacent to A rea s Needed fo r S afe S hutdown N OT E xting u ished Within 15 Minutes of Control Room Notificat io n OR Verification of Control Room Alarms 2. Fire a ffecting a loaded I SFSI co n fin e ment bounda ry N OT exti n g u is he d w it h i n 15 m inu t es I G U 2 I I TO XI C/FLAM M ABLE GASES I l,....._M_o_d_e_A-LL---.1

1. Life T hreatening T oxic G ases O R F lammable G a s Concentrati o n s as Iden t ified in C-O P 200.5, O il, H azardous Material, Haz a rdous Waste and Mixed Waste C ontingency Plan Affect in g Normal Operation

2. Notification of a Near-Site Release T hat May R equire Evacuation I A ny C ondi t ion F o r Wh i c h Judg e m ent I n di c a tes P o t e n tial D egr ad ation in t he L eve l of S afety o f the Pl a n t AREA S O F CONCERN FOR SAFE SHUTDOWN C on ta i nm en t B uil ding Au x il i ary Bu il d ing Co nt ro l Bu i ld i ng Mai n Steam Va l v e Building D e m i nerali zed Water S t orag e Tan k ESF B uilding Int a ke S t ru ct ure S tation Tra n sfor m ers E mergency G e n e r ator E nclosure F uel B u il d ing C LASSI F I CAT IO N GE N ERAL E M ERGE N C Y ALPHA OR BRAVO Events are i n process or have occurred which Involve actu a l or i mm i n e nt substan ti al core degrada ti on or melting with po t ential for lo s s of conta i nment i nteg ri ty or secur i ty ev e nts tha t r e sult in an ac t u al lo s s of p h ys i ca l cont r ol of the f acili ty. Re l eases ca n be reasonab l y exp e c t ed to e x ce e d EPA Protect i ve Action Guidel i ne e x posure le v els offsite for more than the Immediate site a r ea . S IT E AREA E M ERGE NCY CHARLIE-TWO E vents are in process or have occurred which involve an actual or likely major failure of plant functions needed for protection of the p ublic or sec ur ity events that r esult in intentional damage or malic i ous acts; (1) t oward site personnel or equipment that could l ead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the p u blic. Any releases are not expected to result in exposure levels which exeed E PA Protective Action Guideline exposure levels beyond the site boundary. ALERT CHARLIE-ONE E vents are in process o r 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 equ i pment because of inte n tional m alicious dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA P ro t ective Action G l!_ideline exposure lev e l s. I UNU S UAL E VENT I k-CC* I DELTA ,,, WO OR DELTA-ONE Events are i n p r o cess or have ,gccur r e d which indicate a potential degradation of the lev e l of safety of the plant or indicate a security threat to facility prote ct ion. No releases o f radioactiv e material requi r ing offsite response or monitoring are expected unless further degradation of safety 3 Millstone Mi ll stone Eme r gency P lan R evisio n 5 3 April 2016 I 7 of 8 MILLSTONE 3 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE IlVlMINENT

-No Turnaround in Safety System Performance is E x pected AND Escalation to G ene ral Emergency Conditions Will Occur Within 2 Hours INDICATORS FUEL CLAD BARRIER RCS BARRIER I FCB1 I I LOSS I I RCB1 I I LOSS I IT] Core Co oling -RED Not Applicable I PO T ENT IA L LOSS I I POTE N TI A L LOSS I 0 STATUS TREES Core Cooling -ORANGE 0 H eat Sin k -RED AND BOTH of t he Foll owing: 0 RCS Integrity -RED . Requ ired F eedwate r F low Can NOT B e E stablished Within 15 Minutes 0 H ea t S ink -RED AND R equired F eedwater F low Can . RCS Bleed and F eed Can NOT B e E stablished NO T B e E stablished Within 15 Minutes I FCB 2 I I LOSS I I RCB2 I I LOSS I IT] Core E xit TC Temp e ratures > 1200 ° F [TI RCS Subcooling < 32 ° F D ue to RCS Leak (115°F CORE EXIT TC Adverse CTMT) I POTENTIAL LOSS I I I TEMPERATURES POTENTIAL LOSS 0 Not Applicable Core E xit T C Te mperatures > 718 °F I RCB3 I I LOSS I Not Applicable I POTENTIAL LOSS I PRESSURE 0 Uncontrolled RCS Pressure Decrease and Increasing Conta inment Radiation Mon itors -.. I RCB4 I I LOSS I cg En try I nto E-3, " S team G enerator Tube R upture" AND Reactor Coolant Leak > Ca pacity of One C harging Pump I POTENTIAL LOSS I GOO LANT 0 R eacto r Co o lant Leak > Capacity of One Charging Pump LEAKAGE AND ANY of the followi ng: . E n try into E-0 , " Reactor Trip or Safet y Inject io n" . E ntry into AOP 3555, " R eactor Coo la nt Le ak" . En try in to AOP 3576, " Steam Generator Tube Leak" 0 En try i nto E-3 , " Steam Generator Tube Rupture" AND Reactor C oolan t L eak ..:s. C apacny o f One Charging P ump I FCB3 I I LOSS I S ustained Va li d RE-04N05A Read ing >

• A/h r. R eadings are I RCB5 I I LOSS I considered sustained valid when the effects of TIC have diss ipa ted. [TI Susta i ned Valid RE-04/05A Reading > 5 R/h r W ithou t ITJ Sustained valid RE-04N05A Reading > 5 A/h r Without R C S F uel Clad Barrier Loss. Readings are considered Re lease Inside Containment.

R eadings are considered sustained valid when the effects of TIC have diss ipated. RADIATION sustained va li d when the effects of T IC have d issipate d. ITJ At Least 5% Fu el Clad Damage As Determined By Core I POTENTIAL LOSS I Damage Estimate ITJ Dose R ate at On e F oot from Unpressurized RCS Sample Not App lica ble 1!. 50 mR/hr/ml ITJ RE-41/42 Read ing >0.040 A/hr S/D or> 0.060 A/H r Fu ll Power for > 15 M in. Without RCS Re l ease Ins id e Containment I POTENT I AL LOS S I *S ee T able 1 Not Applicable WATER I FCB4 I I LOSS I LEVEL Not Applicable I POTENTIAL LOSS I 0 RVLMS ..:S. 19% (Plenum) with OPERABLE 19% sensor (NA if no OPERAB LE 19% sensor) I FCB5 I -I I RCB6 JUDGEMENT Any C ondition For Which Judgement Indicates Lo ss or Potential L oss Any Condition For Which Ju dgement I ndicates L oss o r P otential of Fue l Clad Barrier D ue to: Lo ss of RCS B arrier Due to: . Immine nt Barrier Degradation Based On Current Safety . Immine nt Barrier Degradation B ased On Curren t Sa fety System P erformance System Pe rformance . D egraded F ission Barri er Monitoring Capability Making Barr ier . Degraded F ission Barrier Monitoring C apability Making Status I ndet ermi nate Barrier Status Ind eterminate CTMT BARRIER I C N B1 I I LOSS I Not Appli c able I POTENT IA L LOSS I 0 Contai nm en t -RED I CNB 2 I I LOSS I Not App licable I POTENTIAL LOSS I 0 Entt In to FR-C.1 , R esponse to Inadeq uate Core Cooling , or FR-.2, Response to Degr ade d Co r e Co oli ng with RVLMS ..:s. 19% (P lenum) with OPERABLE 19% sensor (NA if no OPERABLE 19% sensor)AND Core Ex it TC Tempe ra ture s D o NOT D ecreas e With i n 15 M i nutes I CNB3 j I L OSS I cg R ap id Unexplained CTMT Pr essure De crease Following In itia l Increase cg No CTMT P ressure In crease When Expectation Exists I POTENTIAL LOSS I 0 CTMT Pressure 1!. 60 PSIA AND Increasing 0 CTMT H 2 C oncent r ation1!. 4% I CNB4 j I LOSS I cg Pr imary to Secondary > Tech S pec Lim its AN D EITHER e x i sts: . Nonisolab l e Steam R el ea se from Affecte d S/G to environment. . P rolonged Release F rom Affected S/G to E nvironment When Use d for Co oldown. (see basis for descript io n of prol on ged release) ITJ F ailu r e of BOTH Isolat io n Val ves AND a P athway to the Environment E xists cg Entry In to ECA-1.2, LOCA Outside Containment , Is Requ ire d AND Reactor Coo lan t L eakage is Verified I POTENTIAL LOSS I 0 E ntry Into ECA-1.2 , LOCA Ou ts ide Co n tai nment I CNB5 j I LOSS I cg Offsite D ose P lu me Ra te 1!. 5x1 o-6 T imes RE-0 4NRE-05A -R eading if Coolant Loss is to CTMT I POTENTIAL LOSS I 0 Su stained Va li d RE-04 N05 A Reading >

• A/hr. R eadings are considered sustained valid when the effects of TIC have dissipated.

0 At Least 20% Fuel Clad Damag e As De termine d B y Core D am age Es t ima te *See Tab le 1 I CNB6 I I LOSS I ITJ No CTMT Sump Leve l Inc rease When E xpectation Ex i sts I POTENTIAL LOSS I Not Applicable I CNB7 I A ny Condition F or Which Judgement Indicates Lo ss or Potential Loss of C TMT Ba rrier Due to: . Imminent Barrier D egradation Based O n Cu r rent S afety S ystem Performance . Degraded F ission B arrier Monitoring Capability Making Barr ie r S tatus Indeterm inate MORE THAN ONE BARRIER AFFECTED GENERAL __ .\ ALP-HA *

t" SITE AREA EMERGENCY ONLY ONE BARRIER AFFECTED L p CLAD Time After Shutdown (hr s) ..

s.2 > 2to 4 > 4 to 12 > 12 Table 1 FCB3 ALERT ONE UNUSUAL EVENT DELTA-ONE CNB5/RG1 Fuel Clad L o ss Threshold Containment L o s s Threshold (R/hr) 200 125 50 25 3 Millstone M ills tone Emergency P lan Rev isi on 53 Ap r il 2016 1-8 Of 8 (R/hr) 800 500 200 100 AppendixJ APPENDIXJ EVACUATION TIME ESTIMATE PLUME EXPOSURE PATHWAY J-1 Millstone Station Emergency Plan Revision 53 April 2016 AppendixJ Estimates for Evacuation of the Plume Exposure EPZ The following tables sumrriarize 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. population estimates are based on the 2010 U.S. Census bl()ck 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. A 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 :p.etwork. J-2 Millstone Station Emergency Plan Revision 53 April2016 ... w s r-r > "C < g C'l i::: 6"'< =i ::s ,__ Ul 0\ w =i Region I Affecl2d Zone-s Swnmer MJdwlf1.e]c Midday Good Weather I !Rain* Summer WeekA;!nd Midday Good Weather I 1iaJn Summer Midweek Weekend Winter Mldwli!lelk:

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.,.. Vl 8 2,004 871 9 , 77(} c 61 S2 3,954 0 0 l.9,630 0 8,731 311 2 ,11 8 .! 38 0 1 , 669 (} 0 12,867 **' £ 45,4.56-1 , 617 4 ,&:!S 6,747 8,'552 0-0 f 236 , ... 0 °' 0 0 (]; 0 (} 0 0 0 NO T£S: ., lmnil,te pop.1latlon a , t York hi>s , , .. Within the sped;!! Far (his re;i:son , :.l,68S people have frcm pop,ilat ilan i n * "4! * :1> <i\l\ldd doul>le l;Ollnt,fng, h Unlt.ed S.tates Co.astGu.ard s n,idm U l rw;:luded in total school enrQ11ment. for this 1,100 ha.w b"" removed from the population In Zcme l8 to a cJ. .. L :.-oubl ec.oun!lng.

c. Shqdowfl'opulation information.

d.

Fadlit,le$ bQl:h medlcil l fa dll tles a n d fadlltles. AppendixK APPENDIXK SERO PERSONNEL TRAINING

SUMMARY

K-1 Millstone Station Emergency Plan Revision 53 April2016 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 (TPG) 7.212. In addition, EPA-FAPOl defines specific training requirements. See Reference

1. 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-26-training drill, facility walk-through or on-the-job training. EPA-FAPOl 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. --.*----* -Pr o vi d e fa miliarization training on the evenL .. c,: * '.

• _._-,
• 7 -----.-... -.. ,_.., ... .... . . Identify l\TRC initiatives in the area of accideni:. .. 1\cl iJ.. 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 14 the State of Connecticut. Provide training for performance of on-shift radiological dose calculations using 15 computer programs. K-2 Millstone Station Emergency Plan Revision 53 April 2016 TIPCK02 To Facility Address From Date/Time DOCUMENT CONTROL . DESK MP Department U.S. NUCLEAR REGULATORY COMMISSION DOCUMENT CONTROL DESK (7108) WASHINGTON, DC 20555-0001 CONTROLLED 05/05/16 11:38 DOCUMENTS Trans No. 000155179 Transmittal Group Id: 1610665 Total Items: 00001 Item Facility Type Sub Document Number I Title

• 0001 MP PROC EP MP-26-EPI-EPMP Sheet MILLSTONE POWER STATION EMERGENCY PLAN Revision 053 Please check the appropriate response and return form to NDS Bldg 475/3 Millstone Station or Fax to 860-440-2057.

§ All documents received. Documents noted above not received (identify those not received) . I no longer require distribution of these documents. Date: PASSPORT DOCUME TRANSMITTAL rrni Doc Date Copy # Media Copies 99 p 01 ,Dominion"' Administrative Procedure or Guidance and Reference Document Approval AD-AA-101 -Attachment 4 Page 1 of 1 1. Document Number: MP-26-EPl-EPMP

4. Title: . Millstone Power Station Emergency Plan 5. Requestor(s)

Print Name(s) I Bryce Wilkens 8. Document Request D New 181 Revision 9. Applicable Nuclear Station(s) Millstone 181 10. Reason and Brief Descriptio{l of Change: Modified U3 EAL GU1 and TU2 to include ISFSI 11. Records Retention Requirements Affected?

2. Revision:

3. Document Type: 053 181 Administrative Procedure D Cancel North Anna D 6. Date 4/16/16 D Supersede SurryD 12. Change Management:

0GARD 7. Requestor Phone 0973 D Temporary D Yes (Complete NRRS form from RM-M-101) 181 No Attach Appropriate Pl-M-4000 Attachment(s)

13. Level of Use: D Continuous Use D Reference Use 181 Information Use D Multiple Use Fleet Approval 14. Fleet Approval Required by: (Check one box only. Enter Peer Group Name, i.f applicable)

15. Printed Approver Name i .. "NIA 0 Peer Grou OR D Functional Area Mana er FAM t-l/A . . . l=S=i=te=A=p=p=ro=v=a;;::f

. =======:.======

.* .. -*= 18. Implementation Prerequisites: (Items in addition to those listed on Document Traveler or Change Management Plan) None 19. Implementation Prerequisites Reviewed-.Pro dl (..). :£-r*o;.,;

21. Check Nuclear Station(s) for Which Document is being Approved for Implementation.

Millstone 181 North na D 25. Facility Safety Review Co 1 ee Required?

26. Facility D No 181 Yes 28. Site Vice President Required?

29. Site Vice President)

Print Name/Signature 181No D Yes N/A 20. Date c.1 /rf'/rr NOTE: The individual s ostin a new or revised document to EDMS are res onsible for ensurin Nuclear E-Forms ls u dated. 31. Nuclear E-Forms Updated for Site(s)? 32. Nuclear E-Forms Updated Print Name/Signature

33. Date D MP D NA D SU 'lg] N/A 34. Document.

Number: MP-26-EPl-EPMP

35. Revision:

053 36. Effective Date Key: GARD-Guidance and Reference Document, EDMS-Electronic Document Management System 37. Expiration Date N/A Form No. 728620(0ct 2014) Do111inion Emergency Plan Title: Millstone Power Station Emergency Plan Revision Number: Effective Date: 53 5/12/16 Revision Summary:

• U3 *EAL GUl, added item 2 "Fire affecting a loaded ISFSI confinement boundary NOT extinguished within 15 minutes"
• U3 EAL TU2, added "or a Loaded ISFSI Confmement Boundary" to item 7, TABLE OF CONTENTS Section Page L. t fA di , . .. is o ppen ces ........................................................................................................................

vn List of Tables ............................................................................................................................... viii List of Figures ..............

...................................................................................................................

x ' 1. Concept of Emergency Operations ................ 1-1 1.1 *Description of the Millstone Emergency Planning Zones ..................

..........................

1:.1 1.2 Interrelationships ofState/LocaVLicensee 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 (Re.served) ....................................................................... 3-1 4. Classification System .............................................................

...............................................

4-1 5. Emergency Response Organization ..................................................................................... 5-1 5.X** * . P6sitions ................

.........

..........

........ : ..............

.-.........................................

._;._ .. s:.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 FirstAidTeam. .................................................................................................... 5-5 i Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 5.2 Minimum Staffmg 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 (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.l2-E('.ff i)Zc) ...........

, ;, ...............................

........ ;.:.'.i:.;5-J***:

.. * ,_. _,, /' 5.2.13 OSC -Assistant Radiation Protection Supervisor (ARPS) ...................... ...... .-:. 5-8 5:2.14 Emergency Information Specialist (EIS) .................................................

.........

5-8 5.2.15 Chief Technical Spokesperson (CTS) ................................................................ 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 ...................

.. ***************************************

5-9 5 .2.23 Corporate Support Director ................................................................................ 5-9 ii Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 5.3 Full Staffing Positions .................................................................................................... 5-9 5.3.l 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 ....... ,.-:;* ... :; ........................ .-... ,,:.,fr:.: .. :i ...... ; 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.l6 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.l Corporate Support Coordinator ........................................................................ 5-12 5 .4.2 Corporate Plant Information Coordinator ........................................................ 5-12 5 .4 .3 Corporate External Affairs Manager ................................................................ 5-12 iii Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 5.4.4 Corporate Emergency Plan Specialist.. ............................................................ 5-12 5.4.5 Corporate Executive Spokesperson (CBS) ....................................................... 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 ********oa*o****************************11*****0*********0*********************************0***111**********0** 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 (P ARs) .................................................... 6-3 6.2.3 Dose Assessment ................................................................................................ 6-4 r 2 4 <1,.':hc.*dc,."'gy . * ... -* ** 6-6 t), * -.,,, \.*.

• .* .Ll..Llti ,v '.*'. . *
  • • • ......... .* ... * ** * * *.** *:-*** ****.** . . ...
• ' . . . . -6.2.5 Sec*:mdaty Dose Assessment..

....................

• ......................................................

6-10 6.3 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 Detennination ........................................................ 6-14 6.5 Aid to Affected Personnel ............................................................................................ 6-15 6.5.l Exposure Control Guidelines**:******************** .................................................... 6-15 6.5.2 Emergency Exposure Control Guidelines for Off-Site Personnel.. .................. 6-15 iv Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 6.5.3 Decontamination ...................................................

...........................................

6-16 6.5.4 First Aid ..............................................

• ..............................................................

6-16 6.5.5 Medical Transportation ...............................................

....................................

6-16 6.5.6 Medical Treatment ........................................................................................... 6-17. 6.6* Public Information ........................................................................................................ 6-17 7. Emergency Facilities and 7-1 7.1 Control Room .......................................... ......................................

• .................................

7-1 7.1.l 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 7:2.3 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.l Function ..................

• ............................................................................................

7-4 7.3.2 Location .....................................................

• ... .-.....................................................

7-5 7.3.3 Structure and Habitability .................................................................................. 7-5 7.3.4 Layout .......................................................

.........................................................

7-5 7.3.5 Communications ................................................................................................. 7-6 v Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS

• Section 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 Emergency Equipment .. : .................................

..............................................................

7-7 7.5.1 Emergency Response Data System (ERDS) ...................................................... 7-8 7.6 Security Posts ..............................................................................................................

.. 7-8

., ..... '. .. ,;., *. .-: .. ....* ..*. ...................

.:.* ...................

....... . .:. *. : .** , ..*...*...

.:;,,:* .. "':-::;fr

.... --*: *-7.8 *Alternate

.ecation

... : ...... : ....... ........................................................

.....

..................

7-8 *'***", 7 .9 Communication Systems ................................................................................................ 7.:.9 7.10 Assessment Facilities ...................................................................................................... 7-9* 7.11 First Aid and Medical Facilities ....................................................................

.................

7-9 7.12 Damage Control Equipinent ......... .. '. .........................................

....... ; ..........................

7-10 7.13 Meteorological Data ................................................................................. 7-10 7.14 Innsbrook Corporate Support Center (ICSC) ............................................................... 7-10 8. Maintaining Emergency .... ................................. ., ........................................ 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 vi Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section 8.2 Tests, Drills, and Exercises ............................................................................................ 8-3 8.2.l 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 .......................................... 8-7 8.4 Public Information Programs .................................................................................. , ...... 8-7 8.5 Media Information Program ........................................................................................... 8-8 9. *Recovery

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • ci******a*ci***********ao*o************o*o***o*o*********a****1100***********************

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 .'3f .. ,, ..... : .. ., ... ? ....... .......................... ,.... ................. , *:*.. ..

9.2.5 Manager

of Radiation Con\rol/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 9.2.9 Licensing Department .....................

..................................................................

9-3 9.2.10 Millstop.e Representative in the SEOC and Joint Media Center ........................ 9-3 vii Millstone Station Emergency Plan Revision 53 Apri12016 ,;_\, .. 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 ....................................................................... 1-1 Appendix J -Evacuation Time Estimate: Plume Exposure Pathway ............. .......................... J-1 Appendix K-SERO Persorniel Training Summary ................................................................ K-1 viii Millstone Station Emergency Plan Revision 53 April2016 TABLE OF CONTENTS Section LIST OF TABLES 1-1 Off-Site Host Community and Reception Centers .......................................................

........ 1-4 2-1 Supporting Plans and s*ources ...............................................................................................

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:i J;ime Estfrnat.:1 Summary: ............................

-...........................

.. ,.; ....

ix Millstone Station Emergency Plan Revision 53 April2016 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-la Notification ofE!llergency Response Organizations

..... ." ................................................... 7-12 7-lb NRC Emergency Notification System and Health Physics Network ................................ 7-13 7-1 c 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 EvacuationRoutes.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 :W.i'ariofMills-i?nne JO Mile Emergency' Planning Zo11e*.; .. , ... ... ;* .*. :, ..... ;-,:,;i, * .-** , .. **. ;.-;; **** ;;, ** ;;;:: *** :c .. 5 . -' "C-5 Map of Millstone Station Evacuation Routes .......................................................................

C-6 E-1 Millstone Emergency Equipment Summary .......................

.................................................

E-2 . F-1 Diagram ofTSC I OSC Layout .............................................................................................. F-2 F-2 Diagram of Emergency Operations Facility ..............

...........................................................

F-3 F-3 Diagram of OSC Assembly Area Layout ....................................... _, ...................

• ...................

F-4 x Millstone Station Emergency Plan Revision 53

• April2016

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 50-mile planning zone for the Ingestion Exposure Pathway (IPZ). Millstone Station occupies approximately 500 acres and is located 3.2 miles west-soutl1west 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 50-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 ..agreed Massachusetts shci.11 be excluded frcr1T.* t:hr. . Millstone

.; * ':"'* '" ** *** *** . ,

• 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). In accordance with 10CFR50.82(a)(l)(i) and IOCFR50.82(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 53 April2016

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 focal 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 co_ntact 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 identify resources for each organization. Local radiological. emergency fil'c\t .. r.:o--vie.wed and, u::pi;r.o\:!ed* appropriate

• .. , ,*
• tocal programs training and pr,.:ciodk drills ot ex'!rdses;*
• 1.3 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 re$ponse 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, mid assessment of accident consequences. The licensee will classify the incident in accordance with federal guidelines and the State of Connecticut Nueiear Incident Classification Scheme. Tµe licensee will notify designated Connecticut and New York state and local officials and licensee personnel, as appropriate, within 15 minutes of an incident classificatfon. 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 York, 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. 1-2 Millstone Station Emergency Plan

• Revision 53 April2016 After initial classification, the licensee ensures that plant conditions are evaluated and updated information or event reclassification is completed as necessary.

1.4 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 :@. .. *T°l;fl:S program; as described in Se-2tion* for the meG.fa .. and provides .general radioiog:7_;ic;;,and*-

• • * ... emergency response infonnatio,;.1:
• ,
• 1-3 Millstone Station Emergency Plan Revision 53 April2016 . . '

Table 1-1 Off-Site Host Community and Reception Centers Local Community East Lyme Fishers Island, New York Groton, City of Groton, Town Ledyard Lyme Montville New London Old Lyme ,. :*. Host Community-Reception Facility New Haven -Southern Connecticut State University Moore Fieldhouse Windham -Windham High School Norwich-Norwich Technical High School Norwich -Norwich Technical High School Storrs - of Connecticut Fieldhouse New Haven -Southern Connecticut State University Moore Fieldhouse East Hartford -East Hartford High School Windham -Windham High School New Haven -Southern Connecticut State University Moore Fieldhouse

East Hartford,.

F.:;tst-Hartfot<l High Scfi.o.::>f. 1-4 Millstone Station Emergency Plan Revision 53 April2016 Figure 1-1 Emergency Response Organizations Responsibilities A. Licensee Responsibilities

1. Classification of event. 2. 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 ofNew 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 I. Activation of State EOC and Joint Media Center at SITE AREA EMERGENCY or higher level incident notification (standby at ALERT). 2. Notification of host comm.unities.

3. Notification of Rhode Island and New York (SO-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. Impler::J::ireio.f*

. *>1'

,>t;la '?r.tg.

<< fo::: ?*. r--:, ... \ . : ..... 1. Activation ofEOCs 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 IPZ States I. Activate EOCs at SITE AREA EMERGENCY (Standby at ALERT) level. 2. Monitor food pathways.

3. Implement ingestion pathway protective actions. 1-5 Millstone Station Emergency Plan Revision 53 April 2016

1-2 Responsibilities of State and Local Agencie'.i!. For The Various Incident Classifications i .* UNUSUAL EVENT* ' ALERT**

• All agencies acknowledge
  • All agencies Standby _ SITE AREA EMERGENCY 1 --GENERAL EMERGENCY J I Governor Direct actions of all State agencies.

Coordinate media releases. Declare a State of Emergency as necessary and assume overall command of State and local emergency response activities. I Department of Energy and Environmental Protection -Division of Radiation Conduct independent assessment of the incident and/or respond with assistance. Recommend public -protective actions, as necessary, I Deploy radiological monitoring teams to affected areas, as necessary, for radiation measurements. NOTE: In case of RADIOACTIVE MATERIALS INCIDENT OR GENERAL INTEREST EVENT only the Department of Energy and Environmental Protection will be notified per the State RERP. 1-6-,?, Divisi' on Erner Manage Homeland ger;.;c_ .. ::, . **:It menHf.!.n d rity Disseminate emergency data to local, State, and Federal agencies. Maintain communications with towns and respective DEMHS Area offices.

• Coordinate services, material support and manpower to the towns. Activate State EAS,_ necessary.

Provide radiatio.n monitoring support to the townsJ Notify and record "tr1'e actions of other State ag9_r;Gles. . ***/'\ :* ;* Activate host I Local Chief Executives Execute and direct emergency protective actions within their jurisdiction. Public Alert (siren) system activation. Further duties as defined in RERP. Millstone Station Emergency Plan * * * -:_ Revision 53 ik -: April 2016 -.:"{ . : I Department of Public Safety Serve as backup communications link between the site and State EOC. Provide traffic and access control. Assist local police in evacuation of residents in affected areas. Figure 1-3 Licensee Emergency Response Facility Responsibilities (ALERT or higher event classifications) Control Room

• Initial incident classification 2
• Implement mitigation actions
• Implement corrective actions
• Declare incident classification changes, as necessary
• Perform notifications, develop and transmit incident reports 2
• On-Shift Dose assessment
• , Initial 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 (P ARs) 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 * . , . fr. Provide !nput to Director of . . ,(h,. ,?i'i:r.;ritize TSC/OBC *assessment and repair activities in coordination
• ...
• o , 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 53 April2016

.*

2. Applicability and 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 1. State of Connecticut Radiological Emergency Response Plan 2. State Agency Procedures

3. New York State Radiological Emergency Preparedness Plan 4. State of Rhode Island Ingestion Exposure Pathway Emergency Response Plan 5. Local Community Procedures:

• Town ofEastLyme
• City of Groton " Town of Groton of :fishel,:* (NY) '"' Town of Ledyard o Town of Lyme " Town of Montville
• City ofNew London
• Town of Old Lyme
• Town, of Waterford

6. Host Community Procedures:

• Town of East Hartford
• UCONN I Storrs
• City ofNew Haven
• City ofNorwich
• TownofWindham

7. Lawrence and Memorial Hospital Master Emergency Preparedness Manual, Section II, Part K, Radiation Accident Plan 8. Treatment and Decontamination of Radioactively Contaminated Patient( s) at Middlesex Hospital 9. Manual of Protective Action Guides and Protective Actions for Nuclear Incidents Source State of Connecticut Division of Emergency Management and Homeland Security, State .Anllory Hartford, Connecticut State of Connecticut Division of Emergency Management and Homeland Security, State Armory Hartford, Connecticut New York State Disaster Preparedness Commission Albany, New York Rhode Island Emergency Management Agency Cranston, RI Local Community Emergency Management Agencies Local Host Community Emergency Management Lawrence and Memorial Hospital New London, Connecticut

• Middlesex Hospital Middletown, Connecticut EPA-400-R-92-001 U.S. Environmental Protection Agency 2-1 Millstone Station Emergency Plan Revision 53 April 2016 '1':-***

3. Section Intentionally Left Blank 3-1 . . '**-:l '-'* .. ( Millstone Station Emergency Plan Revision 53 April2016

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 mcidents be assigned a state posture code at the time of classification. The state plan also defmes 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 ate 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 L The emergency classificati9n_ nnd action level ' . . °i' .;'\

• -o; A '" ,.;. '.,\: < LJ '* . . . * . . . ,., . . . . , * .t'(.::> *,'-I: -'l.iD){ >>J requlremeut8;

.. _ . . . *.. ... . --.. 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 in 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. 4-1 Millstone Station Emergency Plan Revision 53 April2016

• Table 4-1 Unusual Event -Licensee Actions Class Description 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. No releases of radioactive material requiring 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 Corpo:i;ate 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.

8. A close-out 1erYorH2 provided with verbal summary to off-site authorities, foli:owed:by a -written summary to the NRC as required by 10 CFR 50.73, as appropriate.

4-2 Millstone Station Emergency Plan Revision 53 April2016 Table4-2 Alert -Licensee Actions Class Description ALERT (State Posture Code: CHARLIE-ONE): Events are in process or have occurred which an actual or potential substantial degradation of*the level of safety of the plant. 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 Innsbrook 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 pltime exposure EPZ. s.* Activation ofthe Station Emergency Response Organization (SERO) and appropriate emergency response facilities (ERFs) 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

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 slll111ilary to the NRC as required by 10 CFR 50. 73, as appropriate.

4-3 Millstone Station Emergency Plan. Revision 53 April2016 Table4-3 Site Area Emergency -Licensee Actions . Class Description 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. 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 Connectjcut and New York state agencies and local communities (responsible locatofficial) within the plume exposure EPZ. . 6. Activation of the Station Emergency Response Organization (SERO) anq ,PRFs . ' . *-* .* .. --*

! -.**i -: 7. 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* provided to off-site authorities.

12.

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 IO CFR 50.73, as appropriate.

'1 .** -;*_,. 4-4 Millstone Station Emergency Plan Revision 53 April2016

• • .*.:...

_.,._, Table 4-4 General Emergency -Licensee Actions Class Description GENERAL EMERGENCY (State Posture Code: ALPHA [significant radiation release] or BRA VO): Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. 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, l:!-S_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.-. ., '.' Establisr:tconnnunications with the SEOC iri Hartford, when activated.

--.. *.. 8: Notification of the NRC. 9. DepIOyment 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.

-.. ' 4-5 Millstone Station Emergency Plan Revision 53 April2016

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 CFR 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 anaiysis 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 'n Table 5-1. The DSEO has the discretion to relieve the activatiJn with :less. than, minimum staffing when the necessary specified positions are in accordance with NUREG-0654, Pianning '3tti.ndmi:t 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 hours. 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 staf.f, may be activated, as 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 m Appendix D, as applicable. This section also includes brief descriptions of the state, local and other organizations that would provide assistance upon request. 5-1 Millstone Station Emergency Plan Revision 53 April2016 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: e Shift 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
• FiJ;e Brigade .
• First Aid Team The minimum staffing management positions include the following:

s Director of Station Emergency Operations (JI. Assistant Director, Techtricctl St:tiV.ort fuhit i;-3) '*

• Manager of Technical Support Center
• Manager of Radiological Consequence Assessment
• Manager of Radiological Dose Assessment
• Manager of Communications (Unit 2, 3) *
• Manager of Operational Support Center (2 Positions)
• Chief Technical Spokesperson
• Nuclear News Manager
• Manager of Resources
• Emergency Information Specialist
• Corporate Support Director 5-2 :r, *, * . ,:.-:: ' Millstone Station Emergency Plan Revision 53 April2016

' .1 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 After being relieved .. by aIJ.9ther qualified, ........... , .. . the Shift Manager becomes the .{iontrof Rc-0n:i.. . 'Ope.rations (MCRO). The following CRDSEO .responsibilities cannot be*

• Event classification 4
• 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.

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 1. 5-3 Millstone Station Emergency Plan Revision 53 April2016 For a Umt 1 event, the Unit 2 SM/CFH functions as the CRDSEO. 5.1.2 Shift Technical Advisor (STA) The STA is responsible for the analysis of operational data 5. 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 The Emergency Communicator 1s 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 relate.cl fimctions in a;*'3c-rdance v1itL unit

• procedures, and as direcfod l'ij

* ** The PEOs

• provide . 'basic on-shift mechanical and 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 SMIMCRO. The Security Shift Operations Supervisor is assisted by security personnel in providing site access control and accountability. 5 This position is not reqllired for a pennanently 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 53 April2016

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 injuries.

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 to respond to the specific -; ... ,,* .. >_,.*, ....

• % minu:tes of facility activation*.

The following DSEO u;t\-: **2'-"<'1 1'-f 4elegated:

• 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.' 5-5 Millstone Station Emergency Plan Revision 53 April2016 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 8 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
• Evaluating conditions for directing entry into Severe Accident Management Guidelines

5.2.3 Manager

of Technical Support Center (MTSC) The MTSC reports to the ADTS. The MTSC analyzes operating data and provides support to the ADTS, MSRO, and the M.Of:C. .. .. ,.,*> ;:taff and Management Yearn report to the MTSCand

's

;;:U-ffifirlli';'

.* ,;: *;"* * *.

• assessment functions.

The MTSC is assisted by a mechanical engineei*, 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 assi.st 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 5-6 Millstone Station Emergency Plan Revision 53 April2016
• Approving Potassium Iodide (Kl) issue to emergency personnel assigned totheADEOF
• Developing, recommending and updating off-site P ARs 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 Kl 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 Radi?logical Communicators (RAD COM). ". : ,,, .,, .. ,. . , ._,; .... ;; .. ,: .. ,. , , .

• I:_<&u1:ag*'!'t-Qf Dose Asse.ssment . : -,,,' .. ** ,_;;.<: :,:y.:* *>-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 Radiologic;al 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. 5-7 Millstone Station Emergency Plan Revision 53 April2016

• 1., "'i, _,. ..

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) riTt::.1;E;:i!G to DSEO. The EIS assists the .. fogging &nd provides other administrative assisknr.*.,.:;. as * * ' * * .:' * . * .: needed. 5.2.15 Chief Technical Spokesperson (CTS) The CTS 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 CTS 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 CTS 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 53 April 2016 5.2.18 Technical Support 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, I&C Technician -.. : .,.. *: .. Th h . 1 . . d )'&rt T 1..-. * ' .. "' 1*. ... C"' <.\ ;{ e mec amc, e ectrician, an J: -' . ecrn11c1ru1 repmt 1.0

• ' .: .. *; *:*
• are responsible for assessment, rej_)air, and cortective
• **

5.2.23 Corporate Support Director 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 c:Roc 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 CTS and provides the CTS with technical information as required. 5-9 Millstone Station Emergency Plan Revision 53 April2016

' *.. .,\

5 .3 .3 Meteorological The Meteorological Assistant reports to the MRDA and provides meteorological data interpretation, calculations and long term meteorological. information to support dose assessment activities.

5.3.4 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 CHETS Operator reports to the MRCA. to the and assists the radiological assessment te'anr-in dose calculations.

5.3.8 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. 5-10 Millstone Station Emergency Plan Revision 53 April2016 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. 'i. ?., 7--0* T,.*,::hnical Rri(?>fer (TB) The TB reports to the Media Center Liaison and is responsible for providing technical, 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 briefmgs. 5.3.17 Offsite Monitoring Facility (OMF) 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. 5-11 Millstone Station Emergency Plan Revision 53 April2016 5.3.19 Station'Emergency Planning Liaison (SEPL) The SEPL reports to the CTS and is responsible for providing support to SERO and state personnel in the SEOC. 5 .4 Corporate Support .. 5.4.1 Corporate Support Coordinator

• 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
• Monitors the Operations Network and OFIS
• Provides the Innsbrook Corporate Support Center (ICSC) with technical . perspective

.1) . 5.4.3 *Corporate External Affairs Manager

• 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
• Provides assistance with facility operations and interpretation of the Millstone Emergency Plan 5-12 Millstone Station Emergency Plan
• Revision 53 April2016

5.4.5 Corporate

Executive Spokesperson (CES)

• Assumes responsibility as spokesperson from the CTS. If it is determined that a CBS 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 agenciesJ 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

• of

&gerc.cit:s may also be .Details of the expected are cmitained in lett-ers uf * ,

• agreement.

The letters are updated annually cir 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 tci an accident.

The licensee maintains work centers for both FEMA and the NRC at the 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. 5-13 Millstone Station Emergency Plan Revision 53 April 2016 Major Function-al Ar.ea Major Tasks Unit Operations and Responsible for safe operation assess. of operational of the unit including the aspects, assessment of implementation of normal & off-normal operational emergency operating aspects procedures Emergency Direction and Assume command and control Control, Support of of Station Emergency Operational Accident Event 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 Technical Spokesperson 5-14 Table 5-1 Station Emergency Response Organization Normal Position/Title<n> Emergency Position/Title Shift Manager (SM)/CFH Manager of Control Room Operations<q) Shift Technical Advisor, Station Duty Officer Security Supervision Shift Technical Advisor Shift Technical Advisor (STA) Unit Supervisor (US) us Control Operator (CO) co Plant Equipment PEO Operator (PEO) (Unit 2,3) Unit 2 Operator (Unit 1 responder and Unit 2 PEO Appendix R responder) Manager, Nuclear Director of Station Operations, Shift Emergency Operations Managers/CFH Directors, Managers Directors, Managers, Chief Technical Nuclear Specialist Spokesperson Licensing, Technical Assistant Engineers/Process Leadership, Maintenance Millstone Station Emergency Plan Revision 53 April 2016 Emergency Location Affected Unit CR Affected Unit CR Affected Unit CR Affected Unit CR . Affected Unit CR Affected Unit CR Unit2 CR Affected Unit Control Room<m> EOF SEOC/Joint Media Center SEOC/Joint Media Center On-Minimum StaffinQ *

• Full Training Rad Resp Shift 30-60 60 Staffing (b) Summary Worker Qua I Minutes Minutes (Refer to App K) 1 (d, i) 1,4,6,9, 14 YES YES 1 (a) 1,4 YES YES 1 ca. i) 1,4 YES YES 1 (i) 1,4,6,9,14 YES YES 2(i) 1 YES YES 2(i) 1 YES YES 1(i) 1 YES YES 1lffiJ 1,4,6,9, 14 YES YES 1 1 toJ 1, 4, 9, 14 1 1,2, 9 Major Functional Area Major Tasks Public Information Supervise public information activities.

Disseminate 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. Support coordination with CT Public Information Staff. Support public _information effort with 1eqhnical info(mation. Support public information effort with radiol.oaical information. Radiological Calculations Assume command and control and Event of internal/external Communications communications, radiological 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 Radiation Controls EOF, supervise Decon Facility Notification and Notify licensee, corporate, Communications federal, state and local officials. Communicate with CR. Activate EROS Notification and Coordinate technical data Communications communication between EOF, (Technical) CR, TSC/OSC, and qovernment aqencies. Technical Information Obtain plant data for Communications Emergency Response Facilities and Technical Assistant at SEOC as required. 5-15 Table 5-1 Station Emergency Response Organization Normal Position/Title<nJ Emergency Position/Title Various Nuclear News Manager Senior Executive Corporate Support Director Various Media Center Liaison Various Technical Briefer Various Radiological Briefer Managers, Supervisors Assistant Director Emergency Operations Facility HP Tech EOF HP Tech Work Control SRO Emergency Communicator STA/Security Supervision SDO Work Control SRO Emergency Communicator SRO TSC-Shift Manager/CFH Work Control SRO Emerqencv Communicator Operator Training Staff Manager of Communications Unit Personnel, Operator Technical Information Training Staff Coordinator Millstone Station Emergency Plan Revision 53 April 2016 Emergency Location SEOC/Joint Media Center ICSC SEOC/Joint Media Center SEOC/Joint Media Center SEOC/Joint Media Center EOF EOF Unit CR Unit CR EOF TSC/OSC Unit CR EOF EOF On-Minimum Staffinq *

• Full Training Rad Resp Shift 30-60 60 Staffing (bJ Summary
• Worker Qua I Minutes Minutes . (Refer to App K) 1 tn)(o) I 1, 4, 9 1 (h) 1, 4, 9 1 1, 4, 9 1 1, 4, 9 1 1, 4, 9 -. 1 1,4, 7, 9, 14 1 1 YES YES 1 \CJ 1,3,4, 9 YES YES 1 1, 4, 9 YES YES 1 1,3,4,9 YES YES 1 (9) 1, 4 YES YES 1,3,4,9 YES YES 1(9) 1 1,2,4,9 ' 1 (9) 1 1, 2, 4, 6 or 7, 9 Major Functional Area Major Tasks Administrative Support Provide administrative support to the DSEO. Maintain log for the DSEO. Facilitate information exchange with other emergency facilities.

Technical Data Ensure needs for plant data Communications and information are met. On-Site Radiological Direct On-site RMTs, sampling Accident Assessment program and radiation protection program. Perform dose assessment calculations. Radiological Surveys HP coverage and station surveys for repair, corrective actions, Search and Rescue, and fire-fighting. Personnel monitoring; and dosimetry . issue .. **

• Radiological Protection Radio Chemistry Assessments I Initial Dose Ass*essment Access control* Off-site Radiological Dose Coordinate off-site sampling Assessment program, dose assessment and core damaqe assessment Dose Calculations Dose Assessment,*

Radiological Calculations Radiological Control Within Provide radiological controls the OSCAA within the TSC/OSC, OSC AA and provides radiological support for emergency teams dispatched from the OSC AA Radiological Radio Deploy RMTs, collect data. Communications Radiological Surveys Off-site Surveys Meteorological Services Provide meteorological data interpretation, calculations, long term meteoroloqical information Environmental Services Plume and Ingestion Pathway and/or Health Physics Sampling 5-16 Table 5-1 Station Emergency Response Organization Normal Positionrritle<n) Emergency Position/Title Various Emergency Information Specialist Operator Training Staff Control Room Data Coordinator Radiological Protection Manager of Radiological and Waste Services Consequence Assessment HP Ops Support HP Ops HP Supervisors HP Technician RMT#1 Chemistry Technicians Chemistry Technicians HP Technician RMT#2 (A,B,C,D) Engineers/Manager-Manager of Radiological Chemistry Supervisors Dose Assessment Engineers/Analysts/ Radiological Assessment Specialists Engineer Chemistry Supervisors, Assistant Manager of Chemistry Training Radiological Dose Assessment Engineers/Analysts/ Specialists HP Assistant Radiological Protection Supervisor Site Services, HP Services Field Team Data Coordinator HPNarious RMT #3-4-5 and Drivers Environmental Specialists Meteorological Assistant Environmental/HP RMT #3-4-5 and Drivers Personnel and/or HP REMP Tech Millstone Station Emergency Plan Revision 53 April2016 Emergency Location EOF Affected Unit CR TSC/OSC Affected Unit CR CR, OSCAA NAP/SAP EOF EOF EOF OSCAA EOF EOF EOF EOF On-Minimum Staffing** Full Training Rad Resp Shift 30-60 60 Staffing (b} Summary Worker Qua I Minutes Minutes (Refer to App K) 1 : 1, 4, 9 2\9) 1, 2, 4, 9 YES 1 1, 4, 9 YES 1 (d} 1 1, 4 YES YES 2<d.f) 1, 15 YES YES *'. 4 1, 4 YES YES 1 1, 4, 5, 7, 9, 11, 12, 13, 14 2 1, 4, 5, 9, 11, . 12, 13 2* 1, 4, 5, 7, 9, 11, 12, 13, 14 1 1, 4 YES YES 1 . 1, 4, 5, 9 2 4 1, 4 YES YES 1 1, 4, 10 2ui YES Major Functional Area Major Tasks Contingency Offsite Set up and operate Offsite Contamination Monitoring Monitoring Facility for Station Staff Accident Assessment Assume command and control Management and of the station operating, Consequence Mitigation technical assessment and repair staff. Recommends chanqes to classifications Unit System Engineering Responsible for analysis of operations data, development of procedures, *recommend repair, and corrective actions Assist Manager of Technical Support Plant System Engineer Assist of.Technical Repair and Corrective Support.Provide accident Action analysis

• Repair and Corrective Evaluation, repair, and Actions corrective actions Operational Support Coordinate on-site activities and personnel Resource Acquisition

& Coordinates requests for 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 5-17 Table 5-1
• Station Emergency Response Organization Normal Pos'ition/Title<n>

Emergency Position/Title Radioactive Material OMF Staff Technician Manager-Operations, Assistant Director, Supervisor Nuclear Shift Technical Support Operations, Supervisor-Operator Training Manager-Engineering/ Manager of Technical Supervisors, Engineers Support Center Manager-Site Services Mechanical Engineer TSC-ME Electrical Engineer TSC-EE Reactor Engineer TSC-RE Nuclear Instrument Generation Test Services Technician (GTS) Specialist Safety Analysis, Nuclear Accident Management Fuel Engineering Team-Leader Safety Analysis, Nuclear AMT-Thermal-Hydraulic Fuel Engineering Engineer (T-H) Manager-Maintenance Manager of Operational Supervisor Support Center Mechanic Mechanic Electrician Electrician l&C Technician l&C Technician Supervisor-Maintenance OSC Assistant Supervisor-Maintenance OSC Assistant Various Manager of Resources IT Personnel None Millstone Station Emergency Plan Revision 53 April2016 Emergency Location EOF TSC/OSC TSC/OSC TSC/OSC TSC/OSC TSC/OSC OSCAA TSC/OSC TSC/OSC TSC/OSC, OSC AA OSCAA OSCAA OSCAA TSC/OSC, OSC AA TSC/OSC, OSC AA EOF Millstone Station On-Minimum Staffing** Full Training Rad Resp Shift 30-60 60 Staffing (bl Summary Worker Qua I Minutes Minutes (Refer to App K) 5tPJ. 4 YES 1(9) 1 1,4,6, 8,9 YES 1 1 1,4, 7,9 YES 1 1 1, 2, 4 YES 1 1 1,2,4 YES 1 1, 2, 4 YES 1 1 YES 1 1,2,4, 8 YES 1 1, 2, 4 YES 1 1 1, 4, 9 YES 1 1 1 *YES YES 1 1 1 YES YES 1 1 1 YES YES 2 1, 4, 9 YES 2 1, 4, 9 YES 1 1, 4, 9 (i) Major Functional Area Major Tasks Firefighting Firefighting and communicate and strategize with Control Room Search and Rescue Search and rescue operations Operations External Response Provide logistics support for Logistics external response personnel. Liaison with NRC Site Response team. Backup SERO Communications with Notifications ADTS/DSEO. Backup SERO Notification System Communications HP Communications Exposure Control Exposure Monitoring First Aid Emergency Medical Services -Site Access Control and Establish EOF security. Directs Personnel Accountability Security Personnel in support of emergency operations (firefighting communications, personnel accountability) assist in personnel accountability Establish station security, Support emergency operations and perform personnel accountability Supervise on-site security operations Support Provide support to SEOC staff Provide support to EOF staff 5-18 Table 5-1 *Station Emergency Response Organization Normal Position/Title(n) Emergency Position/Title Fire Brigade Fire Brigade Security Personnel I Security Personnel I Station Station Personnel, as Personnel required Licensing, Engineering Regulatory Liaison Security Personnel Security Person -HP Staff RAD Communicator HP Staff CBETS Operator First Aid Team First Aid Team Security Personnel Manager of Security Security Personnel Security Personnel Security Shift Operations Security Shift Operations Supervisor Supervisor EP Narious State Emergency Planning Liaison EP Staff Station Emergency Preparedness Representative Millstone Station Emergency Plan Revision 53 April2016 Emergency Location As Required As Required EOF CAS/SAS EOF, TSC/OSC OSCAA As required TSC/OSC SEOC/Joint Media Center EOF Totals Unit 1 Unit 2/Unit 3 On-Shift Minimum StaffinQ *

• Full Training Rad Resp 30-60 60 Staffing (bl Summary Worker Qua I Minutes Minutes (Refer to App K) Per Local 1 YES YES TRM<al Comm and Support FPER(al Per Sec. 1 YES YES Plan 1 1, 4 1 1 YES YES 2 1, 4 YES 1 1, 4 YES 2 (a) Local 1 YES Comm Support 1 1, 4, 7, 9 YES Per 1 YES YES Security Plan 1(a) 1, 7 YES 1 1,4,9 1 1,4,9 10<1<. 0 11 3o<eJ 38 15(k, I) 11 30(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 hours. c Station position (Counted as affected unit resource).

d One for Unit 1/Unit 2; one for Unit 3; (for Chemistry and Health Physics, two each per site) e Assigned, affected unit resources, addltional 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-l)perating 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. On-Shift total reflects Shift Manager I Affected Unit Control Room DSEO as one position. m For a Unit 1 event the Unit 2 SM/CFH becomes the CRDSEO; after_ responsibilities to the ADTS and EOF DSEO, the Unit 2 CRDSEO becomes the n Higher level personnel may be used to fill these roles as necessary. o A 90-minute goal has been established for the Chief Technical Spokesperson 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 from.the-time of notification to report to emergency assignments. 5-19 Millstone Station Emergency Plan Revision 53 April2016 Figure 5-1 Organization of Station Emergency Management Personnel (Page 1 of3) Senior SERO Management Structure ADTS (Onsite Response) I ADEOF .(Offsite Response) Public Information SERO Structure .;/. .. -CTS-(Public Information) _ --. I Tech Assistant State EP Liaison II Indicates positions necessary for facility activation. D Indicates fully augmented organization positions .. 5-20 *Millstone Station Emergency Plan Revision 53 April 2016 Onsite SERO Structure .F1s:are 5-1 Organization of Station Management Personnel 2 of3) )ADTS ------------..-------......,...

• ,j;,,W"'*""*

"'4-------1------------------ MTSC Electrical Eng Mechanical Eng Indicates on shift positions. II Indicates positions necessary for facility activation. D Indicates fully augmented organization positions. 5-21 -.. .:. MRCA MOS .... **-*::.:.:;,:.:,:;:-*

• _.:,* ;:::,. *:::-;*(_::*:.:=;

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

... * .... ** .....,..-'-'-'.-.....-------------.\;1y;g .....,._ _____ __.)/X? .*. :.-...>,*' ....... . . * .... ** . * .. *:. ****: .. : .. : ***** .... . *,.:,., .** . ....-.... = .-:=.* ... '.*,1:.i.'.:; ...

• :* ... *.' ',*:* .. ::*:*.: ..... :** ' ' . . Millstone Station Emergency Plan .,_, * . *:* ** . Revision 53 *-<" ;r* . April 2016
• ._.

,--' -\\*;* .,., 5 1 -Organization and Location of Emergency Management Personnel (Page 3 of3) Offsite SERO Structure II D MRDA Rad Com Met Assistant Indicates positions necessary for facility activation. Indicates fully augmented organization positions.

• I I Station EP Rep Reg Liaison --.J

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 proteetive 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, the NRC and initiating immediate actions necessruy to limit the consequences of the emergency reside with the Shift Manager (SM), who is on site 24 hours 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 terrr.iinated. After relief by the EOF DSEO, the SM assumes responsibility as Manager of Control Room Operations (MCRO). The CRDSEO /DSEO 1s responsible for ensunng that timely and appropriate notifications are made. .. . . "** ' *' J;n:f:.fJ be transferred during a normal shift rbta:iior. when a qualjfied. Teliefre.ports 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. 6-1 Millstone Station Emergency Plan .Revision 53 April2016 . ..... * .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 commurucate 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 o_:fficials aclmowledge 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) The ill.itial or reclassification messages are received by off-site officials calling the dedicated telephone numbers provided to each responder.

The information above is repeated and additional information is provided as follows: e Date and time of event classification ];'.farf:l.e ind Title of communicator

• _.-;,* .* ' ;i. .. Verbal summary of incident details (major and ininor 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 o:ffsite 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. 6-2 Millstone Station Emergency Plan Revision 53 April2016 The Chief Technical Spokesperson, 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 co111Iliunication 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 InitialAssessment Event classification is based on EALs. The EAL tables. provide. an incident '

• based on instrument v3:;\q;l:J I.ti; fr1

.. . . . .The NRC incident classi:fi\'::a:tlo.tt e.m.il pbsture codes are transmitte.d to state and local

• • :.:* :::. On-Shift dose calculations are conducted, when appropriate, and used to validate the incident classification and any PAR if applicab,le.
• The Shift Technical Advisor (STA) provides independent assessment of emergency actions. When activated, the T$C 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. P ARs requiring evacuation: are to be initiated only for GENERAL EMERGENCY events. Millstone Station Emergency Plan Revision 53 April2016 P ARs 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 P ARs are warranted from the Control Room before activation of the station response organization, the appropriate P ARs 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 action 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 associated with the GENERAL EMERGENCY posture codes. When emergency response facilities are activated, the State DEEP wiil collect and process information to independently verify and recommend changes, if necessary, to the licensee provided P ARs. 6.2.3 Dose Assessment

• : *I ",;:*. ***' ** ** * *. *, ;"-'* " Radiologj.G11.1 .asi:>es;tm,.i:nt:;*.
• by* fhe SERO include -dk.l't'.JJ.'n:,Gnaiit1!Jl 0 t)f :rs.ditkiO:tr*
• exposure rat.tl!s*

by both analytic.* ancl direct* measmement

• 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 IvlRCA. Off-site RMT activities are coordinated by the FTDC under the direction of the MRDA. Field data and projected dose information is transmitted to the State DEEP, as necessary. The emergency plan procedures contain methods for relating the var10us 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. 6-4 Millstone Station Emergency Plan Revision 53 April2016

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 containrp.ent of radioactive materials if 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 vfilues 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 I gaseous effluent releases are-continuously monitored . for radioactive gases by a Spent Fuel Pool Island (SFPI) radiation monitoring Gaseous effluent is sa1npk;k for . continuous sampling system which collects fer: ani:tlJsjs, . 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. 6-5 Millstone Station Emergency Plan Revision 53 April2016

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 rates. The high-range radiation monitor.readings . are tu r03:ease rate using C;.

f1ctor. Gi:ab

, .7::* * . * , * **"" {,::: results, if available, may be more accurate than .rcadiag-3.

• * *. ,,*.
• 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 detennine the quantity ofKr-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 predetennined noble gas ratio (depending on the plant conditions) to obtain the iodine release rate. 6-6 Millstone Station Emergency Plan Revision 53 April2016

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.

e 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 The assessment methodologies used* by l'v'.lillstone Station are intended to provide a rapid best estimate of core damage which, when evaluated together, help to develop ail 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. 6-7 Millstone Station Emergency Plan Revision 53 April 2016

• Containment and Main Steam Line Radiation Levels: An indirect 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. Sam nl1e Anailvs1s -,ii, .. ........ <>fuod . ___ .... ... .. .... . *.* -* .

• • * .. : .. ** 1 . .:Vhi.ch yield:JtP..,e

t.nost accurate* . * :(:or all types of ac,iidents.

Requires swifp-leci system( s) be in a'

• steaqy 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. 6-8 Millstone Station Emergency Plan Revision 53 April2016

f. Committed Dose Equivalent (CDE)-Thyroid 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.

g. 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 t"'"('}n*<, ... o;:.fu:u 0ff-*sit*"'

• . . .. ** )!'.,. '*'"J..".:.I.
• '-.'lb *L ,.,_,,

..... :,. ,t<* _ 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 Thermo luminescent Dosimeters (TLDs) 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.

6-9 Millstone Station Emergency Plan Revision 53 April2016 . -_, ...

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 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. . -" . -' . -l',..,,:-*; -* T'he followillg additiOnal corrective. actions a.re implemented

' ,. 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 assista,nce is needed, the Waterford Fire Service is called. 6.3.2 pamage 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. 6-10 Millstone Station Emergency Plan Revision 53 *April 2016

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 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 briefmg process unless immediate access is authorized by the ADTS to facilitate emergency repairs. a. Notification ' .... , ,*'* . *'\ The actuation. of radiafam station . ¢metgency .. . . alarm, fire alarms, and public. address 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 53 April2016 A precautionary dismissal directs all non-essential Millstone employees, contractors, and visitors to leave the site. d. 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.

Eyacuation 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 . J?-f!rt of evacuation, may be to a fot:.*m-onitorh1g and de<X'l;n;tamination. 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 units for the imme4iate 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. 6-12 Millstone Station Emergency Plan Revision 53 April2016

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 involvt1d 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 mi,ssing.

Accountability is required to be completed within 45 minutes of its initiation (the names of any missing persons identified to the DSEO orADTS and announced over the PA). If precautionary dismissal or evacuation could endanger plant personnel, h . b d r.* d .. 1 ,., .. 1*. h -.;. ' 1 *,a* ., .. t ese ac*t-1ons may e e :4rr1"'* *

• .-'i:*o<':*.
• *

.. :,*: ,; ""' f..1 ... ' p;;... i,,_ (,.,f...,I.:.' . .., *** .-,,..u .a..'Y . * . -. conditions warrant; dismissal, evacuatkm. and accountability will be* .. performed, as appropriate.

1. 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 monito;ring personnel.

An off-site monitoring location will be established if radiological conditions on site prohibit adequate monitoring. Each ERF has radiation detection equipment. The MR.CA 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). 6-13 Millstone Station Emergency Plan Revision 53 April2016 . . ' *'.t, 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 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 " f th "t *11 i**r.1. -*,.. ...

... ,.-...

• • -.e*-*.:.'!..'i" "f ..... , *,:.._., ..
• *. . .' _., .. ac"-ecs areufl 0 Sl e Wli .;.,.,. 1.i{)b:z.O,* .
  • :,.,;: * .;;:

.a

** * * .* e. Radiological waste material will be 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 hours 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) and permanent recording dosimeters (TLDs) 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. 6-14 Millstone Station Emergency Plan Revision 53 April2016 TLDs 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 TLD results become available. The TLD 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.l 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 will be

• evah:at.:'<l for administration to i:,'.ff."'i!ff.
• * * * *'". I ** I ;'t* **** I.,

.... J * .,,,....._ .-.. "l * * ** '\vith emergency. procedures. Exposwces are 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 site responders in accordance with the RPM. 6-15 Millstone Station Emergency Plan Revision 53 April2016 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 (Le., TLD and pocket dosimeter). 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 decontamination are provided. If on-sitc are not usable because of irwmn:ID!.\.i.* 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 hours per day. If necessary, a physician may be requested 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. If 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. 6-16 Millstone Station Emergency Plan Revision 53 April2016

6.5.6 Medical

Treatment Anangements for the primary care of injured, or radioactively contaminated injured personnel are made with the 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 Informat'ion 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 Chief Technical Spokesperson (CTS), 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 F AXed logs from the DSEO/EIS, and plant monitoring systems (OFIS).

• The NNM reports to the Chief Technical Spokesperson at the Hartford Armory. The NNM interacts with the State and Federal media staff at the Joint Media Center and provides feeaback including identified rumor trends to the .ICSC. The Cqrporate
• *(. * . .. * *' *. * ' , . . * * '. ; * ' ' '-I* *,

  nhn&'ge:t tepo . .:<ts

_Support Diiecto:::; the

• -Die fJo'rporate External Affairs Manager devek*:pE and. distributes news 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 Chief Technical Spokesperson represents the licensee in communications with state decision makers at the SEOC and represents* Dominion in media briefs. The CTS may be relieved by a CES at which time the CTS assists the CES in an advisory role and manages the Dominion staff at the Hartford Armory. 6-17 Millstone Station Emergency Plan Revision 53 April2016 Table 6-1 Emergency Exposure Limits Category TEDE Annual Part 20 5.0 Rem(I) Mission to protect valuable property 10.0 RemC 2) Mission to save a life or prevent/mitigate a severe accident Voluntary mission to save a life or prevent/mitigate a severe accident 25.0 RemC 3) >25.0 RemC 4) 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 CFR 50.47(b).11 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 IO Rem TEDE for operations necessary to protect valuable property ..

• on station radiological
• .;*, ex;osures up to*a job/mission-specific designated nut
• ( 4) . Exposures above 25 Rem may be received for life saving activities on a volunteer basis and with full awareness of the risk involved.

e 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 CFR 20 requirements following termination of the event.
• Total Effective Dose Equivalent is defined as part of the station health physics program. 6-18 Millstone Station Emergency Plan Revision 53 April2016
• ' I*,. ,:, . ..'

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 site emergency response facilities (ERFs) are indicated in Table 7-1. The various facilities and equipment are controlled and -surveilled, using MP-26-EPA-F AP05, "Emergency Planning Facility Manl,lal," 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 a Programmable Logic Controller (PLC), two control stations in "monitor mode" only (they can be reconfigured to the . control mode), and an alarm printer. No control functions are available in the "monitor mode." The Unit 2 control room contains 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 and the other ERFs concerning system problems .-as* ...... ,wti:1frL.::is 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 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 applicaple to Unit 1 's decommissioned condition, including the Spent Fuel Pool Island. 7-1 Millstone Station Emergency Plan Revision 53 April2016 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:

• Reactor coolant and Auxiliary systems
• 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 p.0rs.:-rn_r1d transmit notifi.eation Si:'.;l,ff'.

• loe.al emergency

-. 1 1 1 d th t" .c . . . . . . ac mow e ge e nD'

• Cf.ill
• r*E:e1ve a yo1ce-:'.ecorded summary report describing the nature of the incident and the plant status. 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 Millstone Station Emergency Plan Revision 53 April2016 . / ' ...

7.2 Emergency

Operations Facility 7.2. l 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-::;ite data sources and off-site organizations. Emergency radiological monitoring and decontamination equipment and supplies, protective clothing, and respiratory 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 statio.n.t,?.-rotected area, {:refeHo* Appendix F, Figure .. f,,2);,* An alternate EOF is located in the Unit 3 Control Room Tagging Area 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 i power. 7 .2.4 Layout The EOF functional areas are indicated in Appendix F, Figure F-2. 7-3 Millstone Station Emergency Plan Revision 53 April2016 . . 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

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 d * *

• d
• h pr.r Tl..*
• r. *
• l DOF
• proce ures is mamtame mt . p;;,:;

.s* 'l't0!ief/.at.

t1e;*;e .** m. hard copy or electronic form. 7.3 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. 7-4 Millstone Station Emergency Plan Revision 53 April2016 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 con;nnunications with the NRC senior representative on site. J 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 10CFR50 Appendix A, General Design Criteria
• 19 guidelines and the NRC Standard Review Plan for Control

,> .;* *.. ..:," '<'. _ .. Thyroid . Whole body gamma Beta skin dose 30Rem 5Rem 30Rem The HV AC 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 HV AC 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 aisplays. 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. 7-5* Millstone Station Emergency Plan Revision 53

• April2016

7.3.5 Communications

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.

7.3.6 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 ..... *.* The OSC is *a protected area facility, co-located withiii 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. 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/QSC (see Figure F-3). "' 7-6 Millstone Station Emergency Plan Revision 53 April2016

7.4.3 Structure

and Habitability The OSC has the same habitability as the TSC. The OSC Assembly Area has no specific habitability criteria.

7.4.4 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 0 Portable Radios 11 Protective Clothing
• Respiratory Protection A:cceE:s to c%:i;ditioual HP and maintenance equipment is readiJy spc'Cif:fo materials requifod to-perform OSC functio:1;1s. , ' The OSC AA contains the following equipment:
• Dosimetry issue equipment
• Portable radios
• Hotlines and fax machines 7.5 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-EP A-F AP05. 7-7 Millstone Station Emergency Plan Revision 53 April2016 7 .5 .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.

• 7.6 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 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.

7.7 Joint

Media Center .. , .. : .. Joint Media Center is located within thtd}iJ:JC* Trri*'JoiliF**

• . . Media Center is activated by the State DErv.tliS

.. principal rneclia contact poin,tfor 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 .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. 7-8 Millstone Station Emergency Plan ' Revision 53 April2016 7 .9 Communication Systems 7.10 7.11 The communication links between emergency response centers and off-site agencies are shown in Figures 7-1 a through 7-lc. These systems provide* reliable communications and consist of a combination of the station PA system, emergency alarm, intra,plant telephones, computer terminals, dedicated hotlines, commercial and utility (tie-line) telephones, satellite phones, facsimile machines, an4 two-way radios including utility, State Police, Waterford Police, a,nd 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 corrimunication between.the EOF * . I and RMTs. Police and utility radio communication are used by the Control Room in event of the failure of the telephone system for communications. Backup power is for selected communication links in the protected area and the EOF. Ambulances are equipped with radios and can communicate with the hospital. Nornial 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 contacte<l; through the Connecticut DEMHS and. State Police as described in the State RERP. Fishers Island and Plum Island, New York, .. ::i:r-e witbint}l.e plume e4posure ... EP Z m.id ard notified of emerge11e;y . .,:... *'* ,,,;.:: . * * .. ,.

• ':;:,,,,,.::

<'" . ... . . ..

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 IvfRCA 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. 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. 7-9 Millstone Station Emergency Plan Revision 53 April2016 7.12 Damage Control Equipment Damage control equipment consisting 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 i450-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 10-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 of i;neteorological data t:ly tht.** .:: . . system, an electronic data acquisition network. If EDAJ\Y-:iS-,

.1ritical d::tta may be obtained over *the telephone from operators reading Unit 3 Plant Process. Computer data. If the prinurry 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 obtain . 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.

7-10 Millstone Station Emergency Plan Revision 53 April 2016 Table 7-1 Locations Of Emergency Response Centers On-site 1. . Control Room 2. OSC Assembly Area (OSC AA) 3. Technical Support Center/Operational Support Center (TSC/OSC)

4. Alternate TSC . 5. Alternate EOF Off-site 1. Emergency Operations Facility 2. . Assembly Area 3. Joint Media Center 4. State Emergency Operations Center Location Unit 2 and 3 Control Room Cafeteria, Bldg 475 Adjacent to and below Unit 3 Control Bldg. EOF Unit 3 CR Tagging Area Location 18 Stott Avenue, Norwich, CT Simulator Foyer in the Training Building Connecticut State Armory (Hartford)

Connecticut State Armory (Hartford)

5.

Community Emergency Operatiu:!1&:

• ..

Radioiogical

• , *, Centers Response Procedtires*
  • ...... :w .. *-<w,;'.;"-').*

6. Alternate Location 7. Remote Mustering Area 8. Offsite Location Corporate

1.

Corporate Support Center . (ICSC) . State EOC (Armory) Hartford, CT EOF, Norwich, CT EOF, Norwich, CT Location

• Richmond, VA (Innsbrook) 7-11 Millstone Station Emergency Plan Revision 53 April2016 ON-SITE RESPONSE CENTERS T CONTROL ROOM UNITS2AND3 EN T EOF* EN T TSC/OSC/OSC AA EN STATION ON-CALL EMERGENCY RESPONSE ORGANIZATION EN *Located offsite Notification ofEmerge:u;icy Response Organizations T T EN 7-12 T EN EN T EN T COMMUNITY EMERGEN,CY RESPONSE CENTERS CONTIGUOUS T STATES OEM (RI) (NY) Sf/\TE DEEP ... S1'i(TE POLICE. TRQOP EAND F STA1E 1DEPT OF PUBLIC SAFE1tr' COMM CENTER *

... .. STATEDEMHS T : . AFFECTED RESPONSIBLE. OFFICIAL East Lyme. Montville Rshers Island (NY) NewLondon . G-otonCity Old Lyme G-oton To\Nl1 Plum Island (NY) Ledyard ': Waterford Lyme . ':* * :Millstone Station Emergency Plan ., Revision 53 * . .** April 2016 Leg -end: T_ Corrmercjal Telephone Lines EN Bectronic Jlbtification -/ MPEPLAN6.PPT

• Located offsite EYru-.re 7-lb -;*: NRC Emergency Notification System (ENS)

Physics Network (HPN) Millstone Station

• ON-SITE EMERGENCY RESPONSE CENTERS Control Room Units 2 and 3 Emergency Operations Facility* . Technical Support Center
• NRC EOF Command Post NRC Resident's Office 7-13 E E J:. { . Q . . ; ; FEDERAL GOVERNMENT EMERGENCY RESPONSE CENTERS ,___o_e_d""'"ic_at_e_d_li_ne....,s are bridged between NRC and Utilityfacilitie NRC NRC Emergency 11111( E --..i,_ Region 1 Operations Emergency Center H --Response Center* ;,_. H I J Legend: E __:.:_ .. -------r,: -E --ENS -Emergency Notification System, dedicated hottines.

E --H --* HPN -Health Physics Network normal long distance.

• Mill,stone Station Emergency Plan * *Revision 53 April2016

-* ii'i9"'.;;re 7-lc . .,.,_,11.(*r.r::..;:;....:....::;..;;. Lines of Communications Between Emergency Response Centers Millstone Station On-Site Emergency Response Centers . *. State and Local Community Emergency Response Centers --R-' Dominion I Corporate . Executive .I . I . 0 -T-* I Control Room -Unit 2 and 3 -,..:--I I I I -T-I I --I -T-I I I I I -,.. ,. --R-. I I I TSC/OscctJ OSCM Operations Facility.Center* RadiC?lOQical Morntonng Teams ---i--R-. I " " . -: : I ': ---I * -I --. I Innsbrook -* Corporate I --Support Center . I ' I -I I --I I -.... -_. _' --* -----""'""" """ . I -R-"' Legend: .. -T -Commercial -.t!!J. Telephone

• -* Telephones

-R-Radio (U2/3only) FAX Machine --,r Oata Line -Information Line to 06minlon Energy * -T-Contiguous ,___ States (RI) (NY) Affected -T--T-Community EOG Affected -(Waterford) Community EOC -R-I -T State DEEP Desk -R-State EOC I State Armory - -T-Dominion StateEOC --Corporate Joint Media Cir. Nuclear Public Information state Police -T-Troop"F" --R-State Police i:I: . . . Troop"E" Dept of Public Safety -T-Comm. Center *Located offsite 7-14 .. ::, Millstone Station Emergency Plan * -1 Revision 53 April 2016 *-* ;.-. Maintaining Emergency Preparedness Station management is responsible for the staffmg 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) . ., Preparation and conduct of emergency plan drills and exercises.
• Training off-site emergency response personnel.
• Providing input to SERO training.
• Coordination of licensee, state and local emergency plans and procedures.
• 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-jC'b . tr2itth1g

.. nn 1:1 superv.ised kdministration and management 0f . is detal.led in - Emergency Preparedness*implementing -* , * * ...... * .. *:-.. *<' ""';* .,. *** * ... :*. 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. 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-MP-TPG-2400 and MP-26-EPA-FAPOl. 8-1 Millstone Station Emergency Plan Revision 53 April2016 8.1.2 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 inf01mation. 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. In 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 em:ergency organizations are trained in radiation monitoring and protection, activation and operation of evacuee reception centers . . 8.1.3 Additional Emergency Preparedness Training a. Plant Access Training (PAD Employees obtaining unescorted access to the station. for frrst time .. receive ... part. 6-f plMt *,_ * : *access traiillng. This *

J:* wvfow.

<of. -***

• planning, the emergenc)!

-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.

Initial 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 mirllmum.

8-2 Millstone Station Emergency Plan Revision 53 April 2016 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 performance. 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. 82. l 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. s The site emergency alarms and emergency responder notification . . system;:; tests montl;ily. . . . , . ., .. _. . * ....... -.** ' . e

• Communications wiili *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 *RMrs 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.

8-3 Millstone Station Emergency Plan Revision 53 April2016

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-EP A-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 the unit technical requirements manuals. The Station Fire Marshall is responsible for the review and approval of all fire drill scenarios, in advance of their use. The Station Fire Marshall shall evaluate and take appropriate actions for observed fire drill discrepancies. The Station Fire Marshall shall also review and disposition, as necessary, comments from fire drill critiques.

b. Medical Emergency Drills The-Manager, Emergency lO:r:/son<lucting

_ .* o: ,. ' annual medical drills. ArrangeJ.Uents for and drills are . made -through the Lawrence and Memorial Hospital Middlesex Hospital Emergency Departinents,

• 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 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 conduded 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 53 April2016

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 plume exposure pathway EPZ. The level of participation shall be as follows: J:i 6 .

• The State of Connecticut shall fully participate in at least one 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 . . mam exercise.

8-5 Millstone Station Emergency Plan Revision 53 April2016 ._ .. ,*_.

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 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 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 elements not properly d1:iriB.g previous exercise. . .. *< ,, g. Post-Exercise Critique An in-house, post-exercise critique will be conducted, An off-site post-exercise critique will be scheduled at the conclusion of each exercise by FEMA to allow offidal 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. 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. 8-6 Millstone Station Emergency Plan . Revision 53 April2016

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 CPR 50.54(Q) Change Evaluation, for 10 CPR 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 CPR 50.54(q). Evacuation time (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 I 0 CPR 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, te$thrg, <::q;?iipmenr;; 2111 -.:rvaluation.r cf the adequacy.

Of interfaces with state and loca1 g0ve1m'1.trmt and the of dfills and exercises.

The , .. reviewer completes a written report fb&tdetailS" 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 fmdings. 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. 8-7 Millstone Station Emergency Plan Revision 53 April2016 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 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 media with emergency plans, information concerning radiation, and points of contact for release of public information in an emergency. Am::-,dia manual, developed t,.0 meet the ni;;;cds of

media, in.J:110.1&.fon ai1d general information coaceming

• planning, nuclear power* and -. :radiation.

The manual is distributed to the local media v:nd is available for issue at* the Joint Media Center at the time of an emergency. 8-8 Millstone Station Emergency Plan Revision 53 April2016

9. Recovery 9. I 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. Recovery actions are described in emergency plan procedures. 9 .2 Recovery Organization The ORO is in Figure 9-1. 9 .2.1 Site Vice President -.Millstone The Site Vice President -Millstone is responsible for coordinating the station ..... :"*'"**** ... , ...

9.2.2 Director

of Recovery

• .. , .. _. The Director of Recovery Operations (DRO) is responsible for overall direction of recovery operations and reports to the Site Vice

-Millstone. The Director of Recovery Operations (DRO), as well, as those managers reporting directly to him, are chosen by station mari.agement. They possess competep.t 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 co1lecting, retaining, and retrieving data.
• Providing post accident data analysis timeline for the accident.

9-1 Millstone Station Emergency Plan Revision 53 April2016

• 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 sUi.tion support staff during the recovery operation.
• Maintaining an effective station security program.
• Implementing maintenance and repair operations with station staff.
• 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 Ell .Assisting. the fi't'iYJ* DEEP' .. off..:site-*recpvery .. *phase***:\ . .-*.

• v*. sampling, survey .tneasuremer-.tts*

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 proviqing 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.
• Developmg decontamination plans.
• Assisting the State DEEP in determining total integrated population doses by using various inputs. 9-2 Millstone Station Emergency Plan Revision 53 April2016

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.

e general administrative support. e Scheduling and expediting recove1y operations.

• Assisting the DRO in planning activities.
• Coordination of recovery staff meetings.

c, TG;hl>latmg, expediting and closbg out commitment lists in su5f)p0rt 0£ 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.

9-3 Millstone Station Emergency Plan Revision 53 April2016 I Manager, Technical Support *System Analysis *Core Physics *Data Reductions (Post-Accident . Analysis Data) Licensing

• NRC/state licensing I Manager, Plant Operations
• Affected unit staff plus other station staff as applicable 9-4 Figmre 9-1 Recovery' Organization Site Vice President -Millstone I Director of Recovery Operations I I Manager,
• Radiation Centro!

.. *Waste Design *.\

• f >: --*ALARA
• Waste
• . ,S¥;J;!(i;:'YUre Evaluations
  • * "i.
• Specialized

'

• Dosimetry

, ;. *Field Su rve'y an<l Environ mental Sam pie Teams *Off-site and On-site surveys, sampling for recovery/reeqhy . decision maki;ng.

L

' . *'* 1-----1 Advisory Support I Manager, Engineering

• Engineering
• Vendors *AIE *NSSS *Resources
• Construction
• Purchasing
• *Legal
• Insurance
• Project Management
• Schedules
• Cost Control Millstone Station Emergency Plan * . Revisfon 53 . * * :*,. April f016 Millstone Station Representatives in the State EOG and Joint Media Center *Millstone Liaison with the state EOC and official media spokesperson.
• Support State response to FEMA questions*.
• Support local responses to questions and evaluate needs.

Appendix.A APPENDIX A DEFINITIONS, ABBREVIATIONS AND ACRONYMS A-1 Millstone Station Emergency Plan Revision 53 April2016 Appendix A This section provides definitions of commonly used terms that are applicable to this Emergency Plan. ' DEFINITIONS Absorbed Dose The quantify 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 meastires. Corrective Actions Those emergency measures taken to improve or terminate an emergency situation. Actions taken as a result of reaching an Errrergertcy* 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. A-2 Millstone Station Emergency Plan Revision 53 April2016 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 (RCA) An area of the Station where dosimetry is required. 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. Monitoring: Station The Unit 1 facility from which indications and a1mms 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 ari 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. Contamination (Radioactive) The deposition of radioactive material in any place where it is unwanted (e.g., on persons, products or equipment). A-3 Millstone Station Emergency Plan Revision 53 April2016 Appendix A 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. The unit of radioactivity which is equivalent to 3. 7 x

• 10 10 disintegrations per second; millicurie (mCi) = one-thousandth curie; microcurie

(µCi) = one-millionth curie; picocurie (pCi) = millionth micrpcurie. 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. Thresholds for _initiating aotil611ri !tu.ch as d:esignathig ,lJ:Particular class of emergency,.

• . * ( ..... --*.* . :illitiating 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, BRA VO/ ALPHA) Emergency Operations Facility (EOF) A facility located 15 miles north of Millstone from which station activities related to an emergency will be carried out and from which information will be provided to the corporate, federal, state officials and focal community chief executive officers.
• A-4 Millstone Station Emergency Plan Revision 53 April2016 Appendix A 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 ill internal exposure. Ingestion Exposure Pathway The-pathway by which could-b& ". contaminated water or as milk or. whlch 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 hours of SERO activation. Personnel assigned to fill these positions are drawn from a pool of qualified individuals .. 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 no_t 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). A-5 Millstone Station Emergency Plan Revision 53 April2016 Appendix A 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 OSFSD 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 Personne.l assigned to :fulfill a specific SERO position and who report to the station in accordance with Table 5-1. . . :.. .-1 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. Operational Support Center (OSQ 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 .. A-6 Millstone Station Emergency Plan Revision 53 April2016 Appendix A Procedures Emergency Operating Procedures (EOP) Procedures which provide specific actions to mitigate the consequences of and terminate an emergency situation. Emergency Plan Implementing Procedures (EPls) 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 Projected Dose The estimated potential* dose that could be received by affected individuals if no

• protective actions are taken. Protective Action Guides (PAGs) Prqjected absorbed dose to individuals in the general population which warrants protective

' . . , . . M.;ct:ion, ... -:' .... * ...... * ***' : ' 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 ele'ctrically charged ion pairs directly or indirectly in its passage through the medium.

• 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. .A-7 . Millstone Station Emergency Plan Revision 53 Apri12016 / Appendix A Station Emergency Response Organization The organization responsible for station operations under emergency conditions. The State of Connecticut. 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 in the Control Ro9in (or reported to : ..

l. 1 ) h .

• 1 ,. ., ' ... .. -. ;, . ,;, " , L .. 1 . th" . I . .. . . . . . . . .

.. ,.,:. tue Centro Room t at 1s -r ie t.1.zesimKr. a ):(ID1f-"* il74t p.i:ai;;es* ifiP ant. m a* grv.e:Q: ... /';., .. ";:::n emergency classification. A }a,e aH -UJ;Ztrt.mttt.nt tt:imii1'.lg, equipment status fodiCaior., ci. .*. 1" measurable parameter (on-site or ), a discrete observable event, or the results of Technical Support Center (TSC) A center located where technical support personnel monitor station conditions and provide data interpretation. A-8 Millstone Station Emergency Plan Revision 53 April2016 Appendix A ABBREVIATIONS AND ACRONYMS ADTS ALARA AMRDA AMT ARMS ARPS BWR CBETS CCorCM 3 CEDE CES CFH CDE CFR Ci CMS co CONVEX CPM CR CRDC CRDSEO CT CTNG CTS DEMHS DEEP DRS DSEO DOE DOT dpm/100 cm 2 DRO EAL EAS EC ECCS EDAN EIS ENRS ENS Assistant Director Technical Support As Low As Reasonably Achievable Assistant Manager Radiological Dose Assessment Accident Management Team Area Radiation Monitoring System Assistant Radiation Protection Supervisor Boiling Water Reactor Computer Based ExposureTracking System Cubic Centimeter Committed Effective Dose Equivalent Corporate Executive Spokesperson Certified Fuel Handler Committed Dose Equivalent Code of Federal Regulations Curie (Unit of Radioactivity) Central Monitoring Station . Control Operator Connecticut Valley Exchange Counts per minute Control Room ..

• . ... Conti:o} Roam Direetor.

of Station Emergency Operations Connecticut Connecticut National Guard Chief Technical Spokesperson Division of Emergency Management and Homeland Security Department of Energy and Environmental Protection Department of Health Services (formerly DREW) Director of Station Emergency Operations U.S. Department of Energy Department of Transportation Disintegrations per minute per 100 square centimeter area Director of Recovery Operations Emergency Action Level Emergency Alert System Emergency Communicator Emergency Core Cooling System Environmental Data Acquisition Network Emergency Information Specialist Emergency Notification and Response System NRC Emergency Notification System telephone A-9 Millstone Station Emergency Plan Revision 53 April2016 EOC EOP EOF EPA EPAP EPC EPI EPZ ERF ETS FDA FEMA FSRC FTDC GM gpd gpm HAB HP HPN HVAC iCSC INPO IPZ ISFSI JMC KI LCO LOCA MA MAX MCL MCRO Met MOC MOR MOS MPC Appendix A Emergency Operations Center (State, local, or Site) Emergency Operating Procedure Emergency Operations Facility Environmental Protection Agency Emergency Plan Administrative Procedure Emergency Planning Coordinator Emergency Plan Implementing Procedure Emergency Planning Zone Emergency Response Facility Environmental Technical Specification . Food and Drug Administration Federal Emergency Management Agency .

• FacilitY Safety Review Committee Field Team Data Coordmator Geiger-Mueller detector Gallons per day Gallon per minute Hostile Action Based Health Physics NRC Health Physics Network Telephone Heating Ventilation and Air Conditioning System .. . .:.*r:-:::.

';*:. **'. / . .l--. :*. "" , ** *1c.rl1'*.,,,,.

• * *W l,>:.JV . " . . Inilsbrook:'Corporate Support Center Institute of Nuclear Power Operations Ingestion Pathway Zone Independent Spent Fuel Storage Installation Joint Media Center Potassium Iodide Limiting condition for operation Loss of coolant accident Massachusetts Maximum Media Center Liaison Manager of Control Room Operations " Meteorological Manager of Communications Manager of Resources Manager of Security Maximum permissible concentration A-10 Millstone Station Emergency Plan Revision 53 April2016 MPS MRCA MRDA mRern/hr *MSRC MTSC NAP NFSA NG NRC NNM NY OFIS OMF ORO osc OS CAA PA PAO PAR PAT ' . *PEO PF PIO PWR Q QA R rad RAE RCA RCP RCS REM RERP RHR RIEMA RL RMS RMT RO RP Appendix A Millstone Power Station Manager of Radiological Consequence Assessment Matl3:ger of Radiological Dose Assessment 1/1000 Rem per hour Management Safety Review Committee Manager of Technical Support Center North Access Point Nuclear Fueland Safety AnalysiS (formerly RES) National.Guard,.

U.S. Nuclear Regulatory Commission Nuclear News Manager New York Off-site Facilities Information System Offsite Monitoring Facility-EOF Organization for Recovery Operations Operational Support Center Operational Support Center Assembly Area Public address system Protective Action Guide Protective Action Recommendation Plant Access Training Plf"int

• .

factor*.* Public Infmmation Office;;: Pressurized water reactor Reiease rate Quality Assurance ,' Roentgen. A unit of radiation exposure Unit of.radiation dose Radiological Assessment Engineer Radiological Control Area Reactor Coolant Pump Reactor Coolant System Unit of radiation dose Radiological Emergency Response Plan Residual Heat Removal Rhode Island Emergency Management Agency Regulatory Liaison Radiation Monitoring System Radiological Monitoring Team Reactor Operator Radio Pager \ ... ;** A-11 Millstone Station Emergency Plan Revision 53 April20i6 RMP RWP SAP .scBA SDO SEOC SERO SIS SRO SM SPDS STA State TA TEDE TIC TLD. TSC TSCEE TSCSM us USCG u µCi X (chi) X/Q Appendix A Radiation Protection Manual Radiation Work Permit South Access Point Self-contained breathing apparatus Station Duty Officer State Emergency Operations Center Station Emergency Response Organization Safety injection system Senior Reactor Operator Shift Manager Safety Parameter Display System Shift Technical Advisor State of Connecticut Technical Assistant Total Effective Dose Equivalent Technical Information Coordinator Thermoluminescent Dosimeter Technical Support Center Technical Support Center Electrical Engineer Technical Support Center Shift Manager Unit Supervisor .. Gua.sd -vVindspeed "Mitrocuries

• Concentration Relative Concentration A-12 Millstone Station Emergency Plan Revision 53 April2016 AppendixB APPENDIXB LETTERS OF AGREEMENT B-1 Millstone Station Emergency Plan Revision 53 April2016 AppendixB Page Organization B-3 Amtrak B-4 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 Public Safety-Division of State Police B-10 Teledyne Brown Engineering B-13 Town of Waterford Ambulance Service B-14 Town of Waterford Fire Service B-15 Town of Waterford Police Department B-16 Accu Weather I B-17 GEL B-18 Norwich Fire Depmt.m0xrt
• .. . ' -. -**-.. . ..-1 ....

... ... , ,*.-. .. *-.-;._' . ' *-B-19 Salem Volunteer Htit

• ,, , .. .. .. ,. .. . .

.* ,.,, ..... *-*.,. Note: The letters of agreement are reviewed annually and verified to be current. Only letters with significant changes require reissue. B-2 Millstone Station Emergency Plan Revision 53 April2016 4:29PM HP Fax November 17, 2015 Mr. John Daugherty Site Vice President Dominion Nuclear Connecticut Rope Ferry Road Waterford, CT 06385

Dear Mr. Daugherty:

AppendixB . . . . '

• I page 1 This letter ls to confirm that the National Railroad Passenger Corporation will, when requested respond* in the event of an emergency at the Millstone Power Station on Long Island Sound, in the following areas: Implementation Criteria/Authorities.

Responsibilities 7;Jw i.'lll)" understanding that, In the eve;nt of ::,n .. t\co>}

• Site Emergency Operations may rnquost otif'*at."Si::.t&r.t.:e.

A<>sistc;r:cz

• should be rnquestad by calling the Chief Train Dispatcher of the a .. ,s.to;; Cl.ITC Office at 61/345-**

7474. Indicate the nature of the incident, the location, and the type of assistance required. Measures to be Provided/Limits of Actions Our commitment for assistance is to direct train traffic away from any areas that may be affected by the emergency. Information Exchange /Point of Contact at Site Verification communications to the nuclear facility will be by telephone to the Director of Site Emergency Operations al Bf}0/892-5600. Information exchange can be by using the Chief Tran Dispatcher's number.

• Training and Dfills Please notify us of your plant drills so that we may have the opportunity to observe your emergency response actions and meet your emergency operations personnel.

Please coordinate by contacting my offiee at 617/345-7406.

• • .'..** B-3 Millstone Station Emergency.Plan Revision 53 April2016 AppendixB l-Nov 19 2015 4:29PM HP Fax page 2 NATIONAL RAILROAD PASSENGER CORPORATION Mr. John Daugherty November 17, 2015 Page Two Two South Station, 5th Floor, Boston, MA 02110 AMTRAK This letter of agreement shall remain in effect until cancellation by either party, provided on ninety (90) days prior written notice, and shall be reviewed and certified as needed. Sincerely, . Fe{E' Deputy General Manager Northeast SubDivision Cc: P. O'Mara, Amtrak Superintendent

-Operations W. B. Moore, Deputy Chief -Amtrak Police S. Pugs le)!, Amtr::'l!<

• .. Davra. [..;qi-n
• B-3a I..'*. Millstone Station Emergency Plan Revision 53 April2016 AppendixB LETTER OF AGREEMENT BIETWEEN ELECTRIC BOAT CORPORATION AND DOMINION NUCLEAR CONNECTICUT RADIOLOGICAL ASSISTANCE Enclosure (1) to 438-37497 Page 1 of2 It is understood that the Electric Boat Corporation will, upon request, respond with personnel and equipment In the event of an emergency et the Miiistone 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 Radlologlcal 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 s/iipyard Security is *contacted, request that RAD CON Management be notified. for assistance includes. provldi!Jg r<!diologicc;Leoritrcl pereonnel and .eqvipment 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). B-4 Millstone Station Emergency Plan Revision 53 April2016 AppendixB Enclosure (1) to 438-37497 Page2 of2 It Is understood that should the Electric Boat shipyard be affected by a radioactive release from another facility, Electric Boat resources wlll 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 <<:1xchange can be provided by using the same telephone number. It is understood that Miiistone Station wlll train representatives of Electric Boat Corporation's Radiologlcal Training Section annually on the use of Station equipment and procedures. These Radlologlcal Training Section Individuals, in tum, will train selected Electric Boat Corporation personnel on this equipment and procedures. It is understood that this training wlll 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 effect until cancellation by either party, provided on ninety<90) . wrltt.en and shall bo rc*.rieVH3d e.:f, Dominion Nuclear i::Onnectlcut By: / , -:'ffejz4;/JU&& Jk-Name: J. Alan Prjce B-4a . Electric Boat CorporaUori . L2;n<5Z1* M. Toner President Millstone Station Emergency Plan Revision 53 April2016 AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 Nuciear Power Plant Emergency Response Assistance Agreement This Nuclear Power Plant Emergency Response Assistance Agreement (hereinafter "Agreement") has been entered into by and among lNPO and electric utilities that have responsibility for tlie construction or operation of commercial nuclear power plants under a license issued by the U.S. Nuclear Regulatory Commission pursuant to Title 10 of the Code of Federal Regulations (hereinafter "nuclear power plants") and that have subscnbed counterpart signature pages in the form attached hereto (hereinafter "Parties"). 'nte 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 a:p.d obligations that will be incurred.in -responding to r'.!qp.ests for A. "C.oordil:].ation on Sharing Emergency Infon11ation N&. Vtilities" *

• describes the responsibilities and expected NOW, THEREFORE, agreed, that: 1. Assistance rendered by a Party as described hereunder

µiaybe 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 tet:II1$ and conditions herein. 2. The Party that requests assistance shall be known as the "Requesting Company and the Party :furnishing assistance 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 efilail, fax, or phone request (followed with documentation) in emergency circumstances that lists the requested, offered and. agreed upo:µ. Assistance, that references this Agreement, and that is agreed to by both the Requesting and Responding Parties. 1 B-5 Millstone Station Emergency Plan Revision 53 April2016 AppendixB AGREEMENrBETWEENPARTIES November 8, 2013 5. (a) 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 01* the :furnishing of assistance pursuant to this Agreement.

Requesting Company shall notify Responding when its assistance is no longer needed. (b) The :furnishing of assistance hereunder shall be deemed to have commenced when persorinel 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) , - .. aLh1rrangemi;;nt.Bf{{<i* transportatiQit of itS _f:i.:om an.ct to their working baf).e 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 Respondllig Company shall be those of the Re8ponding 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 .. *. B-5a Millstone Station Emergency Plan Revision 53 April2016 AppendixB. AGREEMENT BETWEEN PARTIES November 8, 2013 7. (a) Responding Company shall furnish the requested personnel and equipnieilt to the extent that the Responding Company may determine to do so in its sole judgment and discretioIL (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 known to, or readily ascertainable by, the public without fault or omission of either party or its employees or agents; or (2) was already known 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) vvas

• r,;;;; E**n4 *$.\ther directJy, os indirectly, ac(.'est.tl'.'.

t'l'.it\tow!a:dg<: of other party. .,.,, ** .. ,, . ._, .. :. (c) Responding Compi,i.ny 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 worltjng 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 hours in advance to Requesting Company of the permanent withdrawal of personnel or equipment

furnished.

Responding Company's withdrawal of personnel or equipn;ient shall not affect any obligations which . may bave 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 fumishirig of assistance to the Requesting Company, which statement shall be paid by Requesting Company within thirty (30) days after receipt. 3 B-5b Millstone Station Emergency Plan. Revision 53 April2016

• Appendix.B AGREEMENT BETWEEN PARTIES November 8, f013 9. The Requesting Company shall reimburse Responding Company for all direct and indirect costs and expenses, not including a profit, incurred by Responding Company in giving assistance pursuant to this Agreement, including but not limited to costs and expen8es related to or resulting from compliance with governmental requirements such as Title 10 of1he Code ofFederal Regulations Part 20. Such costs and ex.penses shall be computed in accordance wi1h Responding Company's standard rates and accounting practices, including such overheads as are detennined by Responding Company to be applicable to such direet 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 1 O(b) hereof: Requesting Company shall indemnify and hol9. 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 fro:m fumishlng 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 byR:0sponding Company or its insurers to Responding
• oi:'" . -*' ,,_ -*._._.,.,,,

Company's officers, directors, or employees or their benefiCiaries for bodily injuzy 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 descnoed in this paragraph l O(b) which such insurer may make on behalf of Responding Company because of Responding Company's fumis-hing of assistance pursuant to this Agreement. 4 B-5c Millstone Station Emergency Plan Revision 53 April 2016 AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 ' Responding Company makes no warranty with respect to any goods or seJAT:ices provided to Requesting Company and NOW ARRANTY, EITHER EXPRESS OR IMPLIED, ORAL OR WRITTEN, SHALL APPLY TO THE GOODS OR SERVICES PROVIDED, INCLUDING, WITHOUT LIMITATION, THE WARRANTIES OF . MERCHANT ABILITY AND OF FITNESS FOR SPECIFIED OR lNTENDED PURPOSE. All equipment and services furnished by Responding Company pursuant to

• this Agreement are furnished as is. (d) Jn the event any claim or demand is made or suit, action, or proceeding is filed against Respondmg 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 iii its sole discretion deems necessary or prudent Responding Company shall cooperate with Requesting Company in the resolution ofany such matter. If a Reqoesting Company settles a liability suit with a 3rd party that involves a Responding Company, Requesting Company will eµsure the Responding Compnay is released from liability.

' (e) Each Party to this Agreement agrees to carry the amount of :financial proteetion required by the Atomic Energy Act of 1954, as amended, and self-insurance or comprehensive liability insurauce, including in'Jemnification: and defense obligations set forth herein, sub,1ect;to $;'..:tcli1cypen and-amounts of self-* insurance, retentions, or deductibles as 2.re con."listentwithstandard business practice in-** * *

• the industry. (t) Jn the event a Responding Company provides assistance pursuant to this Agreement through an affiliate or subsidiary, the indemnification provided in this 10 to the officers, directors, and employees of that Responding Company shall apply with equal
• force to the officers, directors, and employees of that aftiliate or subsidiary.

11. Each Party shall provide the Institute ofNuclear Power Operations (hereinafter "INPO") with an executed counterpart 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 B-5d Millstone Station Emergency Plan Revision 53 April 2016 . . ' -. -,.

AppendixB AGREEMENT BETWEEN PARTIES November 8,,2013 12. (a) INPO may provide certain administrative and emergency response support services in furtherance of this Agreement, such as maintaillin.g and distributing to the Parties a roster of the signatories to this Agreement; providing copies of the Agreement and any amendments thereto to all Parties; and preparing and disttibuting to the Parties other documents, such as a list of sources of emergency manpower and equipment. lNPO may provide such other services as may be requested of INPO from time to time by the Parties. The Parties recognize that JNPO shall not be responsible for implementing, enforcing, or interpreting this Agreement. (b) The Parties shall defend, indemnify, and hold harmless 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 ofINPO'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 JNPO, its officers, directors, or employees arising out of its or their performance of INPO's functions described in paragraphs 12( a) and l2(c). (c) Following an emergency at a nuclear power plant the Requesting Company may contact INPO for help in locating and coordinating delivery ofrequested 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 ... -:; ff:.i.:e .. .:tillg'

latfie*S'**.,:. (Responcling Cirrop@lic3J ihr assistance.

hl ca6e file Assistance Agreements will be csmblishd hetweer.. fol* Company mid Responding Companies. (d) If INPO furnishes assistance and unless otherwise agreed by INPO and the Requesting Company, the Requesting Company and INPO 11hall have the same rigl1ts and obligations as ifINPO were a Responding Company (including but not limited to the Requesting Company's ob1igations to INPO, its officers, directors, and employees under paragraph 10 hereof), except that paragraphs 8 and 9 and 10( e) shall not apply to INP.O. 13. This Agreement will.not create any rights or defenses in of any entity or person not a signatory to this Agreement-except to the extent provided in this paragraph and in paragraphs IO and 12 of this Agreement. This agreement shall be binning upon and inure to the benefit of each signatory to this Agreement and the subsidiaries and affiliates of each such signatory. 6 * .... **. B-5e Millstone Station Emergency Plan Revision 53 April2016 "**** : i* . \. i AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 14. Except as otherwise provided in paragraph 15, any Party may withdraw from this Agreeinent 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 arise out of events occurring prior. to the date. No Party may withdraw from this Agreement while it is receivillg 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 bi:iiding upon all Parties thirty (30) days after INPO has received signature pages for the amendment executed by at least a majority of the Parties to the Agreement.

JNPO 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. Notwithstanrung the first sentence of paragraph 14, any Party may withdraw from this Agreement by submitting written notice to INPO 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 0perated on Qf .l!. Party, or an event associated with transportation of nuclear Party; (jj) assistance is issueffto.,.,,_,

to :illch-emergen.cy; and (iii) such assistance is provided, this Agreemcilf stall he 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 B-5f Millstone Station Emergency Plan Revision 53 April2016 AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 EXHIBIT COUNTERPART SIGNATURE PAGE The undersigned comp(llly hereby agrees to become a Party to the Nuclear Power Plant Emergency Response Assistance Agreement and its attachments. Company "))QM V" ()..; Printed Name: J::>ev \.D /\, \-h-.""YX CD cq;; (Corporate OJ;ficer Signature) 8 B-5g Millstone Station Emergency Plan Revision 53 April2016 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 infonnaticin regarding emergencies at nuclear power stations and to maxhnize their assistance roles to their utility members and the industry, the Electric Power Research Institute (EPRI), the 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 purpose 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: I. 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 inforination regarding the emergency.
• NEI will develop and issue, in coordination with the affected utility, appropriate pµblic st_atements to the news media, as necessary.

ci. :r.:IBI-will associated press releases'-to its ., ::nembers and other fr:i<l,:r;.sl.rJ

• • *:ix
• 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.

• JNPO 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 B-5h Millstone Station Emergency Plan Revision 53
• April2016 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 own databases.

• INPO will maintain information on industry assistance capabilities including:

o Personnel with specialized plant or emergency response knowledge o 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 lNPO 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 B-5i Millstone Station Emergency Plan Revision 53 April 2016 ;: ,_ ... -,*. AppendixB AGREEMENT BETWEEN PARTIES November 8, 2013 EXHIBIT 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 January 3, 2014 Company Institute ofNuclear Power Operations By C:. -(Corporate Officer Signature) Printed Name: William E. Webster, Executive Vice President B-5j Millstone Station Emergency Plan Revision 53 April2016 LAWRENCE +MEMORIAL November 23, 20i5 AppendixB BRUCE D. CUMMINGS President & Chief Exe cut Ive Ofiicer John Daugherty, Station Vice President Dominion Nuclear Connect.icut Inc. PO Box128 Waterford, CT 06385.

Dear Mr. Daugherty,

ema.ih bcummlngslmhosp.org 365 Montmrk Avenue I New LondQn, CT 06320 860.442.0711, Ext. 4645 I FAX 860.271.4474 This lett;er* is :to confirm that + Memorial Hospital will respond in the eve qt of a radiological emergency at.Millstone Power Station. Implementation Criteria (Authorities. Responsibilities [tis our understanding that in the event otan emergency, the nuclear facility may request medical assistqnce. The Hospital EmergencyDepartment is to be contacted at calling (860)442-0711 ext. 2261 and requesting to speak to Emergency Department Charge Nurse to acti.vate om: 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 inc 1;:u:t!*1d a

mr

who are *ne*:d r;f medical treatment at Lawr2ncc.+

Ho.qJit?.l, . 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, _.,..-*'_.' <-* 'Bruce 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 *

• Gregory M. Olexy, Emergency Preparedness Specialist,.., Dominion Nuclear Connecticut, Inc.
• D. Smith, Emergency Planning Service ,.., Dominion Nuclear Connecticut, Inc. B-6 Millstone Station Emergency Plan Revision 53 April2016 AppendixB ADMINISTRATION November 19, 2015 Mr. John Daugherty Vice President

& Senior Nuclear Executive Dominion Nuclear Com1ecticut, Jnc. Millstone Power Station Rope Ferry Road Waterford, CT 06385

Dear Mr. Daugherty:

HOSPITAL 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 suppmt for Lawre11ce and Memorial Hospital, acting as the secondary medical treatment facility fo1* the Millstone Station, Any expenses incurred as a result of providing these services will be the l'esponsibility of Millstone Power Station. In case of an emergency situation, we would follow the plan for "Decontamination and Treatment of the Radioactively Contaminated Patient at Middlesex Hospital," currently in effect between om* institution . m1c' tlm TiciEll.y If you iiave ::my qtlci*tlnns coi1cei11ing om* for contaminated patients, please cont&ct i.r;.;* Gary vican Vice President Strategic Planning & Ambulatory Operations GH:aac c: David A. .smith, Manager, Preparedness, Millstone A member of the Middlesex Health System 28 Crescent Street Midclletown, Connecticut 06457-3650 tel 860 344-6000 fax 860 346-5485 ';_'. '* *.' B-7 Millstone Station Emergency Plan Revision 53 April2016 AppendixB SHIPMAN'S FIRE EQUIPMENT CO., INC. 172 CROSS ROAD WATERFORD, CONNECTICUT 06385-0257 (860) 442-0676 .December 6, 2010 Mi:. Skip Jordan Site Vice President Dominion Nuclear Connecticut Millstone Station Rope Ferry Road Waterford, CT .06385 .Dear Mr. Jordan: This letter is to con:.fum that Sb,ipman's Fire Equipment Co., will, when requested, respond in the event of an emergency at the Millstone Power Station, in the following areas: Implementation Criteria/ Authorities, Res,ponsibilities It is our understanding that, in the of an .emergency, the nuclear facility Director of Site Emergency Operations may request services to assist in the emergency effort. Assistance should be requested by calling 860-442-0678:.611. Measures to be Provided/Limits of Actions for in t,Jw e::irent of an

• Power.
• Infonn.nifo:ti Exchange/Point of Contact at Site *Verification communications to the nuclear facility will be by telephone to the Director of Site Emergency Operations.

The telephone.number is unlisted. Infonnation exchange can be provided.by usirig the same telephone number. Training and Drills Since our a8sistance is limited to providing equipment and service, we feel that we do not need to participate in your training drills, However, we would appreciate being invited to your plant drills to Observe your emergency response actions, and to meet your emergency

• 'This letter of agreement shall remain in effect until cancellation by either party, provided on ninety (90) days prior written notice, and shall be reviewed and certified as needed. President cc: David A. Smith. Emergency Preparedness Planning Services Department, Millstone FIRE & SAFETY EQUIPMENT'

... ,; "

• ... -; .. , r .'-'"*r "t.* . '1.' * * . FAX (860) 444-7395 www.shipmans.com Email lnfo@shipniatis.com B-8 Millstone Station Emergency Plan Revision 53 April2016

.. ,; .t. AppendixB STATE OF CONNECTICUT DEPARTMENT OF EMERGENCY SERVICES & PUBLIC PROTECTION O"FACE 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:

Th.is lettP-r. is ta r.or;ifirm that personnel and equipment from the Depart.ment of Emp.rgency .... yvheri requested, respond in the event

i.£.: the Mi11$:0n'e

• *
• This response is submitted in accordance with the State of Connecticut Radiological Emergency Response Plan. Sincerely, \

.. A...-.. .. D COMMISSIONER cc: William P. Shea, Deputy Commissioner* Col. Brian Meravlglla, Deputy Commissioner 111 L Country Club .Road Middletown, CT 06457 Phone: (860) 685-8000 I Fax: {860) 685-8354 .Jl.n .'Affirmative .:Action/'Equa(Oyyortunity '.Emy(oyer B-9 Millstone Station Emergency Plan Revision 53 April2016 AppendixB November 5, 2014 Mr. Stephen E. Scace Site Vice president Millstone Power Station Dominion Nuclear CT PO Box 128 Rope Ferry Road Waterford, CT 06385 2508 Quality Lane Knoxville, TN 37931 865 690-6819

Reference:

Emergency Services Letter of Agreement D.ear Mr. Scace, This letter serves as our Letter of Agreen:ient to provide assistance in the event of an emergency. We have 16 gamma detectors and 40 gross alpha/beta proportional counters which are used for gross alpha/beta, 1-131 and Sr-89 and Sr-90 counting. During an accident 'v'."e could dedicate a large portion of these detectors to provide fast turnaround analysis. Table 1 lists the types of analyses; number of each analysis which can be performed on a one-day, two-day or three-day b!'lsis; sample and detection Table 2 liSl!:s typi!::a! .. ,

• We could be contacted at any time in the l'Nti;it*of an emergency.

The !Q;ecfpe!'Solis ahd telephone numbers can be called in the order listed:* Teledyne Brown Engineering Keith Jeter Marty Webb Rebecca Charles (8Q5) 690-6819 (865) 934-0373, (865) 621-9118 (cell) (865) 934-0375, (865) 776-0573 {cell) (865) 934-0379, (865) 924-6041 (cell) This agreement letter shall remain in effect until cancellation by either party, provided on a ninety (90) days prior written notice, and shall be reviewed and certified as needed. If you need additional Information, you may contact me at the above numller. Sincerely K;ik rrot Keith Jeter Operations Manager Enclosure B-10 Millstone Station Emergency Plan Revision 53 April2016 .. -:.. AppendixB BROWN ENBINEERING, INC * .AToTodyrta Tablel Emergency Analytical Services Days for Analysis Matrix Analysis Gamma.scan 1-131 in Charcoal 1 Milk, Water 1 Other 1 Tritium Water 1 1-131 Miik, Water 3 vegetation 3 Gross Beta Air Particulate 1 Total Strontium Milk, Water 2

• Based on a volume of200 Cubic Meters B-11 Detection Level .04 pCi/Cu.M"' (Cs-137) 5 pCi/L (Cs-137) .05 200pCi/L 1.0 pCl/L .05 pCi/g .01 pO/Cu.M* 1.0 pCi/L Quantity 20 20 30 20 80 20 ...... :. "" -:-*-.. .. *:--*---"'" 'l .-.1 __
• Millstone Station Emergency Plan Revision 53 April 2016 AppendixB Emergency Analytical Services Table2 Analysis Medium Gamma WaterorMUk 41lters Milk 4 liters Soil SOD grams veaetation 500grams Tritium Water 100ml 1*131 Milk 4 llters Ve!le!ation 500!lrams Gross Beta. Air particulate As sampled Water 1 liter Soll 50 grams Total Strontium Water or Milk 1 liter If the above volumes are not available, samples can be run at lower volumes. Detection levels may be elevated or turnaround times increased with reduced sample volumes. ' B-12 Millstone Station Emergency Plan Revision 53 April 2016 I. AppendixB
• . .

Arnhulanc.e Servke, lnco:rponded , 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 wi.*.h Waterford Fire Service and with the Waterford Police Department in accordance with standad ,;, ; Information h\":c'.rng'!/Poin1s of Verification of communication to the site may be by telephone to the Control Room or emergency operatibns Training and Drills We would appreciate and welcome notificalion of the plant drills or addilional training which you feel would be advantageous to us. Please do not hesitate to contact me should you have any question or concerns Sincerely, Steueu'D. President, Waterford Ambulance Service Coples distributed David Smith, Manager, Miiistone Emergency Preparedness Department Daniel Steward, First Selectman, Town of Waterford U. Stephan Bellas, Waterford Police Department/ Emergency Management Director 204 lluslon l'osl 1{011<1, l),O. Uox 137, Wnte1:fol'd 06385 B-13 Millstone Station Emergency Plan Revision 53 April2016 ,,- AppendixB August 6, 2015 Mr. Jolin Dougherty Millstone Power Station Dominion Nuclear Connecticut Rope Ferry Road Waterford CT 06385 Dear Mr. Daugherty Thi$ letter i$ lo con!irn1 that personnel end equipment for the Waterford !'Ire service will, whe11 requested, respond in the event of an emergency at Millstone !lower Station. Implcmcntalion Criteria/Authorities. Responsibilities It is our understanding that, in tho event of au emergency, the Millstone SWft Manager//Jircctor of Slallon Emergency Operations I d<isignco may request pcrsom1cl and equipment to lmndlo the omctgcncy. Assistance sho11I1l be rcquoslccl by calling the Waterford E11iergcncyCom1miniealions Center (91 J), or by other 111eans that 11111y be provided. Aclions 0111* commitment for osslsronce is to 1*espo11d to the best of our ability with perso11nel and equipment ht the event of a tire emergency or a rescue at Miiistone Power Statlo11 Complex and attempt to control the sltuation with the resources that may be available. We will request tho assistance of regional amt sla\o assets as needed.* i:n Ibo event 11f a large s1:nle incident 01* host lie action based event, we will coordinate establishment l)f Incident Command with 1::1e '"O::i:<ot*. t;:..-,J)afrnei.1*, l'ei/Olt* ., s\;\>:; a:"i,:\.f< V.ss: .<g;

• Information ofContnct Veriflcntlo11 of co111111u11ic*111ion to the nuclear facility will be by telephone to the Control Room or Director of Station limergency Operntions/Designee.

Training and Drllls \Ve would appreciate advanced notification of the plant drills or additional lnlining which you feel would be advantageous to us. This notification should also Include any additional security requirements tl1iit are being implemented nt rho Millstone nuclear facility. This letter ofngrcemcnt shall remnin in effe1:t until cancelln1ion by either party, provided on 90 days prior to wrillen notice, and shall be reviewed nnd .eertlf1ed llS needed. Sincerely, .Bruce A. Miller Director of Fire Services co: Dnvld Smith, Mnnuget; Mll'8tone Emergency l?repnredness Depar1me111 Dmlicl Steward, First SelectlllM, Tow1\ of\Vnterford Lt. Stephan Bellos, Waterford Police Depattment/ l:lmcricncy Management Director President Sloven Garvh1, Waterford Ambulunce Service B-14 Millstone Station Emergency Plan Revision 53 April2016 Brett Mahoney Ch ie.f 01' Policu Sept em bcl' 14. '.1.0 I 5 Mr. John Dougherty AppendixB WATERFORD POLICE DEPARTMENT 41 AVERY LANE WATERFORD, CT 06385-2819 Dominion Nuclcm* CT, Millslone Power S!ation P. 0. Box 128 W11terford, CT 06385 .Deur Mr. Douglu:rly: (8l50) 442*9451 TEL bmahoncraP\VL\tcrfordct.org This feller is to confil*m Iha! personnel from tile Walcrforcl Polic;e Department sh11ll scrw us t'he primary inw e11lbrcement ngeney which, when requested, will respond lo !he Millstone Pllwer Station. ln the event of 1111 emergency; the Millstone Shill Mmiager/Dircctor of Station Emergency Operations I dcsignec mny request personnel and equipment from the.Wate1ford Police Ocpar1111cin1 by utilizing tht:' established hot lines wilhin the Wat.crford Emergency Con1111unication Center, calling lite Wnterford Emergcncy Communications Ccnter(9l l ), Of' by o!hcr means that may be pmvickcL The Wi1tcrfonl Police J)cparonent's commitment for assisiance to prc1vidc personnel and equipment may include, but not be limited fo, lrnlTic control, secul'ity and/or tactical assistm1.ce. Whcnnssistnocc inform::ticn wil:. be verified by tbe Waterford ()zp u!ilh:ing !i .. vcrill-;;Hion met ho;!, which be coi\duc(cd Ly the mnking Executive Ofliccr cm duly. ln m1 event sllch <!Sa ho:ililc nction based event !ho Waterford mny establish

• com111m1d, request regional.

stalt: mid federal assiswnce and be the initial Singing area tbr ineidcllls involving outside law c11force111cnl agencies. The Waterford Police Department shall be notified of all noteworthy plnnt drills or additional training that would b.e 11dvnntagcous lo law enforcement Tltis response is i11 accordance with criteria as set lh11h in the Fcdcml Rcgulutiom;, HJ CFR, l)m1 73.55, Rcqui1:eme1its for Physical Protection oFt.icenscc Activilics in Nuclear 1>owcr R<:nctors Against* Radiological Sabotogc" and 10 Cl'R. [>mt 37. *'Phyfiical Pmtcc(lon ofCategmy l and Category 2 Quantities or Radioactive Material." lli*cu Malioney Chief or Police cc: Dnvid Smith. Manugc1', Millstone Emergency Deparlmcllt Daniel Steward. First Selcc1111an, Town of Waterford Lt. Stcpheil Bellas. Waterford l'olice Dcpm1ment/ Emergency Mnimgcmcnt Director B-15 Millstone Station Emergency Plan Revision 53 April 2016 ***' . \ -. ' -, >.--... :. . -, *1." * . * -::\ '? d AccuWeather ENTERPRISE SOLUTIONS'* Dominion Nuclear Connect.icut Inc. Millstone Power Station Good Morning: AppendixB November 20, 2015 In accordance with the purchase order on file the service provided includes the following: Telephone consultation is available 24 hours a day 7 days per week with AccuWeather meteorologists as needed in accordance with the letter of statement. The service includes:

• Millstone site specific forecasts as needed during incidents, alerts, and emergencies at the Millstone Power Station. The forecasts will be delivered via Phone call to the station. *AccuWeather will provide Meteorological support for Drills and exercises at the Station. *AccuWeather will supply Meteorological support for Hurricanes severe weather and other significant events potentially effecting the Millstone Power Station.
• AccuWeather will participate in parodic weather forecast simulations with the Millstone environmental staff. The fee per consultation request is $450.00 per request: . We look forward t.o of continued-support wit\"1.t'1e.Millt?.fone Power Station ..

Lou Louis S Seidel Director Business Development AccuWeather Enterprise Solutions 814 2358608 3$5 Science Park Road, State College, PA 16803-2215 P 814.237.0309 f 814.238.1339 E salesClccuweather.c:om __ ...... B-16 Millstone Station Emergency Plan Revision 53 April2016 . . AppendixB I LalJoratoriesLLC I y '** ... a member of Tiie GEL Group 1rm Ni ti \:ha1!ir;tvn. f;G 29*\ 17 20,H) R!A"'!tJ Char iu;;i;JH. SC 2Mfl7 r r,.12.$!\!\.e1i'1 r November 16, 2015 Mr. John Daugherty Vice President Millstone Power Station Dominion Nuclear Connecticut PO Box 128 Waterford, er 06385 Re: Emergency Plan

Dear Mr. Daugherty:

GEL Laboratories, LLC (GEL) is providing this letter to Dominion as a commitment lo provide emergency response radiochemical analysis of environmental samples to assist your organization in the event of an emergency situation or emergency drill. Please note that in the event of an emergency, Dominion will gel.com* be responsible for the SWJ?le analysis costs as well as the sample disposal costs: * * ,*.;, .;, ,; . ?f'!;;<,;:db:.<

cqi

• restcd analysis will be established at the time servicec ;ir} * ,-* ** ;***'l*"*h;,::icf};

aad analysis will be based on GEL's Standard Operating stm1dard tem1s and conditions, which are enclosed, will apply to tbtr .. analysis as well.

• Should you have any questions or need additional information, please call me at 843-556-8171.

probl<!rn solvecl B-17 Anna K. Contract Manager Millstone Station Emergency Plan Revision 53 April2016 City of Norwich Fire Depl 10 North 'l'hames Norwich, Connoctiout 06360 December 1, 2010 Mr. Skip Jordan Site Vice President Millstone Power Station Dominion Nuclear CT

• Rope Ferry Rd. Wi:iterford, CT 06385

Dear Mr. Jordan:

AppendixB Kenneth J. &;!andariato Fire Chief (860) 892-6080 taX-"(866) 886-25?5 .. This letter is to oon:firm. that the Norwich Fire Dcparbnent will, to the best of its ability during a station emergency, fill breathing bottles brought to the Norwich Fire Deparbnent by Dominion Nuclear Connecticut upon telephone request by its Emergency Response Operations. . . *.\ * .. _.,. ....... : Tha Emergency Planning Se-iVices at Sfu.tfon iS .* ',", .. *.:.:. "".-*:*. ""':s;*'til:

.. questions to this agre<;'Jnen?. (Contact Tom .Dlfilibek at 860-440-4,21'3}

• **. * *. * ; ,-,;_,.. ** : :,.";.\i This agreement shall remain in effect until revised, as agreed upon by both parties, or cancelled by either party with 90 clays written notice. KJSljs cc: David A. Smith, Manager Emerg_em:y

Dept, B-18 Millstone Station Emergency Plan Revision 53 April2016

.. AppendixB SOleM. VOLUNTeeR FIRe co. INC. 424 H!lRTFORD ROllD SOLeM, CT. 06420 November 15. 2001 Mr. William R. Matthews Vice President & Sr. Nuclear Executive Dominion Nuclear Connecti,cut P.O. Box 128 Waterford, CT ,06385

Dear Mr. Matthews:

This letter is to confirm that the Town of Salem and the Salem Volunteer Fire Department will, to the best of its ability, during a station emergency, fill breathing bottles brought to the Salem Volunteer Fire Station by Dominion Nuclear Connecticut upon telephone request by its Emergency Response Operations. The Emergency Planning Services Department at Millstone Station is responsible for any questions pertaining to this agreement. (Contact Tom Dembek at 440-4223) Sincerely, Fire Chief Salem Volunteer Fire Department cc: Paul A. Blasioli, Emergency Planning Services Department.

• Millstone StotiotL 'J'l,ot.e 800-850-0042 StotiotL Fill< 800-850-2901 o* ! , B-19 Millstone Station Emergency Plan Revision 53 April2016 AppendixC APPENDIXC MAPS OF PLUME EXPOSURE AND INGESTION EXPOSURE EPZ, LOCATIONS OF ON-SITE AND OFF-SITE RADIOLOGICAL MONITORING STATIONS, STATION EVACUATION ROUTES C-1 Millstone Station Emergency Plan Revision 53 April2016 EMERGENCY PLANNING ZONE EVACUATION ROUTES waterford to East Hartford:

Rte. 85 Nortll tone. 82 Wesl to n .. 1 1 N orth to rte. 2 W est. to ex/I SA (Main Sl) Rig hi *t llght on1o Brewer St 1o In te rsection w ith Forbes SL Len OnlO Forbes SL 10 East H ig h School. OR 1-95 SOU(b to Rt 9 North to North to Exit 25-26 (ne. 3 Nortll). T*k* Exit 25 , cross over Putnam Bridg e to rte. 2 West to Exit SA (Moln SL) Right at light onto Brewer St. to lnt.ersedlon with Forbes SL Left omo Forbes Sl East Lyme , Lyme & Old Lyme to New Haven: South lo Exit 45 to rte. 10 N to Southern Connectiout Sloltl University field house. " Montville to East Hartfctd: Rte. 85 Nol1h lo rte. 82 We st torte.11 Nonh ID rte, 2 w .. t 1D Exit 5A (Main SL). Right at llgh1 omo Brewer St. to lnten;ectlon wfth Fortes St.. Lett onto Forbes st. to East Hartford H.S. OR lymeEPZ North to rte. 2 West IO E x tt 5A (Mai n S t). Rjght at l i g ht onto Br ei.'ler St. lo w ltfl Fo r bes SL Left. on t o fcrbe.s St. to East Hartfo r d H}9h School. New London to Windham: Rio. 32 N ID Frog Bridgt, ne.615. Right 011erbridge , s1ay 11181ght on Jackson St. to left on VaUey st. Twn Oghl onto Htgh SL up hm to Wlndh1m High School. AU areas U<Jt of rte. 1 56 a n d south of Beaver Brook Rd. Island Sound Mon t v i:!.::. " PZ Fishers Island, NY Ledyard EPZ All a r ea.a . _ Hill Rd., Chesterfield Rd .. rt'!. ic3 an ,: t:ep ot Rd. to the-Waterford All areas southolHurlbUU Rd., 11lt Radiological Emerpency Prop1redn.n Ofllfslon offhe COMtctkc.d Department of ErMrgrmcy Management .nd Hometend Secun"ty

• Groton City & Groton Town to Norwich: Rt e. 12 North to rte. 2A West t o 1-31>5 N to E><lt 81 E (n*..2E) to rte. 169 N orth {Har1and Rd.). Right on O* Hil Rd., nt><t right onto Mehan Drtve to Norwich Technlcol High School. OR Rte. 3<19 Nonh (CB Sharp Hwy) tol-95N10rtt

.117Norlhto rte. 2 Wgt to rte. 169 North (Hortand Rd.). Right on Ox t-al Rd. T*ke next right onto M*Mn Orive to NOIWich Technical High Sdloo l. OR Rte. 1 84 E 1o ne. 201 Norih 10 ne. 2W1o rte. 169 N (Harland Rd.). R i ghi at OK H I H Rd., lum right on1o Mah a n Drive to Nor\Jri'lch Technical Hig h Schoo l Fishers Island to Windham: To New London or Ston i ngton Harbor. S tate prov i ded bus transporta U on to W111dltam High School. 6 N 10 and E9. t 1 'fl . .!: : , n lin es l nd l.l d l ng those. Whalehead Rd. and Sandy Ho l ow Rd. l o rte.1 17. Current for 2011 '--------------------------------' --.. 20 Miles N ! 0 = = 0 rl:> ..... ("'.) 0 s s = = .... ..... .... rl:> = Q., M < r') = ..... .... 0 = 0 = ..... rl:> 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) .. '. : *. . C-3 ,; .. :.* .. Millstone Station Emergency Plan Revision 53 April2016 '*; .

• Figure C-3 Map of Millstone 10 Mile Emergency Planning Zone '" .... Distance (0-2m.i) (2-5 mi) (5-10 mi) Zone l Community A l Waterford (A-1) l East Lyme (A-2) B I East Lyme (B-1) I Waterford (B-2)
• iNew London (B-3) .C l East Lyme (C-1) I Montville (C-2)

.. ................... -......................... , ........ D Lyme (D-1) --. ! .. .. ___ , .......... _. _____ .......................... E ! Ledyard (E-1) . .. .. . .......... _ F I Fishers NI A ................ _ ........ _ ... _ ...................... C-4 Millstone Station Emergency Plan Revision 53

• April 2016 Figure C-4 Map Of Millstone 50-Mile Emergency Planning Zones I \.,.,j Connecticut *[Hartford

\ . I l l L ... -, !., 10-Mile Planning Zone\. -..., \ ...... C-5 BLOCK ISi.AN (} 50-Mile Ingestion Pathway Planning Zone Millstone Station Emergency Plan Revision 53 April2016 ALiEttNATE ROUTE VIA BAi..LFlEiO ACCESS ROAD P!U MARY ACC£SS ROUTE . MH.LSTONE ACCESS ROAD * ... _ *c *i'.i -5 Map of Millstolie. Evacuation Routes C-6. . '*:,_._. Station Emergency Plan* ' * ' Revision 53 April2016 ALTERNATE .ROUTE VIA OLD MILLSTONE ROAD AppendixD APPENDIXD SUPPORTING PROCEDURES LIST D-1 '. '*. Mmstone Station Emergency Plan Revision 53 April 2016 AppendixD Procedure Number Emergency Plan Implementing Procedures (EPls) MP-26-EPl-FAP01 CR Emergency Operations MP-26-EPl-FAP02 MP-26-EPl-FAP03 MP-26-EPl-FAP04 MP-26-EPl-FAP05 MP-26-EPl-FAP06. MP-26-EPl-FAP07 MP-26-EPl-FAP08 MP-26-EPl-FAP09 . MP-26-EPl-FAP10 MP-26-EPl-FAP12

MP-26-EPl-FAP14 TSC Activation and Operation OSC Activation and Operation EOF Activation and Operation State Emergency Operation Center (EOC) Activation and

• Operation
• Classification and PARs Notification and Communications Evacuation and Assembly
• Radiation Exposure Control Dose Assessment Core Damage Assessment Thermal Hydraulic Evaluation Recovery Emergency Plan Section(s) 5.1 5.2, 5.3, 7.3* 5.2, 5.3, 7.4_ 5.2, 5.2.14, 5.2.16, 5.3, 7.2 . 5.2, 5.2.1.4, 5.2.1.6, 5.3 4, 5.2.1, 6.2, 5.2.5 5.1, 6.1 6.4.1 6.4, 6.5 6.2.1, 6.2.3 6.2.4 5.2.18, 5.3.13 -9.0 .. : MP-26-EPl-FAP18 Innsbrook Corporate Support Center 5.4* Offsite Incident Command Post (ICP) Activation and Operation NIA Emergency Pl.an Procedures MP-26-EPA-FAP01 Management Program for Maintaining Emergency Preparedness MP-26-EPA-FAP05 MP-26-EPA-FAP07 MP-26-EPA-FAP08 MP'-26-EPA-FAP09 MP-26-EPA-FAP10 MP-2ff-EPA-FAP11 MP-26-EPA-FAP12 MP-26-EPA-GDL02 MP-26-EPA-GDL03 MP-26-EPA-GDL05 MP-26-EPA-GDL06 Emergency Planning Facility Maintenance Emergency Preparedness Departmental Staff Qualifications Public Ale.rting System Administration Public Alerting .system Test and Maintenance Public Alerting System Siren Test and Repair Public Alerting System Siren Acousticcil Performance Testing Public Alerting System Field Acoustical Measurement (Community Test) Document Maintenance and Storage Station Emergency Response Organization Qualification Maintenance Emergency Response Data System (EROS) Change Process OFIS 7.0,8.0. 7.0, 7.5 NIA 8.2 8.2 8.2 *8.2. 8.2 NIA NIA NIA 7.1, 7.2, 7.3 D-2. Millstone Station Emergency Plan Revision 53 April2016 Procedure Number MP-26-EPA-GDL07 MP-26-EPA-REF01 MP-26-EPA-REF02 MP-26-EPA-REF03 MP-26-EPA-REF04 MP-26-EPA-REF08B Fleet Procedures EP-AA-101 EP-AA-102 EP-AA-103 EP-AA-104 EP-AA-303 EP-AA-400 EP-AA-505 EP-AA-600

- \, .* ,H*,< AppendixD Title SERO Database and ENRS System Modifications Millstone Unit 1 Defueled Emergency Action Level {EAL) Basis Document Millstone Unit 2 Emergency Action Level (EAL) Basis Document Millstone Unit 3 Emergency Action Level {EAL) Basis Document Off-Site Programs Millstone Emergency Planning Resource Book 10 CFR 50.54(q) Change Evaluation Revision and Control of Emergency Plan, Emergency Action Levels (Technical Basis and Matrix), and Reference Manual Emergency Preparedness Performance Indicators Emergency Preparedness Steering Committee Equipment Important to Emergency Response Drill and Exercise Program B.5.b Program Emergency Plan Offsite Interfaces Emergency .Press Releases * *, Cyclic and Prompted Emergency Preparedness Tasks Emergency Plan Section(s) N/A N/A N/A N/A 8.0 8.2.1 N/A N/A N/A N/A Various 8.2 N/A f\l!f\. Nuclear Training Procedures TR-MP-TPG-2300 Millstone Fire Protection Program, Training Program Guide 8.1.3 TR-MP-TPG-2400 Emergency Plan Training Program Guide 8.1.1 Radiation Protection/Radiation Monitoring RPM Section 2.3.4 Inspection Maintenance Process for Respiratory Protection Equipment Various RP-AA-163 REMP Section 2.1 REMP Section 2.6 REMP Section 2.4 REMP Section 2.7 RPM Section 4.8.5 REMO DCM Inspection and Inventory of Respiratory Protection Equipment Various Sample Identification and Transmittal to the Contractor

6.2.4 Analyses

Terrestrial Biota Sampling 6.2.4 Soil Sampling 6.2.4 Terrestrial Water Sampling 6.2.4 Emergency Radiological Equipment Maintenance and Various Inspection Radiological Effluent Monitoring and Off-Site Dose Calculation Figure C-2, Manual Appendix H D-3 Table H-2 Millstone Station Emergency Plan Revision 53 April2016 iAppendixD Procedure Number Millstone Unit-2 Severe Accident Management Guidelines (SAMG) SAMG 4211 Phase 1 Initial Diagnosis SAMG 4212 Phase 2 Verification of Diagnosis SAMG4213 Phase 3 CHLA Implementation SAMG4214 Phase 4 Restorative Actions SAMG 4215 Calculational Aids E:DMG 2.01 MP2 B.5.b Event Initial Response EDMG 2.02 MP2 B.5.b Event TSC Response Millstone Unit-3 Severe Accident Management Guidelines (SAMG) SACRG-1 Severe Accident CR Guideline Initial Response SACRG-2 $ACRS-$ SAG-1 SAG-2 SAG-3 SAG-4 SAG-5 **SAG-6 SAG-7 SAG-8 SAG-9 SCG-1 SCG-2 SCG-3 SCG-4 SAEG-1 Severe Accident CR bi::* Activated

• *,: Severe Accident CR Response Injection into the Steam Generators Depressurize the RCS Inject into RCS Inject into Containment
• Reduce Fission Product Releases Control Containment Conditions Reduce Containment Hydrogen Flood Containment Severe Accident CR Guideline for MP3 :B.5.B TSC Event Response
• Mitigate Fission Product Release Depressurize Containment Control Hydrogen Flammability Control Containment Vacuum TSC Long Term Monitoring

' Emergency Plan Section(s) 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 5.2.2, 5.1.3, 5.3.12 . 5.2.2, 5.1.3, 5.3.12 . ' 5.3.12'. ' . 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5:a.12 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 D-4 Millstone Station Emergency Plan Revision 53 April2016

• Procedure Number SAEG-2 CA-1 CA-2 CA-3 CA-4 CA-5 CA-6 CA-7 DFC SCST AppendixD Title SAMG Termination RCS Injection to Recover Core Injection Rate for Long-Term Decay Heat Removal Hydrogen Flammability in Containment Volumetric Release Rate from Vent Containment Water Level and Volume RWST Gravity Drain Hydrogen Impact when Depressurizing Containment TSC Diagnostic Flow Chart Severe Challenge Status Tree Common Operating Procedures COP 200.2 C OP 200.2AIR COP 200.3 CSP 600.1 CSP 600.2 CSP 600.re *: ..
• CSP 600.4 CSP 600.20 Response to Security Events Airborne Threat Response to Medical Emergencies Paging Evacuation Alarm System Operability Test Communications-ENRS/ARCOS and Callback Monthly Test .. **.

Felice and Waterford Police Radio Systems OpernoiUty

• ' °1-"1'"Sl Communication-Radiopaging and ENRS/ARCOS Practice Test Communications-Emergency Response Data System EROS Operability Test Chemistry Department Procedures CP 3804K PASS RCS/RSS Sample (Unit 3) CP 3804AC CP 3804L. CP 3804M CP 2804L CP 2804M Liquid Waste Sample Sink (Unit 3) . PASS Containment Air Sample (Unit 3) PASS Ventilation Samples (Unit 3) Unit 2 Reactor Coolanf and Liquid Waste PASS Unit 2 Vent and Containment Air PASS Emergency Plan *
• Section(s) 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 5.2.3, 5.3.12 6.4.1 6.4.1 6.5.4, 6.5.5 8.2.1 8.2.1 : . ' ' * * * ****

_..,. ' *,* j>,' ,:" .". 8.2.1 8.2.1 N/A N/A N/A N/A N/A N/A D-5 Millstone Station Emergency Plan Revision 53 April2016 AppendixE APPENDIXE MILLSTONE EMERGENCY EQUIPMENT E-1 Millstone Station Emergency Plan Revision 53 April2016 AppendixE Figure E-1 Millstone Emergency Equipment Summary<6> Emergency Item Control TSC/ NAP/ Ambulance EOF RMT RMT Room osc SAP Kit Kit 1 Kit2 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-110 vac x x* x<?> Air Sampler-12 vdc x x<7l x Area Radiation Monitor x x L-2241-2/HP-210 (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<2> (5) (5) Emergency Dosimetry x x (5) x x x x Protective Equipment I Materials 3 : Respirators x x x. .x (5) (5) SCBA x x Fire Fae Clothing_ __ ._ ___ x x x x x : De<;o!l5m:.natk>n );4ai:iCJric:}.!;

• x t-_r __ ,_ ,---.

.. -,{ * .... -'.*.:..-.--*--* .. -< -* L .Ool")trcl l Decon Matarit1I __ x .. .

<.. .. .. Potassium*

Iodide Tablets U2,U3 x x x x x Communications Eauioment 3 : Dedicated Telephone Lines U2,U3 x x Emergency Radios x x x Satellite Phones U2,U3 x x Emergency Suoolies I Materials 3 : Emergency Preparedness Procedures x x x x x x RMT Vehicles x<2> 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-FAP05, EP Facility Maintenance.) (7) 11 Ov -RMT1 (U2,3 CR) TSC/OSC 12v -NAP/SAP over water E-2 Millstone Station Emergency Plan Revision 53 Aprll2016. AppendixF APPENDIXF DIAGRAMS AND ARRANGEMENT OF EMERGENCY FACILITIES ., '* **'J"* . ,,, *

• ',* ***o ; * *

.* .,_ ... '*; *r.o .. -.,.,.

• 1 * ,_._., *.. ->' ** F-1 Millstone Station Emergency Plan
• Revision 53 April 2016 Figure F-1 Diagram of TSC I OSC Layout NRC Work Area TSC Entrance from Unit3 Technical Support Center
• H\fft,;J.

Not to Scale-Typical

• Layout F-2 Electrical EqptRoom Lavatory Operational Support Center . .

...... I"*,

• Millstone Station Emergency Plan Revision 53 April2016
• ',::

Figure F-2 Diagram of Emergency Operations Facility Boifer Mechanical Switchgear UPS Roo Computer Room Alternate TSC/OSC RL NRC EOC F-3 RMTStorage Muster Are ill IRMT .Garage Entrance Millstone Station Emergency Plan Revision 53 April2016 Office Areas Drawing not to scale-Figure F-3

• Diagram of OSC Assembly Area Layout Building475 Walkway Walkway Cafeteria Kitchen Area OSC Assembly
• Area-Conference Room-102 ';,-,. Millstone Station Emergency Plan Revision 53 April 2016 * ,. '.,.,.:.*.,.17;.

>'. <:, AppendixG APPENDIXG CROSS-REFERENCE TO NUREG-0654 CRITERIA G-1 ::"-* Millstone Station Emergency Plan RevisiOn 53 April2016 Planning Standard AppendixG Summary of Planning Standard A. ASSIGNMENT OF RESPONSIBILITY (ORGANIZATION CONTROL) A.1.a A.1.b A.1.c A.1.d" A.1.e Identify State, Local, Federal and private organizations who are part of emergency plans. . Each organization !?hall specify its concept of operations and relationship to total effort.

• Illustrate relationships by block diagram. Title of individual in charge of emergency operations.

Provide for 24 hr./day emergency response and manning of communications. A.2.a Specify functions and responsibilities for major elements and key individuals by A.2.b Each plan shall contain the legal basis for such authorities. A.3 Include written letters of agreement. Include concept of operations, emergency measures to be provided, criteria for implementation and exchange of information. A.4 Title of individual responsible fOr assuring continuity of resources. B. ON-SITE EMERGENCY ORGANIZATION Plan Cross Reference (Section or Item) 1.1, 1.2, Table 1-1, Figure 1-1, Appendix B, Table 2-1 Sections 1, 5, 6, 9 Figures 1-2, 5-1, 7-1a, b,c 5.2.1, Figure 5-1 Section 5.0 N/A-State and Local requirement only. NIA-State and Local requirement 5.4.1, 5.4.2, Appendix 8 5,2.17, 5.4".3 .. 's_it_e_e_m_e-rg-. .. 8.2 coordinato*r 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. . 8.4 B.5 B.6 B.7 B.7a B.7b B.7d Specify functional responsibilities of emergency coordinator; Specify responsibilities which cannot be delegated (e.g., may not delegate the decision to notify and to recommend protective actions to authorities).

• Specify title and corresponding qualifications of emergency personnel.

lnelude 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. Specify interfaces between on-site and off-site organizations. Illustrate in block diagram. Specify corporate organization. Provide a t8:ble similar to B-1. Logistics support for emergency personnel Technical support for planning, reentry, recovery Management interface with government authorities Release of information to news media 5.1.1, 5.2.1 Table 5-1 1.2, Figures 1-1, 1-2, 1-3, 5-1 5.0, Table 5-1, Figure 5-1 5.2.17 Section9 6.1, Figures 7-1a, c 5.2.14, 5.2.16 G-2 Millstone Station Emergency Plan Revision 53 April2016 Appendix.G Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) 8.8 Specify private organizations and contractors who would provide 5.4 assistance.

8.9 Specify

services _to be provided by local agencies. Include 6.3.1, 6.4.1.b, 6.5.5, transportation and treatment of injured personnel who may be 6.5.6 contaminated.

8.9 Append

letters of agreement with contractor, local, and private 7 .10, Appendix 8 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. C.1.a C.1.b C.1.c C.2.b C.3 C.4 Specify persons by title authorized to request federal assistance. Specify federal resources expected, including expected times of arrival at specific nuclear facility sites. Specify resources available to support the federal response. Licensee may dispatch a representative to principal off-site governmental EOCs. Identify radiological laboratories, capabilities, and expected availability. Identify facilities, organizations, and individuals which can be relied upon in an emergency

• 1.2, 1.4 1.4, 5.4.3 1.4, 5.4.3 1.41 5.4.3 5.2.15, 5.2.16 7.10, Table H-2, Appendix 8, Table H-1 Table H-2, Appendix 8 D. EMERGENCY CLASSIFICATION SYSTEM -* ***' * -***-C*---'*

.. ****: *** .* . -----,,....------:---*-------------------. .._ .. ***. '?*. , *. ,

• -

.. '?-**"'.--*. { 1 ** **Establish EAL scheme per Appendix *1. * * -:_-_

• r;,,.-I . . ' . \'
• 2, 4-3 4-4, f
• 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 consistent with Appendix 1. Provide verification of messages.

1.3, 6.1 E.2 E.3 Establish procedures for notifying, alerting, and mobilizing emergency response personnel. Initial emergency message shall include: class of emergency, whether a release .is taking place, potentially affected areas, whether protective measures may be .necessary: 6.1 6.1 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. G-3 Millstone Station Emergency Plan Revision 53 April2016 '* AppendixG Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) F. EMERGENCY COMMUNICATIONS F.1 Identify organizational titles and alternates for communications 1.3, 6.1, Figures 7-1a, links. Establish primary and backup communications. 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, Figure 7-1a 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 field assessment teams. 7-1a, 7-tc F.1.e Provide for alerting and activating emergency personnel. 6.1 F.1.f Provide communications to NRC Headquarters, NRC Regional Figure 7-1b, 7-1c Office EOC, 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. '**" .. r---*** . -'!"'"- .. '-* ,. .. "'"\ -** l.

• must reach population wiWn
• f. ):'

. . . *. **r f

t:i.,(i . J irlclu<ie

\<tritten material that would likely be availa'!Jle

• . * . . emergency.

Updated information should be dissemb9ted . 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 TSC and OSC 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 for 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 G-4 Millstone Station Emergency Plan Revision 53 April2016 AppendixG Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) H.5.b Radiological 6.2.3, Table H-1, Figure C-2 H.5.c Process 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 . Estc;1blish central point for receipt anc;f, of fiiz!d

• *

' .. :u. W:data associated with EOFl a{Ki

$, H-2* ;;.,,;, * :::;>;,,,;.: . t !--->--. f* media. I ... **

• h:: I. ACCIDENT ASSESSMENT i.1 1.2 Cont'd Cont'd Cont'd Cont'd 1.3 1.3.a 1.3.b 1.4 Provide EALs and corresponding .emergency ,class. Section 4, Tables 4-1, 4-2, 4-3, 4-4 and Appendix I On-site capabilities to provide initial values and continuing N/A assessment (per NUREG-0578 and NRG letter of 10/30/79) including:

' Post-accident sampling capability AppendixD Radiation and effluent monitors Table H-1 In-plant iodine instrumentation Table H-1 *containment radiation monitors Table H-1 ' I Establish methods and techniques for determining: ' NIA Source term (e.g., relation of containment radiation monitors and 6.2.3, Appendix D m.aterial available for release.) Magnitude of release based on plant parameters and effluent monitors. Establish relationship between effluent monitor readings and exposures and contamination for meteorological conditions. G-5 6.2.3, Appendix D 6.2.3, Appendix D, 6.2.4.c Millstone Station Emergency Plan Revision 53 April2016 Planning Standard AppendixG Summary of Planning Standard 1.5 Acquire meteorological information per Appendix 2. Provide meteorological data to EOF, TSC, CR, and off-site NRC center. Make available to the State suitable meteorological data processing interconnections.

1.6 Determine

release rate/projected doses if instruments are scale or inoperable. I. 7 Field monitoring within plume EPZ. 1.8 Provide for rapid assessment of radiological hazards. For field teams include: activation, notification, composition, transportation communication, monitoring equipment.and deployment times. 1.9 Have capability to detect radio-iodine in air as low as 10-7 µCi/cc. 1.10 Relate measured parameters to dose rates. Estimate integrated dose from dose rates and compare to PAGs. J. PROTECTIVE RESPONSE J.1 Establish means and time to warn individuals in owner-controlled J.2 J.3 areas. Provide evacuation routes and transportation for on-site individuals to off-site locations, including alternatives. Provide radiological monitoring for people evacuated from the site. Plan Cross Reference (Section or Item) 6.2.3, 6.2.4.d, 7.13 6.2.3, 6.2.4 6.2.3, 6.2.4.h 6.2.3, 6.2.4.h, Appendix D 6.2.3, 6.2.4.h.4 6.2.3, 6.2.4.c, 6.2.4.e 6.4.1 6.4.1 6.4.1.i J.4 Provide evacuation of on-site non-essential personnel in Site 6.4.1.d, 6.4.1 .. . . . Area Emergency. PrQvide ... . * . .. .. * .-* * ** *

• f ** :*" ......

.. individuals ..... 6 .... .4 ..... =.1."""h"""'._... ... +* """***'----'--u t -t* J.6 J.7 Cont'd J.8 J.10 J.10.a J.10.b J.10.c J.10.m individuals within 30 minutes. Account for all individuals

• continuously thereafter.

Provide for individuals remaining or arriving on-site, Tespiratory

• protection, protective clothing, radioprotective drugs. Establish a mechanism for recommending protective actions to state/local authorities per EALs of Appendix 1 and Tables 2.1 and 2.2ofthe EPA PAGs. Provide prompt notification to off-site authorities .in plume EPZ as specified in NUREG-0654, Appendix 1. Time estimates for evacuation in plume EPZ in accordance with Appendix4.

Plans for protective measures to include: Maps Population distribution Means for notifying population Public protective strategies from plume exposure. 6.4.3, 6.4.4, 5.2.2, 5.2.5 1.3, 6.2.1, 6.2.2, 6.2.3, Figure 1-1, Table4-4 Section 4, Tables 4-1, 4-2, 4-3, 4-4, 6.1, Figures 7-1a; b, c Appendix J Appendix C AppendixJ 1.5, 6.1 6.2.1 G-6 Millstone Station Emergency Plan

• Revision 53 April2016 AppendixG Planning Summary of Planning Standard Plan Cross Referen standard (Section or Item) K. RADIOLOGICAL EXPOSURE CONTROL K1 Establish on-site exposure guidelines for: K.1.a Removal of injured persons 6.5 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 J 5.2.1 J 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 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.p Establish means for radiological decontamination of personnel, 6.4.3. 1 . . :r_supplies, equiprnept, and waste dis12osal. .);, K.6* .. eontrol'; including: ... .*. .... **,**:*:*** '-*-.. -**-,. _.,._ . ..,,. ___ $;;_,.,...-:--"" __ . . . . K.6.a : Area access* control 5.2.2, s*.2.5, 6.4.1, 6.4.3 K.6.b Drinking water and food supplies 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 personnel, 6.5.3 including extra clothing and decontaminates (particularly for radio-iodine contamination) .. L. MEDICAL AND PUBLIC HEAL TH SUPPORT L.1 Describe hospital and medical services, including preparations to 6.5.4, 6.5.5, 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. G-7 Millstone Station Emergency Plan Revision 53 April 2016 ' *, ** ... :. "'\ ... ... .. h AppendixG Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) 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. Section 9 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 N.1.b N.2 N.2.a N.2.b N.2.c Conduct an exercise as set forth in NRC and FEMA rules. Include mobilization of state and local resources. Provide for critique by Federal and State evaluators Conduct drills, in addition to the annual exercise, at the frequencies indicated. Communication drills (Quarterly), FEMA -IP State Fire drills -per technical specifications Medical drills -annually to include contaminated individual, ambulance, and off-site medical help. (Off-site portions may be part of annual exercise). 8.2.2.f 8.2.2 8.2 8.2 8.2 8.2 N.2.d Radiologica1*monitoring -annually (include collection and analysis 8.2 . of sample media). . * . . * . * , * . ..-. :*. .* ,. . .. . . *. ,, .. .. .. _1* *. Physics -*semi-annually to

• ' * * '*<environmental samRles; analyze actual
• J*--. . * . .-*;, * * .... -* N.3 N.4 N.5 with elevated radiation levels. . Describe the conduct of drills and exercises.

Official observers from Federal/State/Local governments critique exercises. Hold critiques. For:mal evaluation based on critiques. Establish means and management control for incorporating observer's comments into plan and implementing corrective actions. ** ' 8.2 8.2.2.g, 8.2.2 0. RADIOLOGICAL EMERGENCY RESPONSE TRAINING 0.1 0.1.a 0.2 Make provisions for training appropriate individuals. Provide training to off-site organizations Training for on-site organization to include drills in which individuals demonstrate abilities. On-the-spot corrections to be made and instructor to show proper performance .. 8.1 8.1.2 8.2 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 OA.b Personnel responsible for accident assessment 0.4.c Radiological monitoring teams G-8 8.1.1 8:1.1 8.1.1, 8.1.2 Millstone Station Emergency Plan Revision 53 April2016 AppendixG Planning Summary of Planning Standard Plan Cross Reference Standard (Section or Item) 0.4.d Police, security, and fire-fighting personnel 8.1.2 0.4.e On-site repair and damage control/corrective action teams 8.1.1 0.4.f First aid and rescue personnel 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 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 P.2 P.3 P.4 P.5 P.6 .. \' P.7 P.8 Cont'd P.9 Cont'd Cont'd Cont'd P.10 Train individuals responsible

• for planning effort. Section 8 Identify by title, individual with overall authority responsibility
• Section 8 for radiological emergency response planning.

Designate Emergency Planning Coordinator. Section 8 Review and certify plan annually. Update plans as needed. 8.3 Incorporate changes identified by drills and exercises. 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. Each plan shall contain a detailed list of s1Jpporting plans their somce . '* .'."""10" ,,,,, ,*,;**

• , " , , ,

... J""!) ..... In appendix, list, by title,

il*nt!:'!et:r.et'fHtre Appendb(D. " plan, including

• sections of the plan to be implemented by procedures.

Include specific table of contents and index. Table of Contents Cross reference to NUREG-01;)54 criteria AppendixG Conduct independent reviews at least every 12 months and 8.3 include: Plan, procedures, practices, training, readiness, testing; 8.3 equipment.and interfaces with State and Local governments. Include management controls for implementation and correction 8.3 of audit findings. Document reports to management and involved Federal, State 8.3 and Local organizations. Retain for 5 years .. Provide for updating telephone numbers in emergency 8.2.1.a procedures at least quarterly. G-9 Millstone Station Emergency Plan Revision 53 April2016

• *-*** .

AppendixH APPENDIXH RADIOLOGICAL ASSESSMENT EQUIPMENT AND FACILITIES H-1 _:;-,, . ,, Millstone Station Emergency Plan Revision 53 April2016 TableH-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector 1. 1. Monitors Meteorological Tower 4 Wind speed indicators 4 Wind direction indicators 3 Delta temp. sensors Meteorological Mast 1 Wind speed indication 1 Wind direction indicator Time History Containment base slab (Unit 2) Accelerographs Auxiliary building Intake structure Free field Peak Accelerographs Containment base slab Steam generator support Pressurizer support . Safety injection tank support Seismic Trigger Containment base slab Response Spectrum Containment base slab Recorder Radiological Monitors Unit 1 Process Monitors RM-SFPl-02 Unit 2 Process Monitors RM8123A Containment recirculation air particulate RM8123B Containment

• recirculation air gaseous RM8262A Containment . recirculation air particulate RM8262B Containment recirculation air gaseous . . RM8434A Radwaste ventilation particulate RM8434B Radwaste ventilation gaseous H-2 Individual Applicability Monitor wind speed at 33', 142', 374', and 447' elevations Monitor wind direction at 33', 142', 374', and 447' elevations Monitor temp. difference between . 33' and 142' 33' and 374' 33' and 447' Monitor wind speed at 33'. Monitor wind direction at 33'. Record ground accelerations with
• respect to time II II II II II II Record peak ground accelerations II II *" '* II ... Activate an annunciator Records ground accelerations Measure gaseous activity Monitor particulate activity Monitor gaseous activity Monitor particulate activity Monitor gaseous activity Monitor particulate activity Monitor gaseous activity Millstone Station Emergency Plan Revision 53
• April2016

','.,;:-' Table H-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

• M.easure 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 range RM8168B range RM5099 Steam jet air ejector RM9095 Waste gas storage tanks discharge gaseous RM4262 Steam generator blowdown RM6038 Reactor building closed cooling water . RM9049 Clean radwaste discharge RM9116 Aerated radwaste discharge RM9327 Condensate recovery tank 2CND-RE245 Condensate polishing neutralizing sump RM-8169 Wide Range Gas Monitor H-3 Monitor high level gaseous activity ' . . ' '

-.

• Monitor gaseous activity
• Monitor gaseous activity Monitor liquid activity Monitor liq.uid activity Monitor liquid activity Monitor liquid activity Monitor liquid activity Monitor liquid activity Monitors particulate and gaseous radioactivity Millstone Station Emergency Plan Revision 53 April2016 TableH-1 On-Site Assessment Equipment and Facilities Functional System Instrument Detector Unit 3 Process Monitors 3HVR-RE10 A & B Ventilation Vent 3HVR-RE11

&12 (A&B) Auxiliary Building (lower levels) 3HVR-RE13, 14 & 15(A&B) Auxiliary Building (upper levels) 3HVR-RE16 (A&B) Charging Pump Cubicle 3HVR-RE17 (A&B) Fuel-Building 3HVR-RE18 (A&B) Waste Building 3HVR-RE19 (A&B) SLCRS 3HVR-RE91 (A&B) Control Room ** 3HVQ-RE49 ESF Building 3CMS-RE22 A&B Containment Atmosphere Individual Applicability Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous activity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity Monitors particulate and gaseous activity

• Monitors particulate and gaseous radioactivity Monitors particulate and gaseous radioactivity

-, 3HVZ\:.REO$F'A&.B Hyardt;;erJ;i'; Recombiner Cubicles 3HVC-RE16 A&B Control Monitors gaseous radioactivity Building Inlet ventilation 3MSS-RE75, 76, 77, 78 4 Main Monitors gaseous radioactivity Steam Relief lines 3ARC-RE21 Condenser Air .Ejector 3GWS-RE48 Hydrogenated Vent 3MSS-RE79 Turbine Driven Auxiliary Pump

• Discharge 3SSR-RE08 Steam Generator Slowdown 3CCP-RE31 Reactor Plant Component Cooling 3CNA-RE47 Auxiliary Condensate 3LWS-RE70 Liquid Waste H-4 Monitors gaseous radioactivity Monitors gaseous radioactivity Monitors gaseous radioactivity Monitors liquid radioa 1 ctivity Monitors liquid radioactivity Monitors liquid radioactivity Monitors liquid radioactivity Millstone Station Emergency Plan Revision 53 April2016 ;.$;:

TableH ... 1 On-Site Assessment Equipment and Facilities Functional System Unit 3 Process Monitors (Cont'd) Unit 1 Area Radiation Monitors Unit 2 Area Radiation Monitors Instrument Detector 30AS-RE50 Turbine Building Drains* 3LWC-RE65 Regenerant Evaporator RM-SFPl-01 RM-7892 Drumming and decontamination area Individual Applicability Monitors liquid radioactivity Monitors liquid radioactivity Monitor Radiation Levels Measure radiation levels RM-7894 Engineered Measure radiation levels safeguards systems area RM-7895 Sampling area Measure radiation leyels 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) HM-8157
• *.'
• wall) RM-8240 Containment High Radiation RM-8241 Containment High Radiation 2-RMS-9813 Drumming area 2-RMS-9799A Control Room ventilation air supply 2.;RMS-97998 Control Room Ventilation air supply 2-RMS-04 (not in use) solid waste 2-RMS-05 (not in use) Condensate demineralizers 2-RMS-06 (not in use) Access area 2-RMS-08 (not in use) Evaporator H-5 Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Measure radiation levels Millstone Station Emergency Plan Revision 53 April 2016 Functional System Unit 3 Area Radiation Monitors TableH-1 On-Site Assessment Equipment and Facilities Instrument Detector Individual Applicability 3RMS-RE01 Manipulator Crane Measure radiation levels 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 Measure radiation levels PiUHoist 52'4" Fuel Bldg . . 3RMS-RE09 Aux. Bldg. General Measure radiation levels 18'6" Aux. Bldg. 3HMS-RE1 o Aux. Bldg. General rt1dlafiJn '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. Measl!re radiation levels 3RMS-RE18 Waste Disp. Bldg. . radiation levels 4'6" Waste Bldg. 4RMS-RE19 Solid Waste Measure radiation levels Storage 24'6" Waste Bldg. 3RMS-RE20 Sample Room Measure radiation levels 43'6" Aux. Bldg. H-6 Millstone Station Emergency Plan Revision 53

• April2016 TableH-1
• On-Site Assessment Equipment and Facilities Functional System Unit 3 Area Radiation Monitors (Cont'd) 2. Radiation Monitors and Sampling Equipment Instrument Detector 3RMS-RE21 Service Bldg. Laboratory 24'6" Service Bldg. 3RMS-RE22 Control Room Monitor 47'6" Control 131dg. Individual Applicability Measure radiation levels Measure radiation levels 3RMS-RE24 Waste 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" (Normal Range) 4'6" ESF Bldg. 3RMS RE34 R ,_,I:'.'.

f"', .. : . . -1 r .. f,.f:,\f" . (Normal Range*) 4'6"ESFB,fitJfi: .. Measure 3RMS-RE35 ln-Cor1C*{nst:

• .. * ,, * *-Measure radiation levels Thimble Area 3'8" Containment 3RMS-RE36 Fuel Pool Monitor Measure radiation levels 52'4" Fuel Bldg. ; 3RMS-RE37 Condensate . Measure radiation levels Demin. Area 14'6" Cond. Polishing Bldg. 3RMS-RE38 Area Measure radiation levels 38'6" Cond. Polishing Bldg. 3RMS-RE41 Fuel Drop Monitor Measure radiation levels 51'4"

• 3RMS-RE42 Fuel Drop Monitor Measure radiation levels 51'4" Containment 3RMS-RE52 Recombiner Measure radiation levels Control Room 24'6" Recombine Bldg. Gamma spectrometers Isotopic identification and analysis Geiger-Mueller survey Measure gamma and beta radiation instruments R/hr range) dose rate H-7 Millstone Station Emergency Plan Revision 53 April2016 TableH-1 On-Site Assessment Equipment and Facilities Functional System Radiation Monitors and Sampling Equipment . (Cont'd) 3. Fire Detection

4. Facilities Instrument Detector Individual Applicability Ionization chamber (0-1,000 R/hr Measure gamma and beta radiation range) dose rate Contamination survey Air sampling equipment Neutron survey instrument TLD Direct reading pocket ion chamber Smoke detectors Rate of rise heat detector Fixed heat detector Chemistry la.boratory 9 radiation monitoring stations 4 Fixed air sampling stations Health Ptiys!:cs Lahorcto!j' H-8 Count samples for gross alpha and beta Sample for airborne radionuclides (particulate, iodine, gaseous, and tritium) Measure neutron radiation dose rate Measure personnel radiation dose Measure personnel gamma radiation dose Detects products of combustion Detects quick rise of temperature Detects a set temperature Equipped for chemical and radiological analysis Measure gamma radiation dose Sample particulates and iodines Equipped .for rqdjologicql_ . . ;:*_ --. ' . . , *: Millstone Station Emergency Plan Revision 53 April 2016 Functional System 1. Geophysical Monitors Meteorological Seismic 2. Radiological Monitors Environ mental Monitoring

3. Laboratory Facilities Radiochemistry laboratory AppendixH TableH-2 Off-Site Assessment Equipment and Facilities Instrument Detector Meteorological forecasting contractor for full weather forecast service Individual Applicability Provide current and forecast weather for Millstone area United States Geological Survey Record ground accelerations (USGS) for Strong motion recorder As specified by REMODCM Teledyne Brown Engineering Environmental Services GEL Environmental Laboratory Gamma radiation dose and sample particulates and iodines Equipped for chemical and radiological analysis Equipped for chemical and radiological*analysis , :

• Emergency
• Equipped for limited radiological analyses.

H-9 Millstone Station Emergency Plan Revision 53 April2016 Appendix I APPENDIX I EMERGENCY ACTION LEVEL SCHEME . r_ . NOTE: 'fhe EAL* s-.cheme provides an e)u'lnple of of 50.47(b) and requirements of Appendix-B: Emergency Assessment procedure MP-26-EPI-FAP06fue usedto classify event I-1 Millstone Station Emergency Plan Revision 53 April2016 M illstone Unit 1 Emer g ency Action Levels D UNUSUAL EVENT DELTA ONE n UNUSUAL EVENT DEL TA TWO n ALERT CHARLIE ONE IN-PLAN T RADIATION SECURITY THREAT/ DESTRUCTIVE P HENOMENA FIRE/GASES '--__ __ N_T ____________ __.ll RADIATION (D-AA2) ,-(D-HAl) . 1. Area radiation monitor reading in Reactor Building or survey results indicate an UNCONTROLLED increase in radiation levels by 100 mR/hr that is not the result of a planned evolution AND impedes operation of systems needed to maintain spent fuel integrity.

2. Valid radiation monitor reading or survey results indicate greater than 15 mR/hr in areas required to be occupied 24 hours a day. 1. Any on-going or imminent security compromise to the safety of the plant. I TA2 DESTRUCTIVE PHENOMENA

_ (N I A) An event that damages systems, structures , or components needed to maintain spent fuel integrity that may result in overexposure of site personnel or results in an uncontrolle d decrease in the spent fuel pool water level or damage to spent fuel. .l R_u __ i __ RE_A_c_T_o_R __ B_UIL __ D_IN __ G __ Jll TUl ,-RADIATION (D-AU2) . SECURITY EVENT (D-HUl) Area radiation monitor reading in Reactor Building or survey results indicate an UNCONTROLLED increase in radiation levels by 25 mR/hr that is not the result of a planned evolution. l,

• Security events as determined for Station Safeguards Contingency Plan and reported by Secuiity Shift Supervision.

2. A credible site-specific security threat notification.

setpoin ts are contained in EPI-FAP06 , "C la ssification and PARs." l l GUI FIRE (D-HU3) I. Life threatening toxic gases OR flammable gas concentrations as identified in C-OP 200.5, "Oil , Hazardous Material , Hazardous Waste and Mixed Waste Contingency Plan ," affecting activities in areas needed to maintain spent fuel integrity.

2. Notification of a near-site release that may require evacuation of MPI. FUEL POOL EQUIPMENT FAILURE FUEL POOL LEVEL (D-SUI) Uncontrolled decrease in fuel pool level indicated by a low level alarm actuation with all spent fuel assemblies remaining covered by water. UNPLANNED OFFSITE RELEASES .TUDGEMENT I OAl OFFSITE DOSE (D-AAl) 11 JAI JUDGEMENT . (D-HA2) 1. Unplanned release of 3.42E-l Any condition for whichjudgment

µCi/cc to the environment indicates that the level of safety times REMODCM for the Reactor Building or other release limit) for minutes. areas important for maintaining

2. Grab sample analyses indicate unplanned gaseous release rate 3.42E-l µCi/cc times the REMODCM limit) for minutes. 1 1 OUl UNPLANNED RELEASES (D-AUI) I. Gaseous eftluen t monito r*-* 3.42E-3 µCi/cc (2: 2 times REMODCM limits) 60 minutes. 2. Grab sample analyses indicate unplanned gaseous release 3.42E-3 2 times the REMODCM limit) for minutes. the integrity of the spent fuel is substantially degraded and which requires Station Emergency Response Organization (SERO) staffing.

JUDGEMENT (D-HU2) Any condition for which judgement indicates the potential or actual degradation in the level of safety of the Reactor Building or other areas important to maintaining the integrity of the spent fuel. AREAS NEEDED TO MAINTAIN SPENT FUEL INTEGRITY

• Reactor Building -4th and 5th Floors
• Reactor Building , Fuel Pool Pump Mezzanine

-2nd floor

• H& V Room -Lower Level (DHR)
• H& V Room -Roof -Coolers 11 11 CLASSIFICATION ALE R T CHARLIE ONE Events are in progress or have occurred which indicate an actual or potential substantial degradation of the level of safety of the plant, to plant personnel, or to the safe storage of fuel in the spent fuel p o ol. UNUSUAL EVENT OR DELTA ONE Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. 1 Millstone Millstone Emergency Plan Revision 53 April 2016 Page I-2 of8 MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS I] GENERAL EMERGENCY ALPHA SITE AREA EMERGENCY D GENERAL EMERGENCY BRAVO D CHARLIE-TWO D ALERT CHARLIE-ONE BARRIER FAILURE .__ __ A_N_Y_TW_O_BA_R_R_l_ER_s

__ _.I I Mode 1 , 2 , 3, 4 See Barrier Failure Reference Table §] I FUEL CLAD OR RCS BARRIER I I Mode 1, 2, 3 , 4 See Barrier Failure Reference Table I BA2 j __ s_T_EA_M_L_JN_E_B_R_EA_K __ _.l I Mode 1, 2, 3, 4 Unisolable Steam Line Break Outside CTMT l.__ __ c_T_M_T_B_A_R_R_IE_R __ ___.l I Mode 1 , 2, 3, 4 See Barrier Fai l ure Reference Table ___ R_c_s_L_EA_KA_G_E __ __..I I Mode 1, 2, 3 , 4 1. Pressure Boundary Leakage > 1 O GPM 2. Unidentified Leakage > 1 O GPM 3. Identified Leakage > 25 GPM 4. Primary to Secondary Leakage >25 GPM I FUEL CLAD DEGRADATION I ._I __ M_od_e_A_L_L _ __. 1. RCS Activity> 60 µCi/gm 1-131 DEQ 2. Dose Rate at One Foot from Unpressurized RCS 2 mR/hr/ml LOSS OF POWER __ s_T_A_TJ_O_N_B_LA_C_K_O_UT __ _.I I Mode 1 , 2 , 3, 4 Loss of Voltage on Buses 24C AND 24D AND ANY of the Following: Restoration of Power to AT LEAST One Vital Bus is NOT Likely Within Four Hours Core Exit Thermocouple Readings Indicate Superheat Inadequate SG Heat Removal Capability as Indicated by SG Water 10% in BOTH SGs AND Inadequate Terry Turbine Feedwater Flow I Mode 1 , 2 , 3, 4 Loss of Voltage on Buses 24C AND 24D > 15 Minutes I LOSS OF DC I I Mode 1, 2, 3, 4 Loss of Voltage on DC Buses 201 A AND 201 B > 15 Minutes ._I __ S_T_A_T_IO_N_B_LA_C_K_O_U_T _ ___.I I Mode 5 , 6, 0 Loss of V o ltage on Buses 24C llli.Q 24D > 15 Minutes I PA2 I I SINGLE AC POWER SOURCE I I Mode 1, 2 , 3 , 4 Only One AC Power Source Available to Supply Buses 24C AND/OR 24D > 15 Minutes Such That Loss of That Power Source Would Result in a Station Blackout (Unit 3 Buses 34NB CANNOT be Credited unless already aligned to Unit 2 Bus 24C or 24D) I LOSS OF OFFSITE POWER I ._I _M_o_d_e_A_LL _ _, Loss of all OFFSITE power to buses 24C AND 24D for > 15 Minutes. ___ Lo_s_s_o_F_Dc ___ _.I _M_o_d_e_5_,6 _ _, Loss of Voltage on DC Buses 201A AND 201 B > 15 Minutes 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. EQUIPMENT FAILURE I ATWS/JNADEQUATE COOLING I _1 _ _. Functional Recovery of Reactivity Control Ineffective AND EITHER of the Following: RCS Heat Removal by Steam Generator Heat Removal SFSC Criteria Can NOT Be Satisfied Core Exit TC Temperature Readings> 800°F ._l ____ A_TW_s ___ __.I ..... Manual Reactor Trip Attempted At Panel C 04 AND Reactor Is NOT Shutdown .-I -1N_A_B_IL-ITY_T_O_M_A_INT_A_IN_H_O_T_S_/D---.I I Mode 1 , 2, 3, 4 1. No RCS Heat R em o val Via Steam Gene rators AND.On ce Through Coo ling NOT Effect ive AND Shutdow n Coo ling is NOT In Service 2. RCS Boration C apability Unable to Eliminate Inadvertent Criticality I IN-VESSEL FUEL UNCOVERY I I Mode 5 , 6 Shutdown Cooling Has Been Lost htlQ ANY of the Following Conditi ons Exist: Alternate Methods for Restoring RCS Inventory are NOT E ffective RVLMS Read ing = 0% with OPERABLE #8 string (NA if no OPERABLE #8 string) Core E xit TC Temperature Read in s Indicate Su;..pe_r_h_ea_t ____ oss OF ANNUNCIATORS{fRANSIEN I Mode 1 , 2, 3 , 4 Loss of Most (75%) MCB Annunciators AND BOTH of the Following Sign ificant Transient in Progress Loss of SPDS AND ICC Instrumentation I AUTOMATIC RX TRIP FAILURE I l.___M_o_d_e_1.;...., 2 _ _, Failure of Automatic Reactor Trip A.t:fil Manual Tr ip Was Successful I EA2 I j 1NABILITY TO MAINTAIN COLDS/DI I Mode 5, 6 1. Uncontrolled RCS Temperature Increase> 10°FThat R esults in RCS Temperature> 200°F 2. Inadvertent Cr iticality I EA3 I koss OF ANNUNCIATORSffRANSIEN) Mode 1 , 2, 3 , 4 Loss of Most (75%) MCB Annunciators > 15 Minutes AND EITHER of the Fo llowin g: Significant Transient in Progress Loss of SPDS AND ICC Instrumentation I LOSS OF COLD S/D FUNCTION I Mode 5, 6 1. Loss of Shutdo wn C ooling > 15 Minutes AND Refue l Pool Water Level < 35 Ft., 6 In. 2. Uncontrolled RCS Temperature Increase> 10°F 3. RCS Boron Concentration < Minimum Requ i red I REFUEL/SPENT FUEL POOL LEVELi .... I _M_o_d_e_6_, o _ _, 1. Unco ntrolled Sp en t Fue l Pool Water Le v el Decrease Causing Loss of Coo li ng Suction Flow 2. Uncontrolled Re fuel Pool Water Le v el Decrease Requiring Containment Evacuation AND All Spent F uel Assemb li es in Safe Storage Locat ions I LOSS OF ANNUNCIATORS I I Mode 1 , 2 , 3 , 4 I Los s of Most (75%) MCB Annunciators > 15 Minutes htlQ SPDS OR ICC Instrumentation Available I EU4 I I LOSS OF COMMUN ICATI ONS I l.....__M_o_d_e_A_LL _ _, 1. Loss of ALL Ons tte Elect ronic C ommunications Methods 2. Loss of ALL Electronic Communications Methods Wrth Government Agencies I SHUTDOWN LCO EXCEEDED I I Mode 1 , 2 , 3 , 4 I. Unit NOT Brought To Required Mode Wrthin App licable LCO Ac tion Statement Time Limits D UNUSUAL EVENT DELTA-TWO OFFSITE RELEASES I OG1 I I OFFSITE DOSE I I Mode ALL 1. MP2 Kaman Vent Monitor (RM-8168) Reading z 2 µCi/cc for > 15 Minutes 2. MP2 WRGM S i te Stack Effluent Activity (RM-8169) Reading z 30 µCl/cc for > 15 Minutes 3. MSL Monitor (RM-4299/A/B/C) Read i ng .!!._2 R/hr for > 15 Minutes 4. Measured Plume Dose Rate OnSitez 1,000 mR/hr for > 15 Minutes 5. Rad Assessment Determines Integrated Dose Offsite z 1 Rem TEDE OR z 5 Rem COE Thyroid .... I ___ o_FF_S_JT_E_D_O_S_E __ __,I I Mode ALL 1. MP2 Kaman Vent Monitor (RM-8168) Reading z 0.2 µCi/cc for> 15 Minutes 2. MP2 WRGM Site Stac k Effluent Activity (RM-8169) Reading z 10 µC i/cc for> 15 Minutes 3. MSL Monitor (RM-4299A/B /C) Reading z 0.3 R/hr for > 15 Minutes 4. Measured Plume Dose Rate Onsite z 50 mR/h r for > 15 Minutes 5. Rad Assessment Determines Integ r ated Dose Offsite .!!. 0.05 Rem TEDE OR.!!. 0.25 Rem COE Th yro id .... I ___ O_FF_S_IT_E_D_O_S_E __ __,j I Mode ALL 1. MP2 Kaman Vent Monitor (RM-8168) Reading z 0.02 µC i/c c for> 15 Minutes 2. MP2 WRGM Site Stack Effluent Activity (RM-8 169) Reading z 1 µCi/cc for > 1 5 Minutes 3. MSL Monitor (RM-4299NB /C) Reading.!!. 0.03 R/hr for> 15 Minutes 4. Measured P lum e Dose Rate.Onsit e z5 mR/hr for > 15 Minutes 5. Rad Assessment Dete rmines Integrated Do se Offsite z 0.005 Rem TEDE OR.!!. 0.025 Rem COE Thyroid D UNUSUAL EVENT DELTA-ONE CLASSIFICATION I GENERALEMERGENCY I I ALPHA -I OR BRAVO Events are In process or have occurred which inv olve 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 offsite for more than the immediate site area. SITE AREA EMERGENCY CHARLIE-TWO Events are in process or have occurred which involve an actual or likely major failure 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 exeed EPA Protective Action Guideline exposure levels beyond the site boundary. ALERT CHARLIE-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 Protect ive Action Guideline exposure level s. UNUSUAL EVENT DELTA...:fW9 OR DELTA-ONE Events are in process or have occurred which in d icate a potential degradation o f the level of safety of the plant or indicate a security ttfreat to facility protection. No releases of radioactive material requiring offsite response or monitoring are e x pected unless further degradation of safety systems occurs. 2 Millstone Millstone Emergency Plan Revision 53 April 2016 1-3 of 8 MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS ri GENERAL EMERGENCY ALPHA SITE AREA EMERGENCY D GENERAL EMERGENCY BRAVO D CHARLIE-TW O D ALERT CHARLIE-ONE IN -PLANT RADIATION SECURITY THREAT/ FIRE/GASES D F STRUC T TVE PHENOM ENA I MAJOR FUEL DAMAGE I I Mode ALL I I SECURITY EVENT I I Mode ALL I --' 1. RM-8240/8241 Rea.ding > 1 1 200 R/hr_ , A HOSTILE FORCE has taken control of plant equipment such that 2. At Least 20% Fuel Claq Damage As Determined By Core plant personnel are unable to operate equipment required to Damage Estimate ' --maintain safety functions. Any of the following meet this EAL: . 3. Spent F).1el is frorp *water from Operi 1. Loss of Control Room Cavit}r, Or SF Pool AND !i!OTH of the Following: _ * '* 2. Loss of Hot Shutdown Panel (C-21) (West 480v SWGR Room) 3. Loss of Cold Shutdown Panel (C-10) (Upper 4160v SWGR Room) !. Spent Fuel Has Decayed -S 30 Days -* 4. Security reports the loss or imm i nent loss of a Target Set -*

• CTMT l_ntegrity is Establisl]e

.d OR Expo5ed Spent OR Fuel is Outside CTMT -A HOSTILE ACTION has caused failure of Spent Fuel Cooling r -** . Systems and IMMINENT (for EA Ls) fuel damage is likely for a freshly .. -. ' ' . off-loaded reactor core in pool. -I SPENT FUEL DAMAGE I I Mode ALL I I SECURITY EVENT I I Mode ALL I I CONTROL ROOM EVACUATION I I Mode ALL Spent Fuel is E x pos ed from Op en Vessel or Ca vity AND BOTH A not ifi cat ion from the s ite security force that an armed attack , Uni t Con trol from Hot Shutdown Pane l C-1 O Or C-21 of the Follow in g: e xplosive attack , a irli ner impact , or other HOSTILE ACTION i s NOT Establi shed Within 15 Minutes A fter C ont r o l Room occu rr i ng or has occurred within the protected area. Evacuat io n . Sp ent Fuel Has D ecay ed < 30 Days . CTMT Integrity Es t ablish ed --§] I SPENT FUEL ASSEMBLY DAMAGE I I Mode ALL I I SECURITY EVENT I I Mode ALL I I CONTROL ROO M EVACUATION I I Mode ALL Spent Fue l is Exposed f rom Open Vessel , Ca vity, or SF Po o l 1. Security Events as de te rm ine d for St ation S afeguards Co ntingency Plan and reporte d by Security S hift S upervision. (Addre sses events Con trol Room E v acu atio n Initiated AND Sp ent Fuel Has D ec ayed.?!. 30 Days that involve Actual or Potential Substant ial degradation to the level of 2. Fue l Handling Accid en t Caus in g Damage to Sp e nt Fuel , safety of the plant.) I GA2 I I I I Ind ic ated by Fu e l Building OR C ontai nm en t Radiat io n Monitors 2. A not ificatio n from the site se c urity f orce that an armed attack, FIRE/E X PLOS I ON Mode ALL Increasing explosive att a ck, airliner impact, or o t her HOSTILE ACTION is I RA2 I I I I I occurring or h as occurred within the OCA. F ire or Explosio n Affecting Safe Shutdo w n Area AND Damage PLANT RADIATION Mode ALL 3. A validated notif ication from the NRC of an airliner attack threat less to Structures QB Saf e Shutdown Equipm ent In d icated. than 30 minutes away. 1. Rad iation Readings > 15 mR/hr in Contro l Room OR C entral I TA2 I I A la rm Station QB Se con dary Alarm Stat io n DESTRUCTIVE PHENOME NA I I Mo de ALL I I GA3 I I TO XIC/FLAMMABLE GASES I I Mode ALL 2. Radiat ion Reading > 5 R/hr in Ar ea s Requiring Access for 1. Seism ic Event > 0.09g ZPA Life Thre ate ning To x ic Gases QB F lammable Gas Concentrat io ns Safe Shutdown 2. Ons i te Sustained W indspeed > 90 MPH 3. Vis ible D amage to Stru ct u res or Equipment AND Affecting Saf e as Identified i n C-OP 200.5 , " Oil , Hazardous Material, Hazardous Shu tdown Waste and Mixed Waste Conti n gency Plan" Affecting Areas for 4. Vessel or Vehicle Co llision AND Affect in g Safe S hutdown Sa fe Sh utdown 5. M issiles Affect ing S afe S h utd own 6. Flood in g Affecting Sa le Sh utdown I RAD MONITORS I I Mode ALL I I SECURITY EVENT I I Mode ALL I I FIRE I I M ode ALL I 1. Security Cond ition as determined for Stat io n Safeguards Con tingency 1. Fire in Building OR Ar eas Ad jacen t to Areas Needed for S ale 1. Unc ontro ll ed R efuel P ool Water Level Decr ease AND Rad Plan and reported by S ecurity Shift S upervision. (Addresses events Shutdown NOT E xtinguished Wrthin 15 Minutes o f Notification QB Levels R equire Evacuat i on of CTMT or Sp ent F:uel Po ol Area that involve P otential degradat ion in the level of safety of the plant.) Verificat ion of Control Room Alarms 2. A credible site specific sec ur ity th reat n otification.

2. F ire Affect ing a Load e d ISFSI Confinement Bound a ry NOT 2. Une x pect e d Area Rad Monitor R e ading Offscal e High QB E xtin g uished Withi n 15 Minutes of Not ifi cat ion. > 1000 Times Normal Reading 3. A va lid a t ed no tification from the NRC prov i ding i nformation of an aircraft th reat. I Gu2 I I TOXIC/FLAMMABLE GASES I I I I I I I Mode ALL DESTRUCTIVE PHENOMENA Mode ALL 1. Life T hreatening To xic Gases QB F lammable Gas Concent rations as 1. S eismic Activity Detected Per AOP-2562 , Eart hquake Identified in C-OP 200.5, " Oil , Haza r dous Material , Hazard ous Waste 2. R eport by Plant Personne l of Tornado S triking Within P rot ected Area and Mixed Waste C ontingency P l an" Affecting Normal O peration 3. Visible Damage to Structures or Equipment Within the Protected Area 2. Notification of a Near-Site Re lea se That May Require E vacuation

4. Onsite Sustained Windspeed

> 75 MPH D UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE JUDGEMENT CLASSIFICATION I JUDGEMENT I I Mode ALL I I GENERAL EMERGENC Y I Other Conditions Exist For Which Judgement Indicates: I .ALPHA** I 1. Actual Or Imminent Substantial Core Degradation OR With Potential For Loss Of Containment, QB. BRAVO 2. Potential For Uncontrolled Radiological Releases . Events are In process or have occurred which These Releases Can Be Reasonably Expected To involve actual or Imm i nent substantial core degradation or melting with potential for loss of Exceed EPA PAG Plume Exposure Levels Outside containment integrity or security events that The Site Boundary result In an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Act i on Guideline exposure levels offsite for more than the immediate site area. I I JUDGEMENT I I Mode ALL I I S I TE AREA EMERGENCY I O ther Condi ti ons Ex i st For Which Judgem ent Indicates CHARLIE-TWO Actua l Or Likely Major Fa ilu res of P la n t Funct io ns Needed Events are In process or have occurred which For Protec ton Of The Pub lic inv o lve an actual or likely major failure of plant functions needed for protection of the public o_r security events that result In intenti on al 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. I I JUDGEMENT I I Mode ALL I I ALERT I Any Cond itio n Fo r Which Judgement Indicates That Saf ety CHARLIE-ONE Sys tem s May Be Degraded AND Which R e qu ire s Emergency E vents are in process or have occurred which I Respons e Organ ization Staffing involve an actual or potential substantial degradation of t he level of safety of the plant or a secu rity event that involves pr obable life threatening risk to site p ersonnel or damage to site equipment because of i nt entional malic ious ded icated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA I Pr otective Action Guide line exposure levels. I JUDGEMENT I I Mode ALL I I UNUSUAL EVENT I Any Condition For Wh ic h Judgement Indicat e s Potent i al Degradat ion in the Level ofSafety of the P lant I ]?_ DELTA-TWO ' .. I OR DELTA-ONE E vent s ar e in process or have occurred which indicate a potential degradat ion oftfi'e level of safety of the plant or in dicate a security threat to facility protection. No releases o f radioactive mater ial requi r ing offsite res po nse or monitoring are e xpect ed unless further degradat i on of sa fety systems occurs. 5. Explosion Within the Protected Area AREAS OF CONCERN FOR SAFE SHUTDOWN 2 6. Turbine Failure Causing Observ able Casing Damage Cont rol Ro om 7. Vessel or Vehicle Collision With Structures OR Equipment Requ ir ed Cable Vaults Sw i tchgear R oom s for Safe Shutdown or a lo ade d I SFS I Confinem en t Boundary Intake Structure Millstone

8. F lood Le ve l > 19 Feet Mean Sea L evel Turbine Build in g Switchgear Area Flood ing in Areas Containing Safe Shutdown Equ i pment Penetration Ar ea s Coolant Tanks Area 9. RBCCW Rooms Containment D i esel Generator Room DC Equipment and Batt ery R o oms Millstone Emergency Plan Charging Pump Cub icles S afety Injection Pump Rooms Revision 53 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 j Switchyard April 2016 I 4of 8 MILLSTONE 2 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE IMMINENT -N o Turnaround in Safety S ystem Performance is Expected AND Escalation to General Emergency Conditions Will Occur Within 2 Hours I INDICATORS FUEL CLAD BARRI E R RCS BARRI ER I FCB1 I I LOSS I I RCB1 I I LO SS I ::;AFETY FUNCTION Not Ap plicable Not Applicable STATUS/ I POTENTIAL LOSS I I I FUNCTIONAL POTENTIAL L OSS 0 Uncontrolled RCS Cooldown AND RCS Pressure-Temperature To RECOVERY the Left Of the PTS Limit 200° F S ubcool i ng Max i mum C urve 0 No RCS Heat R emoval Via S team Generators AND O nce Through Cooling NOT E ffective AND Shutdown Cooling 0 No RCS Heat Removal Via S team Generators

!lliQ Once Through System I s NOT In Serv i ce Cooling NOT Eff ective AND Sh utdown Cooling Sys te m Is NOT In Service I FCB2 I I LOSS I I RCB2 I I LOS S I CORE EXIT TC [IJ Core Exit Thermocouple Readings> 1200 °F ITJ RCS Subcool in g < 30°F TEMPERATURES I POTENTIAL LOSS I I I POTENT IA L LOSS 0 Core E xit Thermocouple Read ings> 700 °F Not Applicab le I RCB3 I I LOSS I Not Applicable I POTE NTIA L LOSS I PRESSURE 0 Uncontro lled RCS Pressure D ecrease and Increasing Conta i nment Rad i ation Monitors -I RCB4 I I LOSS I ITJ R eac tor Coolant Leak > CVCS Capacity A ND Entry Into EOP-2534, St eam Generator Tube R upture or EOP 2540, Funct ional Recovery , to Address S team Gen erato r Tube Rupture )OLA NT I POTE NTIA L LOSS I LEAKAGE 0 Reactor Coolant L eak > CVCS Capac i ty AND Entry Into EOP-2525 , Standard Post Trip Actions 0 Reactor Coolant Leak Rate..$_ CVCS Capacity AND EITHER of the following: . Entry Into EOP 2534, Steam Ge nerator Tube Rupt ur e . Entry Into EOP 2540 , Funct ional Recov ery, to Address Steam Generator Tube Rupture I FCB3 I I LOSS I I RCB5 I I LOSS I -[IJ R M-8 240/8241 Reading > 300 R/h r ITJ RM-8240/8241 Reading > 5 R/hr W ithout Fuel Clad [IJ RM-8240/8241 Reading> 5 R/hr Without RCS R elease Barrier Loss Inside CTMT *[IJ At L east 5% Fuel Clad Damage As Determined By Core Damage Estimate OR Samp le System D ose Rates Obta ined I POTENTIAL LOSS I Using CP 2802N, " Pr i mary System Samp li ng Analys i s" RADIATION [IJ Dose Rat e at One Foot from Unpre ssurized RCS Samp le Not Applicable z28 mR/hr/m l I POTENTIAL LOSS I Not Applicable I FCB4 I I LOSS I WATER Not App licable I I LEVEL POTENT IA L LOSS 0 RVLMS R eading = 0% with OPERABLE #8 string (NA if no OPERABLE #8 strinal I FCB5 I I RCB6 I Any Cond ition For Which Judgement Indi cates Loss or Potential Any Cond ition For Wh ich Judgement Ind i cates Lo ss or Potential Loss of Fuel Clad Barr ier Due to: Lo ss of RCS Barrier Due to: 1GEMEN T . Imminent Barr ier Degradation Based On Current Safety . Imm inent Barrier Degradation Based On Current Safety System Perform ance Sy stem Performance . Degraded Fission Barrier Monitoring Capability Making . Degraded F ission Barrier Monitoring Capability Making Bar rier Status Ind eterminat e Barrier Status I ndeterminate CTMT BARRIER I CNB1 I I LO SS I Not Applicable I POTE NTIAL LOSS I 0 Cor e ExitTC Temperature R eadings >1200°F AND Do NOT Decrease Within 15 M inutes I CNB2 I I LOSS I ITJ Rapid Une xplain ed CTMT Pressure Decrease Fo ll owing Initial Increase ITJ No CTMT Pressure Increase When Expectat i on Exists I POTE N T I AL LOSS I 0 CTMT Pressure > 10 PSIG !lliQ Inc reasing !lliQ No Conta i nment Spray Pump 0 CTM T H2 Concentration z 4% I C NB3 I I LOSS I [IJ Pr imary t o Secondary > Te ch Sp ec Limits and EITHER exists:

• Nonisolable Ste a m Re lease from A ffected S/G to environment . Prolonged R e l ease From Affected S/G to Env iron ment When Used for Coo l down (see basis for description of prolonged release) [IJ Leakage Through BOTH Isolation Valves AND a Pathway to the Env i ronment Exists Requiring Actions Outside the Contro l Room to I solate I POTENT IAL LOSS I 0 E ntry Into EOP-2532, Loss of Primary Coolant, AND Lea kage Exists Outside CTMT Requ iring Iso l ation From in s i de the C on trol Room I CNB4 I I LOSS I ITJ O ffsite Dose Plum e Rate z 1 o-6 Times RM-8240/8241 Read ing if R e lease is to CTMT I POTENTIAL LOSS I 0 RM-82 40/8241 Reading>1,200 A/h r [£] A t L east 20% Fuel Clad Dama ge A s Determined By Core D amage Estimate I CNB5 I I LOSS I [IJ No CTMT Sump Le vel Increase When Expectation E xists I POTENTIAL LOSS I Not Applicable I CNB6 I Any Cond iti on For Which Judgement Indicates Loss or Potent ial Loss of CTMT Barrier Due to: . I mminent Barrier Degradat io n Based On Cu rrent Safety System P erfor mance . Degraded Fission B arrier Monitoring Capability Mak i ng Barr ier Status Indeterm in ate THREE BARRIERS L p L p L p CLAD RCS CTMT 3/3 YES TWO BARRIERS L P L P L p CLAD RCS CTMT 2/3 MORE THAN ONE BARRIER AFFECTED EIYIERGENCY ALPHA --SITE AREA EMERGENCY TWO ONLY ONE BARRIER AFFECTED L p CLAD L p RCS 2 L p CTMT Millstone Millstone Emergency Plan Revision 53 April 2016 J-5 Of 8 ALERT ONE UNUSUAL EVENT DELTA-ONE MILLSTONE UNIT 3 EMERGENCY ACTION LEVELS D SITE AREA EMERGENCY D GENERAL EMERGENCY ALPHA D GENERAL EMERGENCY BRAVO CHARLIE-TWO D ALERT CHARLIE-ONE BARRIER FAILURE I ALL THREE BARRIERS See Barrier Failure Reference Table I FUEL CLAD OR RCS BARRIER I I Mode 1 , 2, 3 , 4 See Barrier Fa ilure Reference Tab le I BA2 I __

I Mode 1 , 2, 3, 4 Unisolable Steam Lin e Break Outside CTMT ___ c_T_M_T_B_A_R_Rl_E_R __ __.I I Mode 1 , 2 , 3 , 4 See Barrier Failure Reference Table ___ Rc_s_LE_A_KA_G_E __ ____.I ..... 1. Pressure Boundary Leakage > 1 O GPM 2. Unidentified Leakage > 1 o GPM 3. Identified Leakage > 25 GPM I FUEL CLAD DEGRADATION I ._I __ M_o_de_A_L_L _ _, 1. RCS Activity > 60 µCi/gm 1-131 DEQ 2. Dose Rate at One Foot from Unpressur ize d RCS Sample .?. 1 mR/hr/ml LOSS OF POWER §] ._I __ sT_A_T_IO_N_B_LA_C_K_o_u_T _ ___.I I Mode 1 , 2, 3, 4 Loss of Voltage on Buses 34C AND 34D (Station Blackout Diesel cannot be credited) AND ANY of the Following: Restoration of Power to AT LEAST One Bus is NOT Likely Within Four Hours Core Cooling -RED Heat Sink -RED AND Required Feedwater Flow Can NOT be Established Within 15 minutes LI __ s_T_A_T1_o_N_B_LA_c_K_o_u_T _ __.I I Mode 1 , 2 , 3, 4 Loss of Voltage on Buses 34C AND 34D > 15 Minutes (Stati on Blackout D ie sel cannot be credited) ..... I ___ Lo_s_s_o_F_Dc ___ _.I I Mode 1, 2 , 3 , 4 Loss of Voltage on DC Buses 1 , 2, 3 AND 4 > 15 Minutes / l...___s_T_A_T1_o_N_B_LA_C_K_o_UT __ _..I I Mode 5, 6 , o Loss of Voltage on Buses 34C 34D > 15 Minutes §] I SINGLE AC POWER SOURCE I I Mode 1, 2, 3, 4 Only One AC Power Source Ava ilable to Supply Buses 34C AND/OR 34D > 15 M in utes Such That Lo ss of That Power Source Would Result in a Station Blackout (Station Blackout Diesel CANNOT be Cred ite d) §] I LOSS OF OFFSITE POWER I ..... I __ Mo_d_e_A_L_L ___, Loss of all OFFSITE power to buses 34C AND 34D for> 15 Minutes ... l ___ Lo_s_s_o_F_Dc ___ __ _ _J Loss of Voltage on DC Buses 1, 2, 3 AND 4 > 15 Minutes NOTE: When two or more EAls apply , always choose the EAL of the highest incident classification; a l so always read from top to bottom in each category. EQUIPMENT FAILURE I ATWS/I NADEQUATE COOLING I ... I __ M_o_d_e_1 _ _.. Reactor Power> 5% Following Entry into FR-S.1 AND EITHER of the Following: Core Cooling -RED All SG Wide Range Levels < 21 % (24% Adverse CTMT) ____ A_TW_s ___ __.I ..... l __ M_o_d_e_1 _ _.. FR-S.1 is Enter ed Direct! From E-0 INABILITY TO MAINTAIN HOT S/D I Mode 1, 2 , 3, 4 1. Heat Sink* RED AND BOTH of the Following:

• Requ ired Feedwater F low Can NOT Be Es tablished With i n 15 Minutes
• RCS Bleed and Feed Can NOT Be Es tablished

2. RCS Boration Capability Unable to E liminate Inadvertent Criticality I IN-VESSEL FUEL UNCOVERY I I Mode 5, 6 AHR Has Been ANY of the Following Conditions E x ist: A l ternate Methods for Restoring RCS In ven tory Are NOT Effect ive RVLMS Reading Decreasing Toward 19% Level (Plenum) with OPERABLE 19% sensor (NA if no OPERABLE 19% sensor) CET Readin gs Ind icate Superheat Conditions

[}ill boss OF ANNUNCIATORS/TRAN SIENj I Mode 1, 2, 3, 4 Loss of Most (75%) MCB Annunciators AND BOTH of the Following:

• Significant Transient in Progress Loss of SPDS AN D ICC Instrumentation I AUTOMATIC RX TRIP FAILURE I ._I __ M_od_e_1_,_2 _ _, Failure of Automatic Reactor Manua l Trip Was Successful I EA2 I I INABILITY TO MAINTAIN COLDS/DI I Mode 5 , 6 1. Uncontrolled RCS Temperature Increase > 1 O ° F That Results in RCS Temperature

> 200 ° F 2. Inadvertent Criticality I EA 3 I boss OF ANNUNCIATORS/TRANSIENj Mode 1, 2 , 3, 4

• I Loss of Most (75%) MCB Annunciators

> 15 Minutes AND EITHER of the Fo llowing: S ignificant Transient in Progress L oss of SPDS AND ICC Instrumentation I LOSS OF COLD S/D FUNCTION I Mode 5 , 6 1. Loss of AHR Cooling > 15 Minutes Af!Q Valid PZR Water Level (LT 462) R eading < 40% 2. Uncontrolled RCS Temperature Increase> 10°F 3. RCS Boron Concentration < Minimum Required I CAVITY SEAL FAILURE II ..... _M_o_d_e_6_, 0--Refueling Cavity Seal Failure AND EITHER of the Following: Valid PZR Le vel (LT 462) Reading < 40% Valid SFP Le vel (LI 26) Reading = 0% Applies in Mode 0 when transfer gate is open. I LOSS OF ANNUNCATIROS II ..... _M_o_d_e-1,-2-, Loss of Most (75%) MCB AnntJnciators > 15 Minutes .tlliQ SPDS OR ICC Instruments Available I LOSS OF COMMUNICATIONS I ._l __ M_o_de_A_L_L _ _, 1. Loss of ALL Onsite E lectronic Communications Methods 2. Loss of ALL Electronic Communications Methods With Government Agencies I SHUTDOW N LCO EXCEEDED I I Mode 1 , 2 , 3, 4 Unit NOT Brought To Requ ire d Mode Within Applicable LCO Act ion Statement T ime Limits D UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE OFFSITE RELEASES loG1j ._l __ o_F_F_s_1T_E_D_o_sE __ L _M_o_de_A_L_L___.

1. MP3 Vent 0 MQnit()r O) Read_ing. _=::. 0.8 for >:*15 M l nutes . _ * * * * . * *. 2. MP3 SLCRS Monitor (3HVR*RE19)

Readin-g > 30 µCi/cc . fo'r > 15 Minutes * . *. * -:--** " -3. MP3 Safeties or Steam Dump Monito( . :. (3.MSS-RE75/76fn/78) Reading_=::.2bjiCiii:c for >15 MinUtes 4. Terry Monitor (3MSS-RE79) Reading.=::. 5 µCi/c c tor> 15 Minutes * * . . '

• 5. Plume c:iose Rate Onsite .:::.* 1,000 mR/hr
• for > 15 Min" utes * ' " 6. Rad Assessment Determi ne s Integrated Dose Offsite 2:. 1 TEDE m;i 2:. 5 Re" in COE Thyroid ... l __ o_F_F_s_IT_E_D_os_E

__ LI _M_o_de_A_L_L__.

1. MP3 Ventilation Vent Monitor (3HVR*R E 10) Read i ng_=::. 0.1 µCi/cc for > 15 Minutes 2. MP3 SLCRS Monitor (3HVR*RE 19) Re ading_=::.

10 µCi/cc for > 15 Minutes 3. MP3 Safeties or Steam Dump Monitor (3MSS-RE75/76m/78) Reading_=::. 0.8 µCi/cc for > 15 M i nutes 4. Terry Turbine Monitor (3MSS-RE79) Reading_=::. 1 µCi/cc for > 15 Minutes 5. Measured P l ume Dose Rate Ons it e _=::. 50 mR/hr for > 15 M in utes 6. Rad Assessment Determine s Integrated Dose Offsite .=::. 0.05 Rem TEDE OR_=::. 0.25 Rem CDE Th yroid loA1I Ll __ o_F_F_s_1T_E_D_os_E_. _ __.I LI _M_od_e_A_L_L__.

1. MP3 Ventilation Vent Monitor (3HVR*RE10)

Reading _=::. 0.01 µCi/cc for > 15 Minutes 2. . MP3 SLCRS Monitor (3HVR*RE 19) Reading_=::. 1 µCi/cc for > 15 Minutes 3. MP3 Safet i es or Steam Dump Monitor (3MSS-RE75/76m/78} Reading.=::. 0.0 8 µCi/cc for > 15 Minutes 4. Terry Turb in e Monitor (3MSS-RE79) Reading Of_=::. 0.1 µCi/cc for> 15 Minutes 5. Measured Plume Dos e Rate Onsite .=::. 5 mR/hr for > 15 Minutes 6. Rad Assessment Determ ines Integrated Dose Offsite _=::. 0.005 Rem TEDE OR_=::. 0.025 Rem CDE Thyroid CLASSIFICATION GENERAL EMERGENCY I ALPHA *I 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 offs l te for more than the . . SITE AREA EMERGENCY CHARLIE-TWO Events are in process or have occurred which involve an actual or likely major fa il ure 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 likelyfailure of or; (2) prevents effective access to equipment needed for the protection of the public. Any re l eases are not expected to result in exposure levels which exeed EPA Protect ive Act ion Gu i deline exposure levels beyond the site boundary. ALERT CHARLIE-ONE Events are in process or have occurred which involve an actual or potential substa ntial degradation of the le ve l of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equ i pment because of intentional ma l icious dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. UNUSUA L EVENT

• DELTA""" TWO -OR DELTA-ONE Events are in process or have occurred which ind i cate a potenti al degradat i on of the level of safety of the plant or indicate a segurity threat to facility protection.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. 3 Millstone Millstone Em erge ncy Plan Re vision 53 April 2016 1-6 of 8 MILLSTONE UNIT 3 EMERGENCY ACTION LEVELS G ENERAL EM ER GEN C Y AL P HA D S I TE AREA EMERGENCY 0 GENERAL EMERGENCY BRAV O CHARLIE-TW O D ALERT CHARLIE-O NE FI R E/GAS E S D UNUSUAL EVENT D ELTA-TW O JUDGEMENT D UNUSUAL EVENT-D ELTA-O NE I N -PLAN T RADIATION -I MAJOR FUEL DAMAGE I I Mode ALL 1. Sustained Valid .REo4 A/o5A Reading->

• R/hr. Read li'i g is Considered Sustaine*d Valid When the Effects of TIC -have dissipated. * * ' * -* 2. At t.:east *20% Fue i Clad Damage As Determined By Core D_amage Esti111ate

-, * , '. 3. Fuel.j s §Xpo , sed Wate r. t.:oss tr om Open Cavity; 9r SF Pool AND BOTH of the Following: -* -* 1' .. * }'

• Spent Fuel Has Decayed < 30 Days .l"
• Can Bypass C T MT . .,;.* *See Table 1 . _:>-r. __

S pent F uel is Expo s e d from O pe n V es s el, or C avity A N D BOT H of the F ollowing:

• Sp ent Fu el H as D ec a yed < 3 0 D ays
• C TM T I n t e gr i ty Estab lishe d I SP EN T F U EL AS SE MBLY DAM AG E I __ I S pent F uel is Ex p ose d from Op en Vessel, Cavity QB SF Po_ol AN D S pent Fu e l Has D ecayed,;::, 30 D ay s .!. F uel Handling A ccident Causing D amage to Spent Fu el , Indicated by Fu el Build i ng QB Co n tai n ment Radiatio n Mon i tors Inc r easin g I RA2 1 __ P_LA_N_T_RA_D l_AT_IO_N ___ I 1. Rad i a t i on R e ad i n g s > 1 5 mR/h r i n C o n trol R oom O R C entra l Al a rm S tatio n OR S ec on dary Al arm St atio n 2. Radi a t ion R e a din g > 5 R/hr in A r e as R e quir i n g Acc e ss f or Safe Shutd o wn ._l ___ RA_D_M_o_N_I T_O_R_s ___ I

1. Containment .QB F uel B uilding Area Rad Mon i tor Alarms I ndicate Cavity Seal Failure 2. Unexpected Ra d Monitor R eading O flscale H i gh OR > 1 000 Ti mes N o rm al R ea d i n g S E C U RI TY TH RE AT/ PH F NO MENA I SECURITY EVE N T I

___.I A HOSTILE FORCE has taken control of plant equipment such that plant personne l are unable to operate equipment required to ma itain safety functions. Any of the following meet this EAL: 1. Loss of Control Room 2. Loss of Remote Shutdown Panel 3. Security reports the loss or imminent loss of a Target Set OR A HOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT (for EALs) fuel damage is likely for a freshly off-loaded reactor core in pool. __ s_E_c_uR_ITY_E_V_E_ N T __ A n otification fro m t he s ite security force t h at an ar me d att ac k, ex p losive attack , airliner i mpact , or othe r HO S TIL E A C TI O N is oc c urring o r has occurred within the protected area. __ s_E_c_u_R_I TY_Ev_E_N_T ___ I __ I 1. Security E vents as determined for S tation S afeguards Contingency P lan and reported by S ecurity S hift S upervision. (Addresses events that involve Actual or P otential Substantial degradation to the level o f safety of the plant.) 2. A no@cation from the site security force that an armed attack , explosive attack, airliner impact, or othe r H OSTI L E AC T ION is occurring or has occurred within the OCA 3. A validated notification from the NRC of an airliner attack threat less than 30 minutes away. I TA2 I I DESTRUCTIVE PHEN O M E N A I I M ode A L L I 1. S eismic E vent > 0.09 g ZPA 2. O nsite S ustaine d Win d speed > 90 M PH 3. V isib l e D a m age to S tr u ctures or Eq uipment AN D Affecting Safe Shutdown 4. Vessel or V ehicle Collision AND Affec t in g Safe Shutdown -5. Missiles Affecting S afe Shutdown 6. F looding Affec t ing S afe Shutdown ._l __ s_E_c_u_R l_TY_E_V_E_N T __ _M_o_de_A_L_L___.I 1. S ecurity Conditio n as determined for S tation S afeguards Contingency P lan and reported by Security Shift Supervision. (Addresses events that involve P otential degradation in the level of safety of the plant.) 2. A cred i ble site specif i c security th r eat notification.

3. A val i dated not i f icatio n fro m the NRC p rovidi n g informa t ion o f an aircraft threa t. I D E S TRU CT IV E PH E N O M E NA I _M_o_d_e_A_LL __ j 1. S eismic Act ivity Detected Per AOP-3570, E arthquake

2. Report by P lant Personne l of Tornado Striking Wrth i n Protected Area 3. Visible Damage to Structures or Equipment Within the Protected Area 4. Onsite Sustained Windspeed

> 75 MPH 5. E xp los ion Within the Protected Area 6. Turb ine Failure Causing Observable Casing Damage 7. Vessel or Vehicle Collision With Structures or E quipment Required for S afe Shutdown or a Loaded ISFSI Confinement Boundary 8. F lood Level> 19.7 F eet Mean Sea Level 9. F looding in Areas Containing Safe Shutdown Equipment I NOTE: When two or more EALs apply , always choose the EAL of the highest incident classification; a lso always read from top to bottom i n each category. I l.__ __ _ __.ll _M_o_de_A_L_L___.I Other Conditions Exist For Which Judgemen t Indicates:

1. Actual Or Imminent Substantial Co r e Oegradation With Potential For Loss Of Containment, QR 2. Potential For Uncontrolled Radiological Releases.

These Releases Can Be Reasonably Expected To Exceed EPA PAG Plume Exposure Levels Outside The Site Bound a ry I C ON TROL ROO M E VA CUAT I O N I _M_o_de_A_L_L___.I l.__ __ J_UD_G_E_M_E_N_T_* _ __.I -M_o_de_A_L_L___.I U nit C ontrol fro m Auxiliary S hu td own P anel N OT Es ta b lished Within 15 Minutes After C ontrol Room Evacuation O the r C ondition s Exist F o r Which Judgeme nt Indica t e s Actu a l O r Likel y Major Fa ilures of P lant Func t ion s Nee d ed F or P rotecton Of T he P u b lic I C O N TRO L R OO M E V ACUA TI O N I ___ J_U_DG_E_M_E_N_T __ I Mo d eALL I C o n trol R oom E v a cua t ion Initiate d IG A2 1 ._l __ F_1R_E_IEX_PL_o_s_1 o_N __ _.ll __ I Fire o r Explosio n A ffecti n g S afe Shu td ow n Ar e a AN D D a mage to Str u ctures QB S a f e Shu t down E quipment Indicate d. I G A3 I I TO XI C FLA MM ABLE G A S E S I _M_o_d_e_A_LL __ j Li fe Th r e a tenin g To xic G a s e s QB Flamm able Gas Concent ratio ns as I de nti fied i n C-OP 2 0 0.5 , Oil , Haza r d o us M at eri a l, Hazard o us Was te a n d Mix ed Waste Cont in g e ncy P lan Affect i ng Areas for Sa f e S hut do wn A ny C ondition F or Which Judgement Ind i cate s Th at Sa fety S yste ms May B e D eg raded A n d W h ich R eq uir es Em e r ge n cy R es p o n se O r g an ization S taffing ____ F_IR_E ___ ___.I _M_o_d_e_A_LL __ I .._I ___ J_U_DG_E_M_E_N_T __ _M_o_d e_A_L_L___,I

1. F ire in Buildings O R A reas Adjacent to A rea s Needed fo r S afe S hutdown N OT E xting u ished Within 15 Minutes of Control Room Notificat io n OR Verification of Control Room Alarms 2. Fire a ffecting a loaded I SFSI co n fin e ment bounda ry N OT exti n g u is he d w it h i n 15 m inu t es I G U 2 I I TO XI C/FLAM M ABLE GASES I l,....._M_o_d_e_A-LL---.1

1. Life T hreatening T oxic G ases O R F lammable G a s Concentrati o n s as Iden t ified in C-O P 200.5, O il, H azardous Material, Haz a rdous Waste and Mixed Waste C ontingency Plan Affect in g Normal Operation

2. Notification of a Near-Site Release T hat May R equire Evacuation I A ny C ondi t ion F o r Wh i c h Judg e m ent I n di c a tes P o t e n tial D egr ad ation in t he L eve l of S afety o f the Pl a n t AREA S O F CONCERN FOR SAFE SHUTDOWN C on ta i nm en t B uil ding Au x il i ary Bu il d ing Co nt ro l Bu i ld i ng Mai n Steam Va l v e Building D e m i nerali zed Water S t orag e Tan k ESF B uilding Int a ke S t ru ct ure S tation Tra n sfor m ers E mergency G e n e r ator E nclosure F uel B u il d ing C LASSI F I CAT IO N GE N ERAL E M ERGE N C Y ALPHA OR BRAVO Events are i n process or have occurred which Involve actu a l or i mm i n e nt substan ti al core degrada ti on or melting with po t ential for lo s s of conta i nment i nteg ri ty or secur i ty ev e nts tha t r e sult in an ac t u al lo s s of p h ys i ca l cont r ol of the f acili ty. Re l eases ca n be reasonab l y exp e c t ed to e x ce e d EPA Protect i ve Action Guidel i ne e x posure le v els offsite for more than the Immediate site a r ea . S IT E AREA E M ERGE NCY CHARLIE-TWO E vents are in process or have occurred which involve an actual or likely major failure of plant functions needed for protection of the p ublic or sec ur ity events that r esult in intentional damage or malic i ous acts; (1) t oward site personnel or equipment that could l ead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the p u blic. Any releases are not expected to result in exposure levels which exeed E PA Protective Action Guideline exposure levels beyond the site boundary. ALERT CHARLIE-ONE E vents are in process o r 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 equ i pment because of inte n tional m alicious dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA P ro t ective Action G l!_ideline exposure lev e l s. I UNU S UAL E VENT I k-CC* I DELTA ,,, WO OR DELTA-ONE Events are i n p r o cess or have ,gccur r e d which indicate a potential degradation of the lev e l of safety of the plant or indicate a security threat to facility prote ct ion. No releases o f radioactiv e material requi r ing offsite response or monitoring are expected unless further degradation of safety 3 Millstone Mi ll stone Eme r gency P lan R evisio n 5 3 April 2016 I 7 of 8 MILLSTONE 3 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE IlVlMINENT

-No Turnaround in Safety System Performance is E x pected AND Escalation to G ene ral Emergency Conditions Will Occur Within 2 Hours INDICATORS FUEL CLAD BARRIER RCS BARRIER I FCB1 I I LOSS I I RCB1 I I LOSS I IT] Core Co oling -RED Not Applicable I PO T ENT IA L LOSS I I POTE N TI A L LOSS I 0 STATUS TREES Core Cooling -ORANGE 0 H eat Sin k -RED AND BOTH of t he Foll owing: 0 RCS Integrity -RED . Requ ired F eedwate r F low Can NOT B e E stablished Within 15 Minutes 0 H ea t S ink -RED AND R equired F eedwater F low Can . RCS Bleed and F eed Can NOT B e E stablished NO T B e E stablished Within 15 Minutes I FCB 2 I I LOSS I I RCB2 I I LOSS I IT] Core E xit TC Temp e ratures > 1200 ° F [TI RCS Subcooling < 32 ° F D ue to RCS Leak (115°F CORE EXIT TC Adverse CTMT) I POTENTIAL LOSS I I I TEMPERATURES POTENTIAL LOSS 0 Not Applicable Core E xit T C Te mperatures > 718 °F I RCB3 I I LOSS I Not Applicable I POTENTIAL LOSS I PRESSURE 0 Uncontrolled RCS Pressure Decrease and Increasing Conta inment Radiation Mon itors -.. I RCB4 I I LOSS I cg En try I nto E-3, " S team G enerator Tube R upture" AND Reactor Coolant Leak > Ca pacity of One C harging Pump I POTENTIAL LOSS I GOO LANT 0 R eacto r Co o lant Leak > Capacity of One Charging Pump LEAKAGE AND ANY of the followi ng: . E n try into E-0 , " Reactor Trip or Safet y Inject io n" . E ntry into AOP 3555, " R eactor Coo la nt Le ak" . En try in to AOP 3576, " Steam Generator Tube Leak" 0 En try i nto E-3 , " Steam Generator Tube Rupture" AND Reactor C oolan t L eak ..:s. C apacny o f One Charging P ump I FCB3 I I LOSS I S ustained Va li d RE-04N05A Read ing >

• A/h r. R eadings are I RCB5 I I LOSS I considered sustained valid when the effects of TIC have diss ipa ted. [TI Susta i ned Valid RE-04/05A Reading > 5 R/h r W ithou t ITJ Sustained valid RE-04N05A Reading > 5 A/h r Without R C S F uel Clad Barrier Loss. Readings are considered Re lease Inside Containment.

R eadings are considered sustained valid when the effects of TIC have diss ipated. RADIATION sustained va li d when the effects of T IC have d issipate d. ITJ At Least 5% Fu el Clad Damage As Determined By Core I POTENTIAL LOSS I Damage Estimate ITJ Dose R ate at On e F oot from Unpressurized RCS Sample Not App lica ble 1!. 50 mR/hr/ml ITJ RE-41/42 Read ing >0.040 A/hr S/D or> 0.060 A/H r Fu ll Power for > 15 M in. Without RCS Re l ease Ins id e Containment I POTENT I AL LOS S I *S ee T able 1 Not Applicable WATER I FCB4 I I LOSS I LEVEL Not Applicable I POTENTIAL LOSS I 0 RVLMS ..:S. 19% (Plenum) with OPERABLE 19% sensor (NA if no OPERAB LE 19% sensor) I FCB5 I -I I RCB6 JUDGEMENT Any C ondition For Which Judgement Indicates Lo ss or Potential L oss Any Condition For Which Ju dgement I ndicates L oss o r P otential of Fue l Clad Barrier D ue to: Lo ss of RCS B arrier Due to: . Immine nt Barrier Degradation Based On Current Safety . Immine nt Barrier Degradation B ased On Curren t Sa fety System P erformance System Pe rformance . D egraded F ission Barri er Monitoring Capability Making Barr ier . Degraded F ission Barrier Monitoring C apability Making Status I ndet ermi nate Barrier Status Ind eterminate CTMT BARRIER I C N B1 I I LOSS I Not Appli c able I POTENT IA L LOSS I 0 Contai nm en t -RED I CNB 2 I I LOSS I Not App licable I POTENTIAL LOSS I 0 Entt In to FR-C.1 , R esponse to Inadeq uate Core Cooling , or FR-.2, Response to Degr ade d Co r e Co oli ng with RVLMS ..:s. 19% (P lenum) with OPERABLE 19% sensor (NA if no OPERABLE 19% sensor)AND Core Ex it TC Tempe ra ture s D o NOT D ecreas e With i n 15 M i nutes I CNB3 j I L OSS I cg R ap id Unexplained CTMT Pr essure De crease Following In itia l Increase cg No CTMT P ressure In crease When Expectation Exists I POTENTIAL LOSS I 0 CTMT Pressure 1!. 60 PSIA AND Increasing 0 CTMT H 2 C oncent r ation1!. 4% I CNB4 j I LOSS I cg Pr imary to Secondary > Tech S pec Lim its AN D EITHER e x i sts: . Nonisolab l e Steam R el ea se from Affecte d S/G to environment. . P rolonged Release F rom Affected S/G to E nvironment When Use d for Co oldown. (see basis for descript io n of prol on ged release) ITJ F ailu r e of BOTH Isolat io n Val ves AND a P athway to the Environment E xists cg Entry In to ECA-1.2, LOCA Outside Containment , Is Requ ire d AND Reactor Coo lan t L eakage is Verified I POTENTIAL LOSS I 0 E ntry Into ECA-1.2 , LOCA Ou ts ide Co n tai nment I CNB5 j I LOSS I cg Offsite D ose P lu me Ra te 1!. 5x1 o-6 T imes RE-0 4NRE-05A -R eading if Coolant Loss is to CTMT I POTENTIAL LOSS I 0 Su stained Va li d RE-04 N05 A Reading >

• A/hr. R eadings are considered sustained valid when the effects of TIC have dissipated.

0 At Least 20% Fuel Clad Damag e As De termine d B y Core D am age Es t ima te *See Tab le 1 I CNB6 I I LOSS I ITJ No CTMT Sump Leve l Inc rease When E xpectation Ex i sts I POTENTIAL LOSS I Not Applicable I CNB7 I A ny Condition F or Which Judgement Indicates Lo ss or Potential Loss of C TMT Ba rrier Due to: . Imminent Barrier D egradation Based O n Cu r rent S afety S ystem Performance . Degraded F ission B arrier Monitoring Capability Making Barr ie r S tatus Indeterm inate MORE THAN ONE BARRIER AFFECTED GENERAL __ .\ ALP-HA *

t" SITE AREA EMERGENCY ONLY ONE BARRIER AFFECTED L p CLAD Time After Shutdown (hr s) ..

s.2 > 2to 4 > 4 to 12 > 12 Table 1 FCB3 ALERT ONE UNUSUAL EVENT DELTA-ONE CNB5/RG1 Fuel Clad L o ss Threshold Containment L o s s Threshold (R/hr) 200 125 50 25 3 Millstone M ills tone Emergency P lan Rev isi on 53 Ap r il 2016 1-8 Of 8 (R/hr) 800 500 200 100 AppendixJ APPENDIXJ EVACUATION TIME ESTIMATE PLUME EXPOSURE PATHWAY J-1 Millstone Station Emergency Plan Revision 53 April 2016 AppendixJ Estimates for Evacuation of the Plume Exposure EPZ The following tables sumrriarize 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. population estimates are based on the 2010 U.S. Census bl()ck 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. A 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 :p.etwork. J-2 Millstone Station Emergency Plan Revision 53 April2016 ... w s r-r > "C < g C'l i::: 6"'< =i ::s ,__ Ul 0\ w =i Region I Affecl2d Zone-s Swnmer MJdwlf1.e]c Midday Good Weather I !Rain* Summer WeekA;!nd Midday Good Weather I 1iaJn Summer Midweek Weekend Winter Mldwli!lelk:

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c. Shqdowfl'opulation information.

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Fadlit,le$ bQl:h medlcil l fa dll tles a n d fadlltles. AppendixK APPENDIXK SERO PERSONNEL TRAINING

SUMMARY

K-1 Millstone Station Emergency Plan Revision 53 April2016 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 (TPG) 7.212. In addition, EPA-FAPOl defines specific training requirements. See Reference

1. 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-26-training drill, facility walk-through or on-the-job training. EPA-FAPOl 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. --.*----* -Pr o vi d e fa miliarization training on the evenL .. c,: * '.

• _._-,
• 7 -----.-... -.. ,_.., ... .... . . Identify l\TRC initiatives in the area of accideni:. .. 1\cl iJ.. 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 14 the State of Connecticut. Provide training for performance of on-shift radiological dose calculations using 15 computer programs. K-2 Millstone Station Emergency Plan Revision 53 April 2016}}