Text

Emergency Plan, Revision 14-3
	ML14276A316
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/17/2014
From:	Capps S; Duke Energy Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	MNS-14-072, FOIA/PA-2015-0025
	Download: ML14276A316 (75)
	v • d • e

Steven D. Capps (DUKEENERGY. Vice President McGuire Nuclear Station Duke Energy MGO1VP 1 12700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com September 17, 2014 10 CFR 50.54(q)

Serial No: MNS-14-072 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001

Subject:

Duke Energy Carolinas, LLC McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369, 50-370 Emergency Plan, Revision 14-3 Please find attached Revision 14-3 to the McGuire Nuclear Station Emergency Plan. This revision is submitted in accordance with the requirements of 10 CFR 50.54(q) and does not result in a reduction in the effectiveness of the Emergency Plan or the Emergency Plan Implementing Procedures.

Questions regarding this submittal should be directed to Kay Crane, McGuire Regulatory Affairs, at (980) 875-4306.

ýSteven D( ;Ca ps Attachments www.duke-energy.com

U. S. Nuclear Regulatory Commission September 17, 2014 Page 2 (Two Copies) cc: Mr. V.M. McCree, Regional Administrator, Region II U. S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 (One Copy)

Mr. E. William Brach, Director Office of Nuclear Material Safety and Safeguards Mail Stop T-8A23 Washington, D. C. 20555-0001 (w/o attachments)

Mr. G.E. Miller NRC Project Manager (McGuire)

U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08C2 11555 Rockville Pike Rockville, MD 20852-2738 Mr. John Zeiler NRC Senior Resident Inspector McGuire Nuclear Station

September 4, 2014 MEMORANDUM To: All Holders of the McGuire Emergency Plan

Subject:

McGuire Emergency Plan Enclosed please find Revision 14-3 to the McGuire Nuclear Site Emergency Plan. Refer to to complete the revision to the manual.

If there are any questions, please call me at 980-875-4672.

Sincerely, Kevin Murray 79t'4ý Emergency Preparedness Manager McGuire Nuclear Station KLM/jcm

Attachment:

Emergency Plan Revision cc: EP File 1502 eprevltr.doc

DUKE ENERGY McGUIRE NUCLEAR SITE EMERGENCY PLAN APPROVED: *Q %

SITE VICE PRESIDENT DATE APPROVED: q/1L,/&I REVISION 14-3: September, 2014 EFFECTIVE DATE: September , 2014 ORIGINAL DATE: August 25, 1980 Rev. 14-3 September, 2014

Attachment I September 4, 2014 Page 1 of 2 SECTION REMOVE PAGES INSERT PAGES Coversheet Revision 14-2 Revision 14-3 Emergency Plan Revision 14-2 Revision 14-3 Revision List List of Effective Complete Section, Rev. 14-2 Complete Section, Rev. 14-3 Pages (LOEP) Pages 1 thru 4 Pages 1 thru 4 List of Figures Complete Section Rev. 14-2 Complete Section, Rev. 14-3 Pages 1 thru 2 Pages 1 thru 2 Table of Contents Complete Section, Rev. 14-2 Complete Section, Rev. 14-3 Pages 1 thru 6 Pages 1 thru 6 Section A Complete Section, Rev. 14-2 Complete Section, Rev. 14-3 Pages Al thru 5 Pages Al thru 5 Section G Complete Section, Rev. 13-3 Complete Section, Rev. 14-3 Pages GI thru G4 Pages GI thru G4 Section P Complete Section, Rev. 14-1 Complete Section, Rev. 14-3 Pages P 1 thru P 10 Pages P1 thru P 10 Section Q Complete Section Rev. 14-2 Complete Section Rev. 14-3 Pages QI thru Q20 Pages Q1 thru Q20 Appendix 5 Agreement Letter #17, Rev. 11-2 Agreement Letter #17, Rev. 14-3 Pages 1 thru 5 Pages 1 thru 5

McGuire Emergency Plan List of Effective Pages Emergency Plan Approval Cover Sheet Coversheet Rev. 14-3 September, 2014 Emergency Plan Revision List Page 1 thru 2 Rev. 14-3 September, 2014 Table of Contents Page 1 thru 6 Rev. 14-3 September, 2014 List of Figures Page 1 thru 2 Rev. 14-3 September, 2014 Introduction Pages i-I thru i-7 Rev. 13-3 October, 2013 A. Assignment of Responsibility Pages A-I thru A-5 Rev. 14-3 September, 2014 B. Onsite Emergency Organization Pages B-I thru B-13 Rev. 14-2 June, 2014 C. Emergency Response Support & Resources Pages C-I thru C-2 Rev. 09-1 July, 2009 D. Emergency Class System/EAL Basis Document Pages D-1 thru D-83 Rev. 14-1 January, 2014 E. Notification Methods & Procedures Pages E-1 thru E-11 Rev. 12-1 May, 2012 Rev. 14-3 September, 2014

McGuire Emergency Plan List of Effective Pages F. Emergency Communications Pages F-i thru F-7 Rev. 06-2 September, 2006 G. Public Education & Information Pages G-1 thru G-4 Rev. 14-3 September, 2014 H. Emergency Facility & Equipment Pages H-I thru H-17 Rev. 14-2 June, 2014 I. Accident Assessment Pages I-1 thru 1-3 Rev. 12-1 May, 2012 J. Protected Response Pages J-1 thru J-22 Rev. 13-3 October, 2013 K. Radiological Exposure Control Pages K-I thru K-4 Rev. 00-3 November, 2000 L. Medical & Public Health Support Pages L- 1 thru L-2 Rev. 13-3 October, 2013 M. Recovery & Re-entry Planning Pages M- 1 thru M-5 Rev. 06-2 September, 2006 N. Exercises & Drills Pages N-I thru N-3 Rev. 10-2 November, 2010 Rev. 14-3 September, 2014

McGuire Emergency Plan List of Effective Pages

0. Radiological Emergency Response Training Pages 0-1 thru 0-2 Rev. 10-2 November, 2010 P. Development Periodic Review & Distribution of Emergency Plans Pages P-1 thru P-10 Rev. 14-3 September, 2014

0. Appendices 1-4 Pages Q-1 thru Q-15 Rev .14-3 September, 2014 Appendix 5 Agreement Letters Index - Page Q-16 Rev. 13-3 October, 2013 Agreement Letter 1 Rev. 13-1 March, 2013 Agreement Letter 2 Rev. 14-2 June, 2014 Agreement Letter 3 Rev. 14-2 June, 2014 Agreement Letter 4 Rev. 13-1 March, 2013 Agreement Letter 5 Rev. 00-1 (Deleted) May, 2000 Agreement Letter 6 Rev. 14-2 June, 2014 Agreement Letter 7 Rev. 14-2 June, 2014 Agreement Letter 8 Rev. 14-2 June, 2014 Agreement Letter 9 Rev. 14-2 June, 2014 Agreement Letter 10 Rev. 14-2 June, 2014 Agreement Letter 11 Rev. 14-2 June, 2014 Agreement Letter 12 Rev. 14-2 June, 2014 Agreement Letter 13 Rev. 14-2 June, 2014 Agreement Letter 14 Rev. 14-2 June, 2014, Agreement Letter 15 Rev. 13-3 October, 2013 Agreement Letter 16 Rev. 14-2 June, 2014 Agreement Letter 17 Rev. 14-3 September, 2014 Agreement Letter 18 Rev. 12-2 June, 2012 Agreement Letter 19 Rev. 12-2 June, 2012 Agreement Letter 20 Rev. 14-2 June, 2014 Agreement Letter 21 Rev. 12-2 June, 2012 Agreement Letter 22 Rev. 12-2 June, 2012 Agreement Letter 23 Rev. 14-2 June, 2014 Rev. 14-3 September, 2014

McGuire Emergency Plan List of Effective Pages Appendix 6 Emergency Plan Distribution Page Q-17 thru Q-20 Rev. 13-3 October, 2013 Appendix 7 SPCC Plan Coversheet Rev. 12-3 November, 2012 Table of Contents Rev. 12-3 November, 2012 Pages 1 thru 75 Rev. 12-3 November, 2012 Appendix 8 Hazardous Waste Contingency Plan Pages 1 thru 19 Rev. 13-1 March, 2013 Appendix 9 Hazardous Materials Response Plan Pages 1 thru 14 Rev. 13-3 October, 2013 Rev. 14-3 September, 2014

DUKE ENERGY COMPANY McGUIRE NUCLEAR SITE EMERGENCY PLAN REVISION LIST August 25, 1980 Date Issued Revision 37, March 1992 Change 1, October, 1980 Revision 92-1, August 1992 Change 2, February, 1981 Revision 92-2, October 1992 Change 3, June, 1981 Rev. 93-1, April 1993 Change 4, August, 1981 Rev. 93-2, June, 1993 Revision 1, November 16, 1981 Rev. 93-3, December 1993 Revision 2, February, .1982 Rev. 94-1, January, 1994 Revision 3, February, 1982 Rev. 94-2, June, 1994 Revision 4, April, 1982 Rev. 94-3, August 1994 Revision 5, June, 1982 Rev. 94-4, October 1994 Revision 6, July, 1982 Rev. 95-1, February 1995 Revision 7, September, 1982 Rev. 95-2, April 1995 Revision 8, November, 1982 Rev. 96-1, April 1996 Revision 9, January, 1983 Rev. 96-2, July 1996 Revision 10, February, 1983 Rev. 97-1, April 1997 Revision 11, June, 1983 Rev. 97-2, May 1997 Revision 12, November, 1983 Rev. 97-3, July, 1997 Revision 13, March, 1984 Rev. 98-1, January, 1998 Revision 14, August, 1984 Rev. 98-2, February, 1998 Revision 15, January, 1985 Rev. 98-3, May, 1998 Revision 16, March, 1985 Rev. 98-4, July, 1998 Revision 17, May, 1985 Rev. 98-5, August, 1998 Revision 18, November, 1985 Rev. 98-6, November, 1998 Revision 19, January, 1986 Rev. 99-1, March, 1999 Revision 20, July, 1986 Rev. 99-2, July, 1999 Revision 21, May, 1987 Rev. 99-3 November, 1999 Revision 22, June, 1987 Rev. 00-1, April, 2000 Revision 23, November, 1987 Rev. 00-2, May, 2000 Revision 24, March, 1988 Rev. 00-3, November, 2000 Revision 25, July, 1988 Rev. 01-1, January, 2001 Revision 26, July, 1989 Rev. 01-2, June, 2001 Revision 27, September, 1989 Rev. 02-1, March, 2002 Revision 28, October, 1989 Rev. 02-2, August, 2002 Revision 29, November, 1989 Rev. 03-1, April, 2003 Revision 30, March, 1990 Rev. 03-2, June, 2003 Revision 31, April, 1991 Rev. 04-1, February, 2004 Revision 32, July, 1991 Rev. 04-2, July, 2004 Revision 33, September, 1991 Rev. 05-1, July, 2005 Revision 34, October, 1991 Rev. 06-1, January, 2006 Revision 35, December, 1991 Rev. 06-2, September, 2006 Revision 36, January, 1992 Rev. 07-1, May, 2007 I

Rev. 14-3 September, 2014

Rev. 07-2, December, 2007 Rev. 08-1, September, 2008 Rev. 09-1, July, 2009 Rev. 09-2, December, 2009 Rev. 10-1, May, 2010 Rev. 10-2, November, 2010 Rev. 11-1, March, 2011 Rev. 11-2, August, 2011 Rev. 11-3, October, 2011 Rev. 12-1, May, 2012 Rev. 12-2, June, 2012 Rev. 12-3, November, 2012 Rev. 12-4, December, 2012 Rev. 13-1, March, 2013 Rev. 13-2, June, 2013 Rev. 13-3, October, 2013 Rev. 14-1, January, 2014 Rev. 14-2, June 2014 Rev. 14-3, September, 2014 2

Rev. 14-3 September, 2014

DUKE ENERGY MCGUIRE NUCLEAR SITE EMERGENCY PLAN Table of Contents Page #

i. Introduction A. Purpose i-3 B. Scope i-1 C. Planning Basis i-3 A. Assignment of Responsibility A. l.a Organization A-1 A.l.b Concept of Operations A-3 A. l.c Block Diagram Interrelationships A-3 A.l.d Key Decisionmaking A-3 A.l.e 24 Hour Emergency Response A-4 A.2.a Responsibility for and Functions of Emergency A-4 Response Organization A.2.b Legal Basis for Authority A-4 A.3 Agreement Letters for Emergency Response Support A-4 A.4 Individuals Responsible for Continuity of Resources A-5 B. On-site Emergency Organization B.I Plant Staff Under Emergency Conditions B-i B.2 Emergency Coordinator B-i B.3 Emergency Coordinator (line of succession) B-1 B.4 Functional Responsibilities of Emergency Coordinator B-2 B.5 Minimum Staffing Requirements B-2 B.6 On-site Functional Area Interfaces B-2 B.7 Augmented Support of On-site Emergency Organization B-2 B.8 Contractor and Private Organizations B-3 thru B-4 B.9 Local Agency Support Services B-4 B.9.a Law Enforcement, Emergency Traffic Control, Related B-4 Police Matters B.9.b Early Warning or Evacuation of the Populace B-5 B.9.c Radiological Emergency Monitoring Assistance B-5 B.9.d Hospitals, Medical Support B-5 B.9.e Ambulance Service B-5 B.9.f Fire-fighting B-5 B.9.g Public Health and Safety, Evaluation of the B-5 Radiological Situation B.9.h Local, State and Federal Support Responsibilities B-6 Rev. 14-3 September, 2014 1

Table of Contents Page #

C. Emergency Response Support and Resources C.l .a Individuals Authorized to Request Federal Assistance C-1 C. 1.b Federal Resources Arrival Time C-1 C. L.c Emergency Operations Facility Resources C-1 Available to Federal Response Organizations C.2.a State and County Representation at the Emergency C-1 Operations Facility (EOF)

C.2.b Licensee Representation at the Off-Site EOC's C-1 C.3 Radiological Laboratories-Availability and Capability C-2 C.4 Emergency Support From Other Organizations C-2 D. Emergency Classification System/EAL Basis Document Emergency Classification System/EAL D-I thru D-83 Basis Document E. Notification Methodology E. 1 Notification of Response Organization E- 1 E.2 Activation of Emergency Organization E-1 E.2.a Notification of Unusual Event E- 1 E.2.b Alert E-2 E.2.c Site Area Emergency E-4 E.2.d General Emergency E-6 E.3 Emergency Message Format (Initial) E-8 E.4 Emergency Message Format (Follow-up) E-9 E.5 State and Local Organizations-Disseminating Public E-9 Information E.6 Alert and Notification System E-9 E.7 Supporting Information for Public Information Message E-9 F. Emergency Communications F. L.a 24 Hour Notification Capability F-1 F. 1.b Communications With State/Local Governments F-1 F. 1.c Communications With Federal Organizations F-2 F. 1.d Communications Between Site, EOF, EOC's F-2 and Monitoring Team F. i.e Activation of Emergency Personnel F-2 F. i .f Communications Between NRC, EOC and F-2 Monitoring Teams F. 1.g ERDS Data Transfer F-2 F.2 Medical Support Communications F-3 F.3 Communications System Testing F-3 Rev. 14-3 September, 2014 2

Table of Contents Page #

G. Public Education and Information G. 1/G.2 Public Education and Information Program G-1 G.3.a News Group - Location and Contacts G-1 G.3.b News Group - Media Center G-1 G.4.a Public Spokesperson G-2 G.4.b Spokesperson Information Exchange G-2 G.4.c Rumor Control G-2 G.5 News Media Training Sessions G-2 H. Emergency Facilities and Equipment H.1 Technical Support Center/Operations Support Center H-1 H.l.a Control Room H-1 H.L.b Technical Support Center (TSC) H-1 H.l.c Operations Support Center (OSC) H-2 H.l.d Alternate Facilities H-2 H.2 Emergency Operations Facility (EOF) H-2 thru H-3 H.3 State and Local Government Emergency Operations Center H-4 H.4 Activation and Staffing H-4 H.5 Assessment Actions H-4 H.5.a Meteorological, Hydrologic and Seismic H-4 thru H-5 H.5.b Radiological Monitors H-6 H.5.c Plant Parameters H-6 H.5.d Fire Detection H-6 H.6 Data, Monitoring Equipment and Analysis Facilities H-6 H.7 Off-site Radiological Monitoring H-7 H.8 Meteorology Instrumentation and Procedures H-7 H.9 Operations Support Center H-7 H.10 Emergency Equipment/Instrumentation Inspection, H-7 Inventory, Operational Check, Calibration H.1I Emergency Kits H-7 H.12 Receipt and Analysis of Field Monitoring Data H-7 I. Accident Asse ssment 1.1 Emergency Action Level Procedures 1-1 1.2 On-site Capability and Resources to Provide Initial Values and Continuing Assessment I.2.a Post Accident Sampling 1-1 I-1 1.2.b Radiation and Effluent Monitors 1.2.c In-plant Iodine Instrumentation 1-2 1.3.a/ Method for Determining Release Source Term 1-2 I.3.b 1.4 Effluent Monitor Readings Vs On-site/Off-site Exposure 1-2 1.5 Meteorological Information Availability 1-2 I-2 1.6 Release Rates/Projected Doses for Offscale Instrumentation Rev. 14-3 September, 2014 3

Table of Contents Page 1.7/ Field Monitoring Within EPZ 1-3 1.8 1.9 Detect and Measure Radioiodine Concentration in the EPZ 1-3 1.10 Relationship Between Contamination Levels 1-3 and Integrated Dose/Dose Rates I.11 Plume Tracking 1-3 J. Protective Response J. L.a Onsite Alerting and Notification J-1 thru J.l.d J.2 Evacuation Routes and Transportation J-1 J.3 Personnel Monitoring J-1 J.4 Site Evacuation Procedures - Decontamination J-2 J.5 Personnel Accountability J-2 J.6 Protective Equipment Breathing Apparatus, Protective J-2 Clothing, KI J.7 Protective Action Recommendations J-3 J.8 Evacuation Time Estimates J-4 J.9 Implementing Protective Measures J-4 J. 10 Implementation of Protective Measures for Plume J-5 Exposure Pathway J. I0.a EPZ Maps J-6 J. 10.b EPZ Population Distribution Map J-6 J.10.c EPZ Population Alerting and Notification J-6 J. 10.d EPZ Protecting Immobile Persons J-6 J. 1O.e Use of Radioprotective Drugs for Persons in EPZ J-6 J. 10.f Conditions for Use of Radioprotective Drugs J-6 J. 10.g State/County Relocation Plans J-6 J. 1O.h Relocation Center Locations J-6 J. 10.i Evacuation Route - Traffic Capacities J-6 J. 10.j Evacuated Area Access Control J-6 J. 1O.k Planning for Contingencies in Evacuation J-6 J. 10.1 State/County Evacuation Time Estimates J-6 J. I0.m Bases for Protective Action Recommendations J-6 J. 11 Ingestion Pathway Planning J-7 J. 12 Relocation Center - Registering and Monitoring J-7 Rev. 14-3 September, 2014 4

Table of Contents Page K. Radiological Exposure Control K. 1 Onsite Exposure Guidelines K-1 K.2 Doses in Excess of 10CFR Part 20 K-1 K.3 Emergency Personnel Exposure and Records K-1 K.3.a Distribution of Dosimetry K-1 K.3.b Dose Records K-2 K.4 State/Local Plan for Authorizing Doses Exceeding PAG's K-2 K.5 Decontamination K-2 K.5.a Action Levels for Determining the Need for Decontamination K-2 K.5.b Radiological Decontamination K-2 K.6 Contamination Control Measures K-2 K.6.a Area Access Control K-2 K.6.b Drinking Water and Food Supplies K-2 K.6.c Recovery Efforts K-3 K.7 Decontamination of Personnel at Relocation K-3 Assembly Area L. Medical and Public Health Support L. 1 Hospital and Medical Support L-1 L.2 On-site First Aid Capability L-1 L.3 Public, Private, Military Hospitals, Emergency Medical L-1 Facilities L.4 Transport of Accident Victims L-2 M. Recovery and Reentry Planning and Post-Accident Operations M. 1 Recovery/Reentry Plans and Procedures M-1 M. L.a Outline of Site Recovery Plans M-1 M. 1 .b Outline of Recovery Plans M-2 M.2 Recovery Organization M-3 M.3 Information to Members of Recovery Organization M-4 M.4 Total Population Exposure Estimates M-4 N. Exercises and Drills N. l.a Exercises N-1 N.L.b Exercise Scenario/Response N-1 N.2 Drills N-1 N.2.a Communications N-1 N.2.b Fire Drills N-2 N.2.c Medical Emergency Drills N-2 N.2.d Radiological Monitoring Drills N-2 N.2.e Radiation Protection Drills N-2 N.3 Exercise and Drill Execution N-3 N.4 Exercise Critique N-3 N.5 Critique Action Items N-3 Rev. 14-3 September, 2014 5

Table of Contents Page #

0. Radiological Emergency Response Training 0.1 Offsite Agency Training 0-1

0. L.a Emergency Response Training (Offsite Agency) 0-1

0. .b Off-site Support Agency - Participation in Training 0-1 0.2 Site Organization Training 0-1 0.3 First Aid Training 0-1 0.4 Training For Radiological Emergency Response 0-2 Personnel 0.5 Training Period 0-2 P. Responsibility for the Planning Effort P. 1 Emergency Planning Staff Training P-1 P.2 Emergency Response Planning P-1 P.3 Site Emergency Planning Manager P-1 P.4 Review of Emergency Plan P-1 P.5 Distribution of Revised Plans P-1 P.6 Supporting Plans P-2 P.7 Implementing Procedures P-2 P.8 Table of Contents P-2 P.9 Audit of Emergency Plan P-2 P. 10 Telephone Number Updates P-3 Q. Appendices Index Q-1 Appendix 1 Definitions Q-2 Appendix 2 Meteorological Program Q-6 Appendix 3 Alert and Notification System Description Q-10 Appendix 4 Evacuation Time Estimates Q-15 Appendix 5 Agreement Letters Q-16 Appendix 6 McGuire Nuclear Site Emergency Plan Distribution Q-17 Appendix 7 SPCC Plan Appendix 8 Hazardous Waste Contingency Plan Appendix 9 Hazardous Materials Response Plan Rev. 14-3 September, 2014 6

LIST OF FIGURES FIGURE NO. TITLE PAGE #

i-i 10 Mile EPZ i-6 i-2 50 Mile EPZ i-7 A-1 Responsibility for Emergency Response Functions A-6 B-la Minimum On-Shift ERO Staffing Requirements for Emergencies B-7 B-lb Minimum Augmented ERO Staffing Requirements for Emergencies B-8&9 B-2 Site Emergency Organization B-10 B-3 EOF Organization - Minimum Staffing Requirements B-1I B-4 Inter-Relationships of Response Organizations - B-12 Unusual Event B-5 Inter-Relationships of Response Organizations - B-13 Alert, Site Area Emergency, General Emergency E-1 Emergency Notification E-10 F-i Emergency Communication Layout Prior to TSC/EOF Activation F-4 F-2 Emergency Communication Layout After TSC Activation, F-5 and During EOF Activation F-3 Emergency Response Radio System F-6 F-4 Emergency Operations Facility Communications F-7 G-1 Corporate Communications Initial Emergency Response Organization G-3 G-2 Corporate Communications Emergency Response Organization G-4 H-1 McGuire Nuclear Site Technical Support Center H-8 H-2 McGuire Nuclear Site Operations Support Center H-9 H-3 McGuire/Catawba/Oconee EOF General Location H-10 Rev. 14-3 I September, 2014

LIST OF FIGURES FIGURE NO. TITLE PAGE #

H-4 McGuire/Catawba/Oconee EOF Location H-11 H-5 McGuire/EOF General Arrangement H-12 H-6 Media Center H-13 H-7 Joint Information Center H-14 H-8 Generalized Met System H-15 H-9 Alternate TSC H-16 H-10 Alternate OSC H-17 J-1 Guidance for Offsite Protective Actions J-8 J-2 Description of Evacuation Regions J-1 1 J-3 MNS ETE Based on 2010 Census - 90% Effected Population J-13 J-4 MNS ETE Based on 2010 Census - 100% Effected Population J-17 J-5 Evacuation Route Map for MNS J-21 J-6 Summary of Population and Demand J-22 K-1 Emergency Workers Exposure Guidelines K-4 M-1 Recovery Organization M-5 P-1 Supporting Plans P-4 P-2 Emergency Plan Implementing Procedures P-5 thru P-8 P-3 Emergency Plan Implementing Procedures Distribution P-9 P-i0 2-1 Meteorological Parameters of the Upgraded System Q-9 Q-1 Siren Range in Feet Q-13 Q-2 Siren Locations Q-14 Rev. 14-3 2 September, 2014

A. Assinmrent of Responsibilitv Planning Objective To assure that State, Local, Federal, private sector, Duke Energy Corporate and McGuire Nuclear Site organizations that are part of the overall response organization within the McGuire Emergency Planning Zone are identified.

A. L.a Organization The principal organizations that are part of the overall response organization within the McGuire Emergency Planning Zone are listed below:

Federal NRC (Nuclear Regulatory Commission)

DHS (Department of Homeland Security)

DOE (Department of Energy)

FEMA (Federal Emergency Management Agency)

NOTE: NRC, DHS, and DOE will coordinate response of other Federal Agencies per the Federal Radiological Emergency Response Plan (FRERP).

North Carolina State N.C. Department of Public Safety, Division of Emergency Management (Note 2)

N.C. Department of Environmental Natural Resources, Division of Radiation Protection Local Government The county governments and municipal governments (within the counties) to include the emergency service departments and other agencies interrelated to these local governments within the 10-mile EPZ (plume exposure pathway) of McGuire Nuclear Site are:

Catawba Gaston Iredell Lincoln Mecklenburg The county governments (and municipal governments within the counties) to include the emergency service departments and other agencies interrelated to these local governments within a 50-mile EPZ (ingestion exposure pathway) of McGuire Nuclear Site are:

Rev. 14-3 A-1 September, 2014

-North Carolina (Note 1)

Alexander Davidson Rutherford Anson Davie Rowan Burke Gaston Stanly Cabarrus Iredell Union Caldwell Lincoln Wilkes Catawba Mecklenburg Yadkin Cleveland Montgomery

-South Carolina (Note 1)

Cherokee Chester Lancaster York Note 1: Agreement letters with these agencies are not a part of the McGuire Nuclear Site Emergency Plan unless specifically noted in A-3.

Note 2: This agency has the principle state responsibility for emergency response.

Private Sector The principal organizations in the private sector that are part of the overall response organization for the EPZ are:

Westinghouse Southern Bell Telephone Company The Independent Telephone Companies Radio and Television Stations Various Nuclear Support Vendors (e.g. Bartlett, GTS, Sun States)

Carolinas Medical Center Member's Southeastern Electric Exchange The Salvation Army The American Red Cross MEDIC Huntersville Fire Department Cornelius Volunteer Fire Department Non-Government Organizations INPO (Institute of Nuclear Power Operations), American Nuclear Insurers (ANI) and the NSSS supplier may be called upon for support as needed.

Rev. 14-3 A-2 September, 2014

A. 1.b Concept of Operations All emergencies or accident situations at the site are handled initially by the Operations Shift Manager. When an abnormal situation occurs, the Operations Shift Manager is able, utilizing site operating and emergency procedures and from background, training and experience, to determine if the abnormal situation is an emergency condition. During the course of the emergency condition and as response personnel are notified, and emergency centers are activated (OSC, TSC, EOF), the Operations Shift Manager is the person in charge, and assumes the functions of the Emergency Coordinator until the arrival of the Station Manager/Designee. When the Station Manager/Designee arrives and relieves the Operations Shift Manager of the Emergency Coordinator function, he/she becomes the person in charge or the decision maker. When the Emergency Operations Facility (EOF) is operational and activated, the EOF Director is responsible for company emergency response.

The Control Room at the site is the initial center for coordination of emergency response for all emergency conditions. For emergencies classified as Alert, Site Area Emergency and General Emergency, the Emergency Coordinator shall activate the Emergency Response Organization.

The TSC acts in support of the command and control function of the Control Room and provides an area for other site personnel who have expertise in all areas of plant operation to support the emergency condition. This facility is equipped with communication equipment, Operator Aid Computer (OAC) terminals, line printers, off-site and on-site computer access, plant drawings, procedures and other materials and equipment to support its function. Personnel in the TSC will be able to assess the accident condition and make responsible recommendations to the Control Room, the EOF and off-site agencies as necessary to provide for the safety of plant personnel and members of the general public.

As the EOF becomes operational and activated, it will assume many of the functions of the TSC and will rely on the TSC as a vital link to the site. The TSC will provide the EOF with up-to-date plant parameters, which will allow this facility to perform its assigned tasks.

The responsibility of the Control Room, TSC and EOF for the various emergency response functions is further detailed in Figure A-1.

A. 1.c Block Diagram of Organization Interrelationships See Figures B-la, B-lb, B-2, B-3, B-4 and B-5, Section B, "On-Site Emergency Organization" which describes the use of these figures.

A. 1.d Key Decision Making During the course of any emergency condition at McGuire, several persons have the potential to be "in charge" or to be the "Key Decision Maker". Prior to TSC activation and arrival of the Station Manager/Designee, the Operations Shift Manager assumes the Rev. 14-3 A-3 September, 2014

functions of the Emergency Coordinator at the Site and is in charge. When the Station Manager/Designee arrives on-site and assumes the Emergency Coordinator function, he/she becomes the person in charge of emergency response and becomes the key decision maker. After the EOF is operational and activated, the EOF Director is responsible for company emergency response.

A. i.e 24 Hour Emergency Response The McGuire Site emergency response organization beginning with the Control Room through the TSC is capable of responding to an emergency 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day, 7 days per week. Section E.2. describes the notification scheme within the site emergency response organization.

A.2.a Responsibility For and Functions of Emergency Response Organization (See State and County Plans)

A.2.b Legal Basis For Authority (See State and County Plans)

A.3 Agreement Letters For Emergency Response Support Appendix 5 contains letters of agreement with the following organizations:

Carolina's Medical Center Huntersville Volunteer Fire Department Cornelius Volunteer Fire Department Mecklenburg County Fire Marshall Mecklenburg Emergency Medical Services Agency (MEDIC)

Charlotte-Mecklenburg Emergency Management Office Iredell County Civil Preparedness Agency Lincoln County Department of Emergency Management Gaston County Department of Emergency Management Catawba County Department of Emergency Management Cabarrus County Department of Emergency Management REACTS DOE - Savannah River INPO - Fixed Nuclear Facility Voluntary Assistance Agreement North Carolina Letter Documenting Duke Energy Assumptions for Offsite Dose Calculation Methodology Duke Energy Back-Up TLD Reader Joint Information Center Alternate Site Agreement G&G Metal Fabrication, INC. Fire Equipment Services Division Lincoln Combustion Turbine Facility Charlotte Mecklenburg Police Department These Letters of Agreement shall be updated as necessary and at least once every three (3) years.

Rev. 14-3 A-4 September, 2014

A.4 Individual Resnonsible for Continuity of Resources The emergency response organization is capable of continuous (24 hour/day) operation for an extended period of time. The EOF Director is the individual responsible for assuring continuity of resources within the emergency response organization.

Figure A-I Responsibility for Emergency Response Functions Emergency Response Unusual Site Area General Functions Event Alert Emergency Emergency Supervision of reactor CR CR CR CR operations and manipulation of controls Management of plant CR(TSC) TSC TSC TSC operations Technical support to CR(TSC) TSC TSC TSC reactor operations Management of corporate CR(TSC) TSC/EOF TSC/EOF TSC/EOF emergency response resources Radiological effluent and CR(TSC) TSC/EOF TSC/EOF TSC/EOF environs monitoring, assessment, and dose projections Inform State and local CR(TSC) TSC/EOF TSC/EOF TSC/EOF emergency response organizations and make recommendations for public protective actions Management of recovery CR(TSC) TSC/EOF TSC/EOF TSC/EOF operations Technical support of CR(TSC) TSC/EOF TSC/EOF TSC/EOF recovery operations Note: (TSC) indicates that activation of this facility or the performance of this function is optional for the indicated emergency class.

Rev. 14-3 A-5 September, 2014

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 Activity Description and References MNS EPLAN Change 14-3, Sect. A BLOCK 1 Change and correct, typographically, references in Section A. 1.c, to correctly reflect "Onsite Emergency Organization" interrelationships depicted in Figures B-la, B-lb, B-2, B-3, B-4, and B-5 in Section B.

Activity Scope: BLOCK2 Z The activity is a change to the emergency plan

---]The activity Ls not a change to the emergency plan Change Type: I BLOCK3 Change Type: BLOCK4 Z The change is editorial or typographical L- The change does conform to an activity that has L-] The change is not editorial or typographical prior approval Li The change does not conform to an activity that has prior approval Planning Standard Impact Determination: BLOCK 5 Li §50.47(b)(1) - Assignment of Responsibility (Organization Control)

L--- §50.47(b)(2) - Onsite Emergency Organization Li §50.47(b)(3) - Emergency Response Support and Resources L §50.47(b)(4) - Emergency Classification System*

L §50.47(b)(5) - Notification Methods and Procedures*

L §50.47(b)(6) - Emergency Comnmunications Li §50.47(b)(7) - Public Education and Information Li §50.47(b)(8) - Emergency Facility and Equipment Li §50.47(b)(9) - Accident Assessment*

§50.47(b)(10) - Protective Response*

1i §50.47(b)(1 1)- Radiological Exposure Control

§50.47(b)(12) - Medical and Public Health Support Li §50.47(b)(1 3) - Recovery Planning and Post-accident Operations Li]§50.47(b)(14) - Drills and Exercises

§50.47(b)(15) - Emergency Responder Training L §50.47(b)(I 6) - Emergency Plan Maintenance

Risk Significant Planning Standards E]The proposed activity does not impact a Planning Standard Commitment Impact Determination: I BLOCK 6 Revision 12 I

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 E-- The activity does involve a site specific EP conmmitment Record the colmnitment or commitment reference:

--] The activity does not involve a site specific EP commitment lesults: BLOCK 7 LII The activity can be implemented without performing a §50.54(q) effectiveness evaluation The activity cannot be implemented without performing a §50.54(q) effectiveness evaluation

'P~prer,) f.........Date:

Preparer Namne:

Renardd p Burrs ..... ..*. *re.......................................................

.*..................r

....... . . . . . . . 8/26/1 Rev*ieer Name: Rev* e S' ature Date-7t0&ry GI SD K Revision 12 2

G. Public Education and Information Information will be made available to the public on a yearly basis concerning notification of a nuclear plant emergency and the response that will be required from the public sector.

G.1/G.2 Public Education and Information Program On an annual basis, the licensee will update and distribute to residents within the plume exposure pathway emergency-planning zone, emergency-planning information concerning McGuire Nuclear Station. It will provide educational information on radiation, emergency planning contacts, protective actions, primary emergency alert system radio stations, evacuation routes, pick-up points for school children, reception centers, and information for residents with special needs. Local telephone numbers to call with questions will also be listed.

Public information for the transient population includes lake-access signs and emergency planning information. Transient locations will be identified by the Emergency Planning Manager/designee, the site Nuclear Communications staff, and state and county emergency management officials.

These locations may include but are not limited to motels, hotels, marinas, and lake access (signs).

The list of transient locations will be reviewed quarterly and updated as needed. Locations will be contacted periodically to ensure adequate copies of materials are available.

G.3.a Communications - Location and Contacts During a drill or emergency, public information at McGuire Nuclear Station will be coordinated and disseminated through the on-site media center located on Hagers Ferry Rd., Huntersville, N.C.

or the Joint Information Center (JIC) located in the Energy Center at 526 South Church Street, Charlotte, N. C. During initial stages of an emergency situation, response to media questions relative to plant status will be provided at the on-site media center. The Charlotte media center, also located in the Energy Center, will be activated as needed. The news release will indicate the location of the primary media center. The news manager and public spokesperson are the primary contacts for the news media.

If the Emergency Operations Facility (EOF) is not activated, the normal Duke Energy news release process is followed. If the EOF is activated, then Corporate Communications will activate the JIC, and the Standard Procedure for Corporate Communications Response to the Emergency Operations Facility (SR/O/A/2000/001) and the Nuclear Communications Emergency Response Plan (RP/O/A/5700/023) are implemented for gathering and disseminating information.

G.3.b Communications - Media Center In a nuclear plant emergency, the licensee relies on the news media to provide prompt, accurate information to local residents and the public. To provide ready access to current information on plant status, a media center is promptly established. An on-site media center will provide space for a limited number of media. A larger media center, located in the Energy Center at 526 South Church Street, Charlotte, NC (near the EOF) can be activated as needed to support additional media.

G-1 Rev. 14-3 September, 2014

G.4.a Public Spokesperson A public spokesperson will provide plant status and company information during scheduled news conferences and media briefings at a designated media center. Designated public spokespersons are the president of Duke Energy nuclear, the chief nuclear officer and his direct reports, and their designees.

G.4.b Spokesperson Information Exchange State, county and licensee spokespersons/public information officers are co-located in the Joint Information Center (JIC) to promote a timely exchange and coordination of emergency information. If the JIC is not activated, or if the state or counties do not send public information officers to the JIC, information will be shared via a Joint Information System (JIS) utilizing email, common shared platforms such as WebEOC, faxes or other communication vehicles agreed upon by the affected agencies.

G.4.c Rumor Control A licensee liaison will work with state, county, and federal public information officers in the JIC or via the JIS to acknowledge rumors and determine the origin. A coordinated response will be made to deal with rumors or correct misinformation.

Customer inquiries are handled by our Customer Contact Centers. Employees are updated via the company intranet/portal. Elected officials and regulatory agencies are updated through our Corporate Communications and governmental affairs departments. Industry groups would assist in disseminating]information to other industry groups.

G.5 News Media Training Sessions The licensee will annually provide the news media with information about emergency planning, radiation, and points of contact for release of public information in an emergency.

G-2 Rev. 14-3 September, 2014

FIGURE G-1 Corporate Communications Initial Emergency Response Organization HOUR ONE I For nuclear event, the nuclear communications duty team will also be notified immediately via pager/phone I

Corporate Communications Duty Person Nuclear

-notified by pager/phone Communications Duty Person Nuclear Public Information Manager Communications

& JIC Staff Manager

-notified by phone/pager/Nuclear Callout Public Spokesperson e

ECOC

-notified via email/phone Duke Energy Nuclear Station Response notified wnagroup page/phone July 2013 ENERGY.

G-3 Rev. 14-3 September, 2014

FIGURE G-2 Corporate Communications Emergency Response Organization Va)ENERGY.

July 2013 Rev. 14-3 G-4 September, 2014

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 Activity Description and References MNS EPLAN Change 14-3, Sect. G BI OCK I Change and correct, editorially, procedure title to "Standard Procedure for Corporate Communications Response to the Emergency Operations Facility" and correct, editorially, procedure number to SR/O/A/2000/001.

Activity Scope: BLOCK2 ZThe activity is a change to the emergency plan

[:]The activity Ls not a change to the emergency plan Change Type: 1 BLOCK 3 Change Type: BLOCK 4 The change is editorial or typographical F-] The change does conform to an activity that has

]

-- The change is not editorial or typographical prior approval E-i The change does not conform to an activity that has prior approval Planning Standard Impact Determination: BLOCK 5

---] §50.47(b)(1) - Assignment of Responsibility (Organization Control)

D-- §50.47(b)(2) - Onsite Emergency Organization

§50.47(b)(3) - Emergency Response Support and Resources i

-- §50.47(b)(4) - Emergency Classification System*

D §50.47(b)(5) - Notification Methods and Procedures*

L-] §50.47(b)(6) - Emergency Communications E-- §50.47(b)(7) - Public Education and Information Z §50.47(b)(8) - Emergency Facility and Equipment I- §50.47(b)(9) - Accident Assessment*

rD §50.47(b)(10) - Protective Response*

D §50.47(b)(1 1) - Radiological Exposure Control E] §50.47(b)(12) - Medical and Public Health Support D §50.47(b)(13) - Recovery Planning and Post-accident Operations D§50.47(b)(14) - Drills and Exercises D §50.47(b)(1 5) - Emergency Responder Training L] §50.47(b)(16) - Emergency Plan Maintenance

Risk Significant Planning Standards

[The proposed activity does not impact a Planning Standard Commitment Impact Determination: BLOCK 6 Revision 12 I

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 Li The activity does involve a site specific EP conimitment Record the comnitment or commitment reference:

The activity does not involve a site specific EP commitment lesults: T BLOCK 7 M The activity can be implemented without performing a §50.54(q) effectiveness evaluation Li The activity cannot be implemented without performing a §50.54(q) effectiveness evaluation Preparer Name: ......

.... I.,..

.. Prture

.t....

Renard Burris . .............. 8/26/14

......... t e . .................................

.Da .........................

Rev' r Name: R gnare Date:

'f&V&Sr CtL /Iy Revision 12 2

P. RESPONSIBILITY FOR THE PLANNING EFFORT To assure that responsibilities for plan development, review and distribution of emergency plans are established and that the Emergency Planning staff are properly trained.

P. 1 Emergency Planning Staff Training Emergency Planning Group personnel will attend training/workshops, information exchange meetings with other licensees, and conferences held by industry and government agencies, as available, to maintain current knowledge of the overall planning effort. The Emergency Planning Manager is required to attend offsite training on an annual basis. This training will be documented in site Emergency Planning files or the Training group database (i.e. People Soft, etc.).

P.2 Emergency Response Planning The Site Vice President has the overall authority and responsibility for the Site Emergency Plan. This planning effort is delegated to the Emergency Planning Manager.

P.3 Site Emergency Planning Manager The Emergency Planning Manager has the overall authority and responsibility for site emergency response planning as well as the responsibility for the development and updating of the site Emergency Plan and coordination of this plan with other response organizations.

P.4 Review of Emergency Plan Review and updating of the site Emergency Plan and Emergency Plan Implementing Procedures shall be certified to be current on an annual basis. Any changes identified by drills and exercises shall be incorporated into the Site Emergency Plan.

On an annual basis, the Emergency Planning Manager will provide each state and local organization responsible for off-site activation and protective action decision-making, a copy of the nuclear site procedures appropriate for their area on emergency classification and notification. A response will be requested by letter within 30 days that a review has been completed with concurrence with the EAL's used for event classification and for protective action recommendations. If problem areas are identified, the Emergency Planning Manager will ensure resolution.

P.5 Distribution of Revised Plans The Emergency Plan and approved changes shall be forwarded to individuals and organizations listed in App. 6. Revised pages shall be dated and marked to show where changes have been made.

Rev. 14-3 P-1 September, 2014

P.6 Supporting Plans Figure P-1 gives a detailed listing of supporting plans to the McGuire Nuclear Site Emergency Plan.

P.7 Implementing Procedures Written procedures will be established, implemented, and maintained covering the activities associated with emergency plan implementation. Each procedure, and changes thereto, shall be reviewed and approved by the responsible implementing manager prior to implementation and shall be reviewed periodically as set forth in administrative procedures.

McGuire Emergency Plan Implementing Procedures are listed in Figure P-2 with a reference to the section of Emergency Plan implemented by each procedure. Figure P-3 contains the distribution list for McGuire Emergency Plan Implementing Procedures.

P.8 Table of Contents The McGuire Nuclear Site Emergency Plan contains a specific table of contents. The McGuire Nuclear Site Emergency Plan has been cross referenced to the applicable sections of NUREG-0654 Rev. 1.

P.9 Audit of Emergency Plan The Nuclear Safety Review Board Chairman will arrange for an independent review of McGuire Nuclear Station's Emergency Preparedness Program as necessary, based on an assessment against performance indicators, and as soon as reasonably practicable after a change occurs in personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but no longer than 12 months after the change. In any case, all elements of the emergency preparedness program will be reviewed at least once every 24 months. Guidance for performing the assessment against the performance indicators is provided in the Emergency Preparedness Administrative Procedure AD-EP-ALL-0001. The independent review will be conducted by the Nuclear Oversight - Audits and will include the following plans, procedures, training programs, drills/exercises, equipment, and State/local government interfaces:

1. McGuire Nuclear Site Emergency Plan and Implementing Procedures

2. State/Local Support Agency Training Program

3. Site Training Program

4. Public and Media Training/Awareness

5. Equipment - Communications, Monitoring, Meteorological, Public Alerting

6. State/Local Plan Interface Rev. 14-3 P-2 September, 2014

The review findings will be submitted to the appropriate corporate and nuclear site management. Appropriate portions of the review findings will be reported to the involved federal, state, and local organizations. The corporate or nuclear site management, as appropriate, will evaluate the findings affecting their area of responsibility and ensure effective corrective actions are taken. The result of the review, along with recommendations for improvements, will be documented and retained for a period of five years.

P.10 Telephone Number Ut3dates Telephone numbers reflected in the online organization charts will be updated quarterly in accordance with PT/O/A/4600/091, Periodic Test of Technical Support Center Communications and Supplies.

Rev. 14-3 P-3 September, 2014

DUKE ENERGY MCGUIRE NUCLEAR SITE FIGURE P-I SUPPORTING PLANS

1. North Carolina Emergency Response Plan in support of McGuire Nuclear Site

2. South Carolina Operational Radiological Emergency Response Plan in support of Fixed Nuclear Facilities (McGuire Nuclear Site)

3. Iredell County, N.C., Radiological Emergency Response Plan in Support of the McGuire Nuclear Site

4. Mecklenburg County, N.C., Radiological Emergency Response Plan in Support of the McGuire Nuclear Site

5. Gaston County, N.C., Radiological Emergency Response Plan in Support of the McGuire Nuclear Site

6. Lincoln County, N.C., Radiological Emergency Response Plan in Support of the McGuire Nuclear Site

7. Catawba County, N.C., Radiological Emergency Response Plan in Support of the McGuire Nuclear Site

8. Cabarrus County, N.C., Radiological Emergency Response Plan in Support of the McGuire Nuclear Site

9. Emergency Response Plan, Water Reactors Division, Westinghouse Electric Corporation

10. N.R.C. Region II Incident Response Plan

11. Interagency Radiological Assistance Plan - Region 3 - U.S. Department of Energy

12. INPO Emergency Response Plan Rev. 14-3 P-4 September, 2014

MCGUIRE FIGURE P-2 PAGE 1 OF 4 EMERGENCY PLAN IMPLEMENTING PROCEDURES Procedure # Title Emergency Plan Section Implemented AP/O/A/5500/047 Security Events (Proprietary Info) Section J RP/O/A/5700/000 Classification of Emergency Section D, E, I RP/O/A/5700/001 Notification of Unusual Event Section D, E, 1.1, J.7 RP/O/A/5700/002 Alert Section D, E, 1.1, J.7 RP/O/A/5700/003 Site Area Emergency Section D, E, 1.1, J.7, M. 1 RP/O/A/5700/004 General Emergency Section D, E, 1.1, J.7, M.1 RP/O/A/5700/006 Natural Disasters Section D RP/O/A/5700/007 Earthquake Section D, H.6 RP/O/A/5700/008 Release of Toxic or Flammable Gases Section D RP/O/A/5700/09 Collisions/Explosions Section D RP/O/A/5700/010 NRC Immediate Notification Section D RP/O/A/5700/011 Conducting a Site Assembly, Site Evacuation or Section E.2, J, K.7 Containment Evacuation RP/O/A/5700/012 Activation of the Technical Support Center (TSC) Section B, H, M.1 Rev. 14-3 P-5 September, 2014

MCGUIRE FIGURE P-2 PAGE 2 OF 4 EMERGENCY PLAN IMPLEMENTING PROCEDURES Procedure # Title Emergency Plan Section Implemented RP/O/A/5700/018 Notifications to the State and Section E Counties from the TSC RP/O/A/5700/019 Core Damage Assessment RP/O/A/5700/020 Activation of the Operations Support Center (OSC) Section H RP/O/A/5700/022 Spill/Incident Response Procedure Appendices 7, 8, 9 RP/O/A/5700/024 Recovery and Reentry Section M RP/O/A/5700/026 Operations/Engineering Required Actions in the Technical Support Center (TSC)

RP/0/B/5700/023 Nuclear Communications Emergency Response Section G Plan RP/0/B/5700/029 Notifications to Offsite Agencies from the Control Section E Room HP/0/B/1009/002 Alternative Methods for Determining Dose Rate Section D, 1.6 within the Reactor Building HP/0/B/1009/003 Recovery Plan Section M HP/0/B/1009/006 Procedure for Quantifying High Level Gaseous Section D, 1.3 Radioactivity Release During Accident Conditions Rev. 14-3 P-6 September, 2014

MCGUIRE FIGURE P-2 PAGE 3 OF 4 EMERGENCY PLAN IMPLEMENTING PROCEDURES Procedure # Title Emergency Plan Section Implemented HP/0/B/1009/010 Releases of Liquid Radioactive Materials Section D, 1.3 Exceeding Selected Licensee Commitments HP/0/13/1009/021 Estimating Food Chain Doses Under Post-Accident 1.10 Conditions HP/0/B/1009/022 Accident and Emergency Response Section I, Section E HP/0/B/1009/023 Environmental Monitoring for Emergency Section E, 1.7, 1.8, 1.9 Conditions HP/0/B 1009/024 Personnel Monitoring for Emergency Conditions J.3, K.7 Rev. 14-3 P-7 September, 2014

MCGUIRE FIGURE P-2 PAGE 4 OF 4 EMERGENCY PLAN IMPLEMENTING PROCEDURES Procedure # Title Emergency Plan Section Implemented HP/0/B/1009/029 Initial Response On-Shift Dose Assessment Section 1.3.aib SH/0/B/2005/001 Emergency Response Offsite Dose Projections Section I SH/0/B/2005/002 Protocol for the Field Monitoring Coordinator Section 1.8 SH/O/B/2005/003 Distribution of Potassium Iodide Tablets in the J.6 Event of a Radioiodine Release SR/O/A/2000/001 Standard Procedure for Corporate Communications Section G Response to the Emergency Operations Facility SR/O/A/2000/003 Activation of the Emergency Operations Facility Section B, H, M.1 SR/O/A/2000/004 Notifications to States and Counties from the EOF Section E EP Manual Section 1.1 Emergency Organization Sections B, E, H PT/O/A/4600/088 Functional Check of Emergency Vehicle and Section H. 1I Equipment Rev. 14-3 P-8 September, 2014

FIGURE P-3 McGUIRE NUCLEAR SITE EMERGENCY PLAN IMPLEMENTING PROCEDURES DISTRIBUTION Control No.

2. Radiation Protection Manager

3. Emergency Planning Manager, Oconee

4. McGuire Nuclear Training

5. Operations Staff Manager

6. Site Emergency Planner, MGO1EP

7. NRC Site Representative, McGuire Nuclear Site (forwarded by McGuire Emergency Planning)

8. Operator Training Director

13. Emergency Planning Manager, CNS

14. Director, Division of Radiation Protection

16. NCEM REP Program Manager

17. Tina Kuhr, Emergency Planning Consultant/NSRB Staff

19. Emergency Operations Facility, EOF Director's Area (MNS Emergency Planning, custodians)

20. McGuire Nuclear Site, Document Control

21. NCEM Western Branch Office Manager

22. NRC Document Control Desk, Washington D.C. (forwarded 1 copy by McGuire Emergency Planning)

Rev. 14-3 P-9 September, 2014

FIGURE P-3 McGUIRE NUCLEAR SITE EMERGENCY PLAN IMPLEMENTING PROCEDURES DISTRIBUTION Control No.

23. NRC, Regional Administrator, Atlanta, GA (forwarded 1 copy by McGuire Emergency Planning)

24. NRC, Regional Administrator, Atlanta, GA (forwarded I copy by McGuire Emergency Planning)

25. NRC Office of Nuclear Materials Safety and Safeguards Rev. 14-3 P-10 September, 2014

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attaclunent 3.10.7.2 Activity Description and References MNS EPLAN Change 14-3, Sect. A BLOCK 1 Change and correct, typographically, procedure reference in Figure P-2 from SR/0/B/2000/001 to SR/0/A/2000/001.

Activity Scope: BLOCK 2

[7The activity is a change to the emergency plan

-The activity is not a change to the emergency plan Change Type: BLOCK3 Change Type: BLOCK4 The change is editorial or typographical E-] The change does conform to an activity that has The change is not editorial or typographical prior approval ElThe change does not conform to an activity that has prior approval Planning Standard Impact Determination: BLOCK5 El §50.47(b)(1) - Assignment of Responsibility (Organization Control)

[E] §50.47(b)(2) - Onsite Emergency Organization L-] §50.47(b)(3) - Emergency Response Support and Resources E §50.47(b)(4) - Emergency Classification System*

LII §50.47(b)(5) - Notification Methods and Procedures*

El §50.47(b)(6) - Emergency Communications El §50.47(b)(7) - Public Education and Information

§50.47(b)(8) - Emergency Facility and Equipment El §50.47(b)(9) - Accident Assessment*

El §50.47(b)(10) - Protective Response*

li]§50.47(b)(1 1) - Radiological Exposure Control

§50.47(b)(12) - Medical and Public Health Support El §50.47(b)(1 3) - Recovery Planning and Post-accident Operations

[l §50.47(b)(14) - Drills and Exercises

§50.47(b)(15) - Emergency Responder Training El §50.47(b)(16) - Emergency Plan Maintenance

Risk Significant Planning Standards E-The proposed activity does not impact a Planning Standard Commitment Impact Determination: IBWCK-6:

Revision 12 I

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 F-j The activity does involve a site specific EP commitment Record the commitment or commitment reference:

- The activity does not involve a site specific EP cormmitment tesults: , BLOCK 7 M The activity can be implemented without performing a §50.54(q) effectiveness evaluation D The activity cannot be implemented without performing a §50.54(q) effectiveness evaluation Preparer Name: Date:

IA~3ature Renard Burris ............

. . .

n tueDate: ............................................................................................

DI ..................

/Re ........

Rev~wer Name:

V (?qd,---

/,3/,(

I I I Revision 12 2

DUKE ENERGY MCGUIRE NUCLEAR SITE APPENDIX INDEX Appendix 1 Definitions Appendix 2 Meteorological System Description Appendix 3 Alert and Notification System Description Appendix 4 Summary of Evacuation Time Estimates Appendix 5 Agreement Letters Appendix 6 Distribution List for McGuire Emergency Plan Appendix 7 Spill Prevention Control and Countermeasure Plan Appendix 8 McGuire Hazardous Waste Contingency Plan Appendix 9 Hazardous Materials Response Plan Q-1 Rev. 14-3 September, 2014

APPENDIX 1 1.0 DEFINITIONS AFFECTED PERSONS Persons who have received radiation exposure or have been physically injured as a result of an accident to a degree requiring special attention as individuals, e.g., decontamination, first aid or medical services.

ANNUAL For periodic emergency planning requirements, annual is defined as twelve months, with a maximum interval of 456 days.

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

BIENNIAL For periodic emergency planning requirements, biennial is defined as at least once every two years, with a maximum interval of 912 days. (Note that this does not apply to the scheduling of biennial exercises. An exercise can occur at any time during the second calendar year after the previous exercise.)

CORRECTIVE ACTIONS Emergency measures taken to ameliorate or terminate an emergency situation at or near the source of the problem to prevent an uncontrolled release of radioactive material or to reduce the magnitude of the release, e.g., shutting down equipment, fire-fighting, repair and damage control.

DEGRADING

" Plant parameters (ex. temperature, pressure, level, voltage, frequency) are trending unfavorably away from expected or desired values AND plant conditions could result in a higher classification or Protective Action Recommendation (PAR) before the next follow-up notification.

" Site conditions (ex. wind, ice/snow, ground tremors, hazardous/toxic/radioactive material leak, fire, security event) impacting plant operations or personnel safety are worsening AND plant conditions could result in a higher classification or Protective Action Recommendation (PAR) before the next follow-up notification.

DRILL A drill is a supervised instruction period aimed at testing, developing, and maintaining skills in a particular operation.

Q-2 Rev. 14-3 September, 2014

EMERGENCY ACTION LEVELS (EAL's)

A pre-determined, site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be: an instrument reading; an equipment status indicator; a measurable parameter (onsite or offsite); a discrete, or another phenomenon which, if it occurs, indicates entry into a particular emergency class.

EMERGENCY OPERATIONS FACILITY (EOF)

The Emergency Operations Facility is the facility utilized for direction and control of all emergency and recovery activities with emphasis on the coordination of off-site activities such as dispatching mobile emergency monitoring teams, communications with local, state and federal agencies, and coordination of corporate and other outside support.

EMERGENCY PLANNING ZONE (EPZ)

The area for which planning is needed to assure that prompt and effective actions can be taken to protect the public in the event of an accident. The plume exposure EPZ is about 10 miles in radius and the ingestion exposure EPZ is about 50 miles in radius.

EXCLUSION AREA The nuclear site property out to a radius of 2500 feet, that meets the 10CFR100 definition.

EXERCISE An exercise is an event that tests the integrated capability and a major portion of the basic elements existing within emergency preparedness plans and organizations.

IMPROVING

" Plant parameters (ex. temperature, pressure, level, voltage, frequency) are trending favorably toward expected or desired values AND plant conditions could result in a lower classification or emergency termination before the next follow-up notification.

" Site conditions (ex. wind, ice/snow, ground tremors, hazardous/toxic/radioactive material leak, fire, security event) have become less of a threat to plant operations or personnel safety AND plant conditions could result in a lower classification or emergency termination before the next follow-up notification.

INGESTION EXPOSURE PATHWAY The principle exposure from this pathway would be from ingestion of contaminated water or foods such as milk or fresh vegetables. The time of potential exposure could range in length from hours to months.

MONTHLY For periodic emergency planning requirements, monthly is defined as once each month, with a maximum interval of 38 days.

Q-3 Rev. 14-3 September, 2014

OPERATIONAL SUPPORT CENTER (OSC)

In the event of an emergency, shift support personnel (e.g., auxiliary operators and technicians) other than those required and allowed in the control room shall report to this center for further orders and assignment.

PLUME EXPOSURE PATHWAY The principle exposure sources from this pathway are (a) external exposure to gamma radiation from the plume and from deposited material and (b) inhalation exposure from the passing radioactive plume. The time of potential exposure could range from hours to days.

POPULATION-AT-RISK Those persons for whom protective actions are being or would be taken.

PROTECTED AREA An area encompassed by physical barriers and to which access is controlled.

PROTECTIVE ACTIONS Those emergency measures taken after an uncontrolled release of radioactive materials has occurred, for the purpose of preventing or minimizing radiological exposures to persons that would be likely to occur if the actions were not taken.

PROTECTIVE ACTION GUIDES (PAG)

Projected radiological dose or dose-commitment values to individuals in the general population that warrant protective action following a release of radioactive material. Protective actions would be warranted provided the reduction in individual dose expected to be achieved by carrying out the preventive action is not offset by excessive risks to individual safety in taking the protective action. The PAG does not include the dose that has unavoidably occurred prior to the assessment.

QUARTERLY For periodic emergency planning requirements, quarterly is defined as once every three months, with a maximum interval of 112 days.

RECOVERY ACTIONS Those actions taken after the emergency to restore affected property as nearly as practicable to its pre-emergency condition.

SEMI-ANNUAL For periodic emergency planning requirements, semi-annual is defined as once every 6 months, with a maximum interval of 228 days.

SITE That part of the nuclear site property consisting of the Reactor, Auxiliary, Turbine, Service Buildings and grounds, contained within the outer security area fence.

Q-4 Rev. 14-3 September, 2014

STABLE Plant conditions are neither degrading nor improving.

TECHNICAL SUPPORT CENTER (TSC)

This on-site center is for use by plant management, technical and engineering support personnel. In an emergency, this center shall be used for assessment of plant status and potential off-site impact in support of the control room command and control function.

TRIENNIAL For periodic emergency planning requirements, triennial is defined as at least once every three years, with maximum interval of 1369 days.

VITAL AREA Areas within the Protected Area that house equipment important for nuclear safety. Access to a Vital Area is allowed only if an individual has been authorized to be in that area per the Security plan, therefore Vital Area is a Security term.

WEEKLY For periodic emergency planning requirements, weekly is defined as once every 7 days, with a maximum interval of 9 days.

Q-5 Rev. 14-3 September, 2014

APPENDIX 2 MCGUIRE NUCLEAR SITE METEOROLOGICAL PROGRAM INTRODUCTION The meteorological program described in this appendix was developed using guidance provided by NUREG-0654, Revision 1, Regulatory Guide 1.23, Proposed Revision 1, Regulatory Guide 1.111, Revision 1, and Regulatory Guide 1.109.

EFFLUENT DISPERSION MODEL A computer model which simulates the transport and diffusion of released effluents is a puff-advection model which incorporates a horizontal wind field that can vary in time but is consistent in space. It is assumed in the puff-type model that the spread within a puff along the direction of flow is equal to the spread in the lateral direction (i.e., horizontal Gaussian Symmetry). In the model, concentration averages are obtained by summing concentrations of individual elements for the grid points over which the puffs pass. Features incorporated into the model include the use of primary, backup and predicted data, building wake effects and an assumed ground release mode. Appropriate persistence would be used for initial releases until a meteorologist is notified to provide predictive data.

INSTRUMENTATION Figure 2-1 shows the type and number of parameters measured at McGuire Nuclear Site. The meteorological conditions present at McGuire Nuclear Site warrant the use of the basic described meteorological variables. These include wind speed and wind direction measured at high and low levels, delta-temperature and sigma theta for stability classification, ambient air and dew point temperature and precipitation.

DATA HANDLING Meteorological data for dose calculation consists of a primary digital recording/storage system and a secondary analog chart recording system both of which meet system accuracies and other specifications as suggested in Regulatory Guide 1.23, Proposed Revision 1. In the digital system meteorological variables are sampled at varying time (1-60 seconds) intervals from which 15 minute total, average and/or standard deviation quantities are computed. Digital data is placed on an external PI server accessible to computers that are used for emergency effluent dispersion modeling and dose calculation. The chart recording system is maintained as a backup to the digital system.

DOSE ASSESSMENT METHODOLOGY Dose assessment is calculated through a dose projection computer model RADDOSE-V. The model provides for the assessment of off-site radiological doses and accommodates both real time and forecast modes in the calculation of exposures to the general public. The model provides results of the sum of the effective dose equivalent from external radiation (both plume and ground deposition) and Q-6 Rev. 14-3 September, 2014

the committed effective dose equivalent from the inhalation of radioisotopes (the sum of both factors equaling the total effective dose equivalent of TEDE), and the committed dose equivalent to the thyroid (CDE thyroid). Dose conversion factors are derived from Regulatory Guide 1.109.

The model uses source term (amount of radioactivity in the unit vent, containment and containment leakage or steam release valves), flow rates and real time meteorology to calculate doses. Unit vent grab sample analyses or unit vent radiation monitor readings are used to determine concentrations of radioactivity within the unit vent source term. Containment atmosphere samples, containment process radiation monitors or containment high range radiation monitors are used to determine concentrations within the containment source term. The containment design leak rate is used unless factors, such as containment pressure, indicate that another value is more realistic. Equivalent concentrations from a steam release are calculated by using known or assumed steam mass release rates and the specific steam line radiation monitor reading.

PHYSICAL SYSTEM DESCRIPTION Continuous parallel signals enter each Operator Aid Computer (OAC) and the analog recorders. The OAC calculates end to end 15 minute quantities, starting on the hour, for all meteorological variables (except sigma theta) with a sampling interval of 60 seconds. It calculates a 15 minute average for high and low level wind direction and speed; 15 minute averages are also calculated for delta-temperature, ambient temperature and dew point temperature. Total water equivalence is computed for precipitation. Sigma theta is calculated by a field unit with a sampling interval of one second again for end to end 15 minute periods starting on the hour, and then is fed to each OAC. All quantities are stored on the OAC with a minimum recall of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . This data is transferred to the MNS PI Server.

Data stored on the PI server is accessible to computers which are used for emergency effluent dispersion modeling and dose calculation DETAILED DESCRIPTION OF SUBSYSTEMS Sensors to Operator Aid Computer Lightning protection is provided for all sensors and signal conditioning equipment; wind sensors are outfitted with heating jackets, when necessary, for protection against icing conditions. Signal conditioners and the sigma theta field unit are housed in an environmentally controlled building at the base of the high level tower. Signal cables to the OACs and analog recorders are shielded to minimize electrical interference.

Q-7 Rev. 14-3 September, 2014

Operator Aid Computer (OAC) to MNS PI Server The process computer OAC system which is utilized for data storage consists of SAIC, HP and RTP equipment. Each unit OAC is a backup for the other, capable of supplying the same required meteorological values. The data is transferred to the MNS PI server which is the server used for long-term data storage and retrieval. Plant data on the PI server is accessible to computers that are used for emergency effluent dispersion modeling and dose calculation.

OUALITY ASSURANCE Meteorological components have been designed, procured and installed as a non-safety related system.

Equipment has been purchased from suppliers which have provided high quality, reliable products in the past. Surveillance during construction was provided as for any other non-safety system.

Q-8 Rev. 14-3 September, 2014

FIGURE 2-1 MCGUIRE NUCLEAR SITE METEOROLOGICAL PARAMETERS OF THE UPGRADED SYSTEM Measurement Existing high level and High level wind speed System 10 meter tower and direction Low level wind speed and direction Delta-temperature Low level sigma theta Dry bulb temperature Dew point Precipitation Q-9 Rev. 14-3 September, 2014

APPENDIX 3 DUKE ENERGY MCGUIRE NUCLEAR SITE ALERT AND NOTIFICATION SYSTEM DESCRIPTION GENERAL DESCRIPTION The Alert and Notification System for McGuire Nuclear Site consists of an acoustic alerting signal and notification of the public by commercial broadcast (EAS). The system is designed to meet the acceptance criteria of Section B of Appendix 3, NUREG-0654, FEMA-REP-1, Rev. 1.

The Emergency plans of Duke Energy, the State of North Carolina, and the counties of Mecklenburg, Gaston, Catawba, Lincoln, and Iredell include the organizations and individuals, by title, who will be responsible for decision-making as regards the alert and notification system. The county locations from which the sirens would be activated and, potentially, the request for an EAS message would come are manned 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day. Each organization's plan describes provisions for use of public communications media or other emergency instructions to members of the public. The plans of the state of North Carolina include a description of the information that would be communicated to the public under given circumstances.

A. Concept of Operations A system of 67 fixed sirens is installed and operational in the 10-mile EPZ around McGuire Nuclear Site. A backup means of alerting and notification is described in the State and County Plans. This backup method includes area-wide emergency service vehicles traversing the area and giving both an alerting signal and notification message.

Each county will control the activation of the sirens within its boundaries (except for Catawba County - their one siren will be activated by Lincoln County). However, Mecklenburg, as the lead county, has the ability to activate all EPZ sirens from its control point.

B. Criteria for Acceptance The alert and notification system for the McGuire Nuclear Site provides an alerting signal and an informational or instructional message to the population (via the EAS) on an area-wide basis throughout the 10-mile EPZ within 15 minutes from the time the cognizant off-site agencies have determined the need for such alerting exists. The emergency plans for the state of North Carolina (Annex E) include evidence of EAS preparation for emergency situations and the means for activating the system.

C. Physical Implementation

1. The activation of this alert and notification system requires procedures and relationships between both Duke Energy and the off-site agencies that support Duke and McGuire Q-10 Rev. 14-3 September, 2014

Nuclear Site. When an incident is determined to have reached the level requiring public protective actions, Duke contacts the cognizant off-site agency via the "selective signaling" phone system and provides its recommendations. This system is available for use 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per day and links the Control Room, TSC, EOF, SERT headquarters, the county warning points, and the county EOC's.

2. The expected performance of the sirens used in this system is described in Figure Q-1.

These sirens complement existing alerting systems. The ambient background sound level in the McGuire area is taken to be 50 db for areas of "less than 2000 persons/per square mile" and 60 db for areas above this density. On this basis, the siren coverages are designed to provide a signal 10db above the average daytime ambient background.

Furthermore, the sirens have been located to assure that the maximum sound levels received by any member of the public should be lower than 126 db.

The basis for selection of the 60 db(c) and 70 db(c) criteria is documented as follows:

Location of heavy industry - There is no "heavy industry" in the McGuire 10 mile EPZ.

Attenuation factors with distance - 10 db loss per distance doubled (See Figure Q-1)

Siren output db(c) at 100 ft. vs. assumed range and acoustic frequency spectra -

2001-AC: 126+ 1.0 db at 100 feet Assumed ranges per Figure Q-1, 10 db loss column Frequency Spectra:

2001-AC: top frequency 750 Hz Map showing siren location - See Figure Q-2 Mounting height of sirens - 50 feet (approximate)

Special weather condition considerations (such as expected heavy snow) - None The siren system will produce a 3 minute steady signal and is capable of repetition.

Q-1I Rev. 14-3 September, 2014

Test Program Periodic testing of the sirens is performed as follows:

Test Req'd By Min. Req'd Freq. Norm. Freq. Perf. By Duke Silent Test FEMA-REP- Every two weeks. Normally performed weekly 10,NUREG-0654 Rev. on Thursdays.

1, App. 3 Full Cycle Test (called FEMA-REP-10, Annually. Normally performed on the full-scale test by NUREG-0654 second Wednesday of each FEMA) Rev. 1, App. 3 quarter, or during the biennial exercise. See Note 1 below.

Growl Test FEMA-REP-10, Quarterly and after See NOTE I below for NUREG-0654 PM is performed. quarterly test.

Rev. 1, App. 3, See NOTE 4 below for FEMA CPG 1-17 growl test following PM.

March 1, 1980

{PIP-G-00-0135}

NOTE: 1. Quarterly full cycle tests fulfill/exceed the requirements for quarterly growl tests.

2. Each site may elect to perform some method of feedback system verification during the full cycle siren test.

3. For the FEMA CPG 1-17 growl test following PM, the siren chopper is sounded for a short period of time so that it never produces full sound output. {PIP G-00-0135}

Refer to FAM Section 3.3 for a detailed narrative of the siren test program.

Q-12 Rev. 14-3 September, 2014

FIGURE Q- 1 SIREN RANGE IN FEET 12 AND 10 dB LOSS PER DISTANCE DOUBLED MINIMUM LEVEL 2001AC COVERAGE 126dB(c)SIREN IN dB 12 10 85 1125 1830 80 1500 2600 75 2000 3680 73 2260 4210 70 2700 5200 68 3000 6000 65 3600 7400 60 4800 10400 Q-13 Rev. 14-3 September, 2014

0~

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&y

APPENDIX 4 DUKE ENERGY MCGUIRE NUCLEAR SITE EVACUATION TIME ESTIMATES DECEMBER 2012 The evacuation time estimates described in part J of this plan were prepared for McGuire by KLD Engineering, P.C. Report KLDTR-501, MNS, development of Evacuation Time Estimates, revision 1.

See MNS-ETE- 12132012-000, MNS Evacuation time Estimates (ETE) dated December 2012.

The purpose of the study was to update the permanent resident population count for the EPZ around McGuire Nuclear Site due to population growth.

The ETE Report has been made available to site, state, and local planners for their use.

Six scenarios were chosen to be studied and ETE listed is for entire EPZ:

1. Winter weekday, fair weather conditions. Estimated evacuation time is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 35 minutes.

2. Winter weeknight, fair weather conditions. Estimated evacuation time is 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 10 minutes.

3. Summer weekend, fair weather conditions. Estimated evacuation time is 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 30 minutes.

4. Winter weekday, adverse weather conditions. Estimated evacuation time is 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 40 minutes.

5. Winter weekend, adverse weather conditions. Estimated evacuation time is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 10 minutes.

6. Summer weekend, adverse weather conditions. Estimated evacuation time is 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 55 minutes.

The evacuation study is available in the MNS Emergency Planning office for study and review.

Q-15 Rev. 14-3 September, 2014

APPENDIX 5 AGREEMENT LETTERS The following agreement letters support the McGuire Nuclear Site Emergency Plan and are attached:

1. Carolinas Medical Center

2. Huntersville Fire Department

3. Cornelius Volunteer Fire Department

4. Mecklenburg County Fire Marshall

5. North Mecklenburg Rescue Squad (DELETED)

6. Mecklenburg Emergency Medical Services Agency (MEDIC)

7. Charlotte-Mecklenburg Emergency Management Office

8. Iredell County Civil Preparedness Agency

9. Lincoln County Department of Emergency Management

10. Gaston County Department of Emergency Management

11. Catawba County Department of Emergency Management

12. Cabarrus County Department of Emergency Management

13. REACTS

14. DOE - Savannah River

15. INPO

16. North Carolina

17. Letter Documenting Duke Energy Assumptions for Offsite Dose Calculation Methodology

18. Duke Energy Back-Up TLD Reader

19. Joint Information Center

20. Alternate Site Agreement

21. G & G Metal Fabrication (Hale pump repair vendor)

22. Duke's Lincoln Combustion Turbine Facility operating agreement with MNS/CNS/ONS on emergency supply of diesel fuel.

These Letters of Agreement are updated as necessary and at least every (3) years to ensure adequate awareness on the part of all concerned of the existence and commitment to provide agreed services or assistance.

Q-16 Rev. 14-3 September, 2014

APPENDIX 6 MCGUIRE NUCLEAR SITE EMERGENCY PLAN DISTRIBUTION NAME McGuire Nuclear Site Document Control, MG05DM Site Emergency Planner, MGO1EP Site Emergency Planner (TSC), MGO IEP Control Room, MGOIOP Operator Training Director, MG03OT Operations Staff Manager, MGO1 OP Operations Shift Manager, MGO1OP Radiation Protection Manager, MGO 1RP Satellite File, MGO1S I Environmental Management, MGO 1EM Regulatory Compliance, MG01RC EOF Director's Area McGuire Emergency Planning, MGO1EP NRC McGuire NRC Resident Inspector, MG01A NRC Regional Administrator (copy forwarded by Emer. Plan)

NRC Regional Administrator (copy forwarded by Emer. Plan)

NRC Document Control (copy forwarded by Emer. Plan)

NRC Office Of Nuclear Material Safety and Safeguards Emergency Planning Consultant/NSRB Staff E. M. Kuhr, EC05P News Group Emergency Planning Consultant, EC12X Catawba Nuclear Site CNS Emergency Planning Manager, CNO 1EP North Carolina Director, Division-of Environmental Health, Radiation Protection Section, Raleigh, NC NCEM REP Program Manager, Raleigh, NC NCEM Western Branch Office Manager, Conover, NC Cabarrus County Coordinator, Cabarrus County Dept. of Emergency Mgmt., Concord, NC Q-17 Rev. 14-3 September, 2014

APPENDIX 6 MCGUIRE NUCLEAR SITE EMERGENCY PLAN DISTRIBUTION Catawba County Catawba County Emergency Management Coordinator, Newton, NC Gaston County Coordinator, Gaston County Dept. of Emergency Mgmt., Gastonia, NC Iredell County Coordinator, Iredell County Civil Preparedness Agency, Statesville, NC Lincoln County Director, Lincoln County Emergency Services, Lincolnton, NC Mecklenburg County Director, Charlotte-Mecklenburg Emergency Mgmt. Office, Charlotte, NC Oconee Nuclear Site ONS Emergency Planning Manager, ON03EP Q-18 Rev. 14-3 September, 2014

APPENDIX 6 MCGUIRE NUCLEAR SITE EMERGENCY PLAN DISTRIBUTION (ADDRESSES)

Director Division of Environmental Health Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 REP Program Manager NC Division of Emergency Management 4713 Mail Service Center Raleigh, NC 27699-4713 Western Branch Office Manager NC Division of Emergency Management 3305-15 16th Ave. S.E.

Suite 305 Conover, NC 28613-9213 Coordinator Cabarrus County Department of Emergency Management P.O. Box 707 Concord, NC 28026-0707 Michael F Weber, Director Office of Nuclear Material Safety and Safeguards Mail Stop T-8A23 Washington DC, 20555-0001 Q-19 Rev. 14-3 September, 2014

APPENDIX 6 MCGUIRE NUCLEAR SITE EMERGENCY PLAN DISTRIBUTION (ADDRESSES Continued)

Emergency Management Coordinator Catawba County Administration Building 100-A South West Boulevard Post Office Box 389 Newton, NC 28658-0389 Coordinator Gaston County Department of Emergency Management Post Office Box 1578 1615 North Highland Street Gastonia, NC 28052 Coordinator Iredell County Civil Preparedness Agency Post Office Box 788 Statesville, NC 28677 Director Lincoln County Emergency Services 115 W. Main Street Lincolnton, NC 28092 Director Mecklenburg Emergency Management 228 East 9th Street Charlotte, NC 28202-2852 Q-20 Rev. 14-3 September, 2014

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 Activity Description and References MNS EPLAN Change 14-3, Sect. Q, Appendix 3 BLOCK I

Correct, typographically, unneeded spacing error in section C, Physical limitations,

Delete reference to a "Low-Growl" Test Program description.

Activity Scope: LBLOCK2

[*The activity is a change to the emergency plan D-The activity is not a change to the emergency plan Change Type: B Ck Change Type: BL .4 D The change is editorial or typographical The change is

[-1 The change does conform to an activity that has not editorial or typographical priorchange TtThe approval does not conform to an activity that has prior approval Planning Standard Impact Determination: BLOCK 5' Revision 12 I

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 L'- §50.47(b)(1) - Assignment of Responsibility (Organization Control)

§50.47(b)(2) - Onsite Emergency Organization

§50.47(b)(3) - Emergency Response Support and Resources LI §50.47(b)(4) - Emergency Classification System*

§50.47(b)(5) - Notification Methods and Procedures*

F-1 §50.47(b)(6) - Emergency Communications

§50.47(b)(7) - Public Education and Information LI §50.47(b)(8) - Emergency Facility and Equipment LI §50.47(b)(9) - Accident Assessment*

LI §50.47(b)(10) - Protective Response*

[I §50.47(b)(1 1) - Radiological Exposure Control LI §50.47(b)(12) - Medical and Public Health Support L-I §50.47(b)(13) - Recovery Planning and Post-accident Operations LI §50.47(b)(14) - Drills and Exercises I §50.47(b)(15) - Emergency Responder Training

§50.47(b)(16) - Emergency Plan Maintenance

Risk Significant Planning Standards MThe proposed activity does not impact a Planning Standard Although this change does not directly affect a Planning Standard this change is related to guidance in NUREG 0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Appendix 3, Means For Providing Prompt Alerting and Notification of Response Organizations and the Population, Section H, Siren Testing Guidance. Guidance in this document suggests that a Growl Test be performed quarterly and when preventive maintenance is performed. Per discussions with Larry Robertson, RAC Chair, FEMA Region IV, the intent of the FEMA guidance to perform a growl test following maintenance is to ensure that an adequate post-maintenance test is performed. This issue was evaluated and documented through the corrective action process at the station (PIP G-00-00135) in 2000. The following conclusions were reached based on that evaluation. The intent of the requirement for performing a growl test after maintenance is to ensure the siren is operable following maintenance.

Emergency Planning has developed Functional Area Manual Directive 3.3, "Alert and Notification System (Siren Program)." This manual section describes the Alert and Notification System (Siren Program) for the nuclear sites. This includes associated testing and maintenance processes of the system. This directive specifies the post-maintenance test requirements following annual preventive maintenance.

RC Preventive Maintenance (performed on radio equipment(

Perform remote tests from Toddville/Oconee - MDS diagnostics, silent, lo-growl.

These post-maintenance tests are considered to be adequate. This manual directive was approved by the EP BEST on June 26, 2000, and is being issued with a June 30, 2000 effective date.

Revision 12 2

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 Post Maintenance Checks for Annual Siren Preventive Maintenance (performed on BLOC 6 mechanical systems)

1. Repeat pre-operational checks (Section A) after preventive maintenance. (All models) EXCEPT ITEM B-6.

(Note: Item B-6 is where power to the siren is removed prior to maintenance.)

2. Test siren to assure operability.

3. Leave all switches in the automatic position.

4. Test siren from remote siren controller.

5. Lock and secure siren boxes (all siren models).

6. Notify county & Telecom that the siren is returned to service.

As such this change does not introduce a reduction in effectiveness in the capability or the function of the alert notification system to promptly alert the general public of a radiological event at the station as it does not change the frequency or overall effectiveness of system tests.

Commitment Impact Determination:

[I] The activity does involve a site specific EP commitment Record the commitment or commitment reference:

Z* The activity does not involve a site specific EP commitment Zesults: i BOK7-,

v, The activity can be implemented without performing a §50.54(q) effectiveness evaluation F- The activity cannot be implemented without performing a §50.54(q) effectiveness evaluation Pe*rep--*

-Na--.e.. ...

....... - r- ... ... . .......... .........

.*n [ ae Preparer Name: prep~i~ignature Date:

Renard Burris 8/26/14 Revjewr Namer

Revic g~tr Date:

Revision 12 3

Letter #17

DUKE Duke Energy

1. ENERGY. 526 South Church Street P.O. Box 1006 Charlotte, NC 28202 June 16, 2014 Mr. W. Lee Cox, Ill, Section Chief Division of Environmental Health, Radiation Protection Section North Carolina Department of Environment and Natural Resources 1645 Mail Service Center Raleigh, NC 27699-1645 Mr. Chris Stanton, Director Division of Waste Assessment and Emergency Response Bureau of Land and Waste Management South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 Barty Simonton, Acting Program Manager Environmental Compliance Specialist Environmental Radiation Program Air Protection Branch Environmental Protection Division 4244 International Parkway, Suite 120 Atlanta, Georgia 30354

Subject:

Letter documenting Duke Energy Carolinas (Duke) Assumptions for Offsite Dose Calculation Methodology On March 17, 1994, a letter from Carolina Power & Light Company, Duke Power Company, US Department of Energy -- Savannah River Operation Office, and South Carolina Electric and Gas Company was sent to your agency. This letter discussed implementation of EPA-400-R-92-001, Manualof ProtectiveAction Guides and Protective Actions for Nuclear Incidents, and the assumptions that would be used in dose calculations supporting Protective Action Recommendations. Duke amended this letter on December 6, 1996, in conjunction with implementing the RADDOSE-V dose assessment code, and renewed it on October 6, 1999; October 11, 2002; August 25, 2005, August 6, 2008, and June 7, 2011.

www.duke-energy.com Rev. 14-3 September, 2014

Letter #17 Duke Energy Carolinas hereby renews the June 7, 2011, agreement letter. At the Utility/State Dose Assessor meeting held November 13-14, 2001, in Charlotte, a decision was made that there was no longer a need for a formal agreement letter. However, the States requested documentation of the assumptions for the utilities' offsite dose calculation methodology. Attachment 1 documents these assumptions. Changes to Duke's assumptions for offsite dose calculation methodology from those in the June 7, 2011, letter are highlighted by change bars on Attachment 1. Currently, the June 7, 2011, agreement letter is listed in Duke's Energy Carolinas Emergency Plans, and our plans require agreement letters be renewed every three years. Since the agreement letter is in the Emergency Plans, Duke Energy Carolinas will continue to renew it on the frequency required for agreement letters. If you have any questions, contact Eric White at 910-512-1056.

Sincerely, Michael H. Austin Corporate Functional Area Manager, Emergency Preparedness : Duke Energy Carolinas Assumptions for Offsite Dose Calculation Methodology Rev. 14-3 September, 2014

Letter #17 cc: (with attachments)

Kim Stenson (SC EMD)

Nathan Nienhius (SC EMD)

James Young (NC DEM)

Elaine Wathen Mike Cook (NC DEM Western Branch Office)

Stephen Clark (GEMA)

Sandra Threatt (SC DHEC)

William Jeffries (NC DRP)

Tom Arlow (CN01 EP)

Kevin Murray (MG01 EP)

Patrick Street (ON01 SC)

Gary Terrell (MG01 RP)

Eric Lampe (ON01 R2)

Robert Beckham (EC07F)

Mike Austin (EC05P)

Tina Kuhr (EC05P)

NEP File #180 Rev. 14-3 September, 2014

Letter #17 Attachment 1 Duke Energy Corporation Assumptions for Offsite Dose Calculation Methodology ATMOSPHERIC DISPERSION

1. The atmospheric stability class will be identified by Pasquill class A through G.

2. The wind speed will be given in miles per hour.

3. RADDOSE-V uses a variable trajectory, puff advection dispersion model to simulate atmospheric transport and diffusion of radionuclides released from Duke Energy's nuclear stations. Plume trajectories are calculated using meteorological data obtained at each nuclear site. The diffusion (or spread) of each puff is based on a Gaussian distribution model. The dimensions of individual puffs, which compose the plume, are determined as a function of travel distance and atmospheric stability.

4. Mixing heights are based on seasonal afternoon mean at each of the Duke Nuclear Sites. During moming hours under stable conditions, however, mixing heights are set to a minimum level of 30.2 meters for Catawba and McGuire and 57.9 meters for Oconee at sunrise and interpolated up to the mean afternoon seasonal height at 2 P.M. Thus, a lid height is assumed in these cases, with the plume always restricted below the lid height (at ground level).

For all other cases and hours, the mean seasonal value is used.

5. The release height will be assumed to be at ground level unless specified otherwise.

6. There will be no allowances made for atmospheric inversion.

DEPOSITION

1. The transport of iodine and particulate radionuclides from the plume to the ground by turbulence and gravitational settling (dry deposition) and precipitation (wet deposition) are accounted for based on the methodologies outlined in NUREG/CR-3344, MESOI Version 2.0: An Interactive Mesoscale LagrangianPuff DispersionModel with Deposition and Decay, November 1983, U.S. Regulatory Commission, and NUREG/CR-4000, The MESORAD Dose Assessment ComputerModel, Volume 1: Technical Basis, March 1986, U. S. Nuclear Regulatory Commission, models.

2. RADDOSE-V accounts for both dry and wet deposition of radioiodines and particulates. For dry deposition calculations, 1 cm/second is used as the deposition rate. For wet deposition, the washout rate is dependent on the precipitation rate. Deposition calculations are not applied to noble gases.

Rev. 14-3 September, 2014

Letter #17 Duke Energy Corporation Assumptions for Offsite Dose Calculation Methodology

3. The duration of exposure to deposition in calculating the TEDE dose will be four days.

RADIOLOGICAL

1. The adult thyroid dose will be calculated using Dose Conversion Factors (DCFs) from EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, May 1992, U.S. Environmental Protection Agency, using an assumed breathing rate of 1.2x1 06 cm 3 per hour.

2. The adult thyroid dose will be reported as a Thyroid Committed Dose Equivalent (Thyroid CDE). The Thyroid Effective Dose Equivalent (Thyroid EDE) will not be added to the Thyroid CDE.

3. The Total Effective Dose Equivalent (TEDE) will be calculated as the sum of:

" The external exposure from the plume (EDE plume)

" The internal exposure from inhalation of the plume (CEDE plume)

" The external exposure from the plume radionuclides deposited on the ground (EDE ground).

4. Radioactive decay during plume passage will be calculated.

5. The radioiodine source term will be reported as Total Iodine. The units will be Curies/second.

6. The noble gas source term will be reported as Total Noble Gases. The units will be Curies/second.

7. The particulate source term will be reported as Total Particulates. The units will be Curies/second.

8. Derived Response Levels (DRLs), if used, will be taken from EPA 400-R 001.

9. Protective Action Recommendations (PARs) for evacuation will be made for projected doses equaling or exceeding 1 rem TEDE or 5 rem Thyroid CDE.

10. Skin doses will be calculated from the TSC/EOF during the Intermediate Phase as needed.

11. The estimate of projected offsite dose will be reported as TEDE and CDE Thyroid for the forecast period only.

Attachment 1 Page 2 of 3 Rev. 14-3 September, 2014

Letter #17 Duke Energy Corporation Assumptions for Offsite Dose Calculation Methodology EMERGENCY NOTIFICATION FORM

1. The time of reactor shutdown, the time the release began, projection time, and an estimated duration of release will be given. The estimated duration will begin at the time of the release start.

2. The release will be quantified in units of Curies per second.

3. There will be no PARs for sheltering for doses below the 1 rem TEDE or 5 rem Thyroid CDE PAGs.

ACCOUNTING FOR INTERNAL DOSE TO EMERGENCY WORKERS

1. During a General Emergency, while an evacuation is in progress, the Self Reading Dosimeter (SRD) reading will be taken as the TEDE for controlling off site emergency worker exposure. After the evacuation is completed, the Duke EOF will provide an adjustment to the SRD reading using the SRD correction factor calculated by RADDOSE-V.

Attachment 1 Page 3 of 3 Rev. 14-3 September, 2014

Emergency Planaing Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 Activity Description and References MNS EPLAN Change 14-3, Sect. Q, Appendix 5, BLOCK 1i Agreement Letter #17 Periodic Update of Agreement Letter #17, Updating Duke Energy Carolinas Assumptions for Offsite Dose Calculation Methodology Activity Scope: BLOCK 2 Z The activity is a change to the emergency plan

[]The activity is not a change to the emergency plan Change Type: I BLOCK3 Change Type: ]BLOCK 4 D The change is editorial or typographical lii] The change does conform to an activity that has Z The change is not editorial or typographical prior approval Z The change does not conform to an activity that has prior approval Planning Standard Impact Determination: BLOCK 5 l-- §50.47(b)(1) - Assignment of Responsibility (Organization Control)

§50.47(b)(2) - Onsite Emergency Organization t §50.47(b)(3) - Emergency Response Support and Resources D §50.47(b)(4) - Emergency Classification System*

[-] §50.47(b)(5) - Notification Methods and Procedures*

[--] §50.47(b)(6) - Emergency Communications D §50.47(b)(7) - Public Education and Information

[-i §50.47(b)(8) - Emergency Facility and Equipment D §50.47(b)(9) - Accident Assessment*

§50.47(b)(10) - Protective Response*

Lii§50.47(b)(1 1) - Radiological Exposure Control 0] §50.47(b)(12) - Medical and Public Health Support L-] §50.47(b)(1 3) - Recovery Planning and Post-accident Operations

[]§50.47(b)(14) - Drills and Exercises

§50.47(b)(i 5) - Emergency Responder Training S§ 50.47(b)(16) - Emergency Plan Maintenance

Risk Significant Planning Standards ZThe proposed activity does not impact a Planning Standard This change is a periodic update of an existing letter-of-agreement between Duke Energy and specified partners to meet specified periodicity requirements. No commitment changes are made as a result of this update. As such no reduction-in-effectiveness results from this change.

Revision 12 I

Emergency Planning Functional Area Manual 3.10 10CFR 50.54(q) Evaluations Attachment 3.10.7.2 BLOCKI6 Commitment Impact Determination:

E- The activity does involve a site specific EP comrunitment Record the conmmitment or conmnitment reference:

" The activity does not involve a site specific EP comnmitment Zesults: BLOCK 7 The activity can be implemented without perfoF1ing a §50.54(q) effectiveness evaluation

-- ] The activity cannot be implemented without performing a §50.54(q) effectiveness evaluation Preparer Name: ~e P4 u vrWSTnatu re, ...

.Date:.;

e......................

Renard Burris

.......... ..... 8/26/14 D........a.............

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Reviewer Name: IDate: / ,

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Revision 12 2

MNS-14-072, Emergency Plan, Revision 14-3

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MNS-14-072, Emergency Plan, Revision 14-3

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