HNP-18-017, CFR 50.54(q) Evaluations

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CFR 50.54(q) Evaluations
ML18036A894
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 02/05/2018
From: Bradley Jones
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-18-017
Download: ML18036A894 (195)


Text

Bentley K. Jones Director, Organizational Effectiveness Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 919.362.2305 10 CFR 50.4(b)(5)(ii) 10 CFR 50.54(q)(5)

February 5, 2018 Serial: HNP-18-017 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63

Subject:

10 CFR 50.54(q) Evaluations

Reference:

Letter from Dennis J. Galvin (NRC) to Kelvin Henderson (Duke Energy), Brunswick Steam Electric Plant, Units 1 and 2; Shearon Harris Nuclear Power Plant, Unit 1; H.B. Robinson Steam Electric Plant Unit No. 2; and Oconee Nuclear Station, Units 1, 2, and 3 - Issuance of Amendments to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes, dated August 21, 2017, Agencywide Documents Access and Management System (ADAMS) Accession Number ML17188A387 Ladies and Gentlemen:

In accordance with 10 CFR 50.4(b)(5)(ii) and 10 CFR 50.54(q)(5), Duke Energy Progress, LLC (Duke Energy), is submitting 10 CFR 50.54(q) Effectiveness Evaluation Forms for revisions to the Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Emergency Plan, Implementing Procedures, and Emergency Program Maintenance Procedures. Specifically, PLP-201, Emergency Plan, Revision 69; PEP-110, Emergency Classification and Protection Action Recommendations, Revision 28; PEP-310, Notifications and Communications, Revision 39; EPM-200, ERO Training Program, Revision 22; and EPM-420, Emergency Equipment Inventory, Revision 18, have been issued. Additionally, PEP-240, Activation and Operation of the Technical Support Center, Revision 24; PEP-241, Technical Support Center (TSC) Emergency Ventilation System Operation, Revision 7; PEP-250, Activation and Operation of the Joint Information Center, Revision 22; PEP-260, Activation and Operation of the Operations Support Center, Revision 19; PEP-270, Activation and Operation of the Emergency Operations Facility, Revision 36; PEP-330, Radiological Consequences, Revision 13; and PEP-500, Recovery, Revision 15, have been superseded by Duke Energy fleet procedures. These changes were effective on January 4, 2018.

The above revisions implement, in part, the Duke Energy Common Emergency Operations Facility for HNP License Amendment No. 160 as issued by the NRC on August 21, 2017, referenced above. Duke Energy has evaluated these revisions, in accordance with 10 CFR 50.54(q), and determined that the revisions are not a reduction in the effectiveness of the Emergency Plan and that the Plan, as changed, continues to meet the standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E. The Enclosure to this letter provides the 10 CFR 50.54(q) Effectiveness Evaluation Forms for the changes identified above.

U.S. Nuclear Regulatory Commission Serial: HNP-18-017 This submittal contains no regulatory commitments.

Please refer any questions regarding this submittal to Jeff Robertson, Manager - Regulatory Affairs, at (919) 362-3137.

Sincerely,

~\~

Bentley K. Jones

Enclosure:

10 CFR 50.54(q) Effectiveness Evaluation Forms for PLP-201, Revision 69; PEP-110, Revision 28; PEP-310, Revision 39; EPM-200, Revision 22; EPM-420, Revision 18; and the Superseding of PEP-240, Revision 24; PEP-241, Revision 7; PEP-250, Revision 22; PEP-260, Revision 19; PEP-270, Revision 36; PEP-330, Revision 13; PEP-500, Revision 15 cc: J. Zeiler, NRC Sr. Resident Inspector, HNP M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II

U.S. Nuclear Regulatory Commission Serial: HNP-18-017 This submittal contains no regulatory commitments.

Please refer any questions regarding this submittal to Jeff Robertson, Manager - Regulatory Affairs, at (919) 362-3137.

Sincerely, Bentley K. Jones

Enclosure:

10 CFR 50.54(q) Effectiveness Evaluation Forms for PLP-201, Revision 69; PEP-110, Revision 28; PEP-310, Revision 39; EPM-200, Revision 22; EPM-420, Revision 18; and the Superseding of PEP-240, Revision 24; PEP-241, Revision 7; PEP-250, Revision 22; PEP-260, Revision 19; PEP-270, Revision 36; PEP-330, Revision 13; PEP-500, Revision 15 cc: J. Zeiler, NRC Sr. Resident Inspector, HNP M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II

U.S. Nuclear Regulatory Commission Serial: HNP-18-017 Enclosure SERIAL HNP-18-017 ENCLOSURE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400/RENEWED LICENSE NUMBER NPF-63 10 CFR 50.54(Q) EFFECTIVENESS EVALUATION FORMS FOR PLP-201, REVISION 69; PEP-110, REVISION 28; PEP-310, REVISION 39; EPM-200, REVISION 22; EPM-420, REVISION 18; AND THE SUPERSEDING OF PEP-240, REVISION 24; PEP-241, REVISION 7; PEP-250, REVISION 22; PEP-260, REVISION 19; PEP-270, REVISION 36; PEP-330, REVISION 13; PEP-500, REVISION 15 (191 PAGES TOTAL PLUS COVER)

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Screening and Evaluation Number Applicable Sites BNP EREG #: 2174957 CNS CR3 HNP MNS 5AD #: 2174934 ONS HNP GO Document and Revision Emergency Plan PLP-201 Revision 69 Part I. Description of Proposed Change:

The NRC approved implementation of the Duke Fleet Common EOF as an element of the HNP Emergency Plan in HNP license amendment 160 dated August 21, 2017, with Enclosure 8 being the Safety Evaluation Report (SER) related to this request. In conjunction with the common EOF, a program initiative was undertaken by Duke Energy to standardize the augmenting ERO positions, functions, and responsibilities (tasks) across the fleet for effective and efficient use of the Common EOF. This involves changes to the current HNP augmenting ERO, based on the number of responders and their titles identified in the site emergency plan and implementing procedures. Included in the standard ERO initiative is the development of fleet standard ERO checklists, procedures and forms.

Note - this initiative makes no changes to the on-shift ERO.

1. Enclosure 1 is the mark up of the HNP emergency plan reflecting the standard augmenting ERO
2. Enclosure 2 is the HNP ERO Position Comparison and Evaluation - TSC/OSC/EOF
3. Enclosure 3 is the HNP ERO Position Comparison and Evaluation - JIC The following changes were implemented in this revision to support implementation of the Standard ERO/Common EOF Project:

From:

2.4.1 Main Control Room A. Shift Manager (SM): Until an emergency is declared, the Shift Manager (SM) has the following responsibilities relating to the Emergency Plan:

1) Direct the activities of the Operations staff.
2) Recognize an off-normal condition as indicated by instrument readings or observation.
3) Implement any Emergency Operating Procedures.
4) Determine when an Emergency Action Level has been met or exceeded, declare an emergency, and assume the position of Site Emergency Coordinator-MCR.

B. Site Emergency Coordinator-MCR: The primary person assigned to the position of Site Emergency Coordinator-MCR during the initial stages of an emergency is the Shift Manager (SM). The assigned alternates are on-shift Licensed Senior Reactor Operators as designated in accordance with operations procedures. Once the Technical Support Center is activated the responsibilities of Site Emergency Coordinator-MCR are turned over to the Site Emergency Coordinator-TSC and the Emergency Response Manager in accordance with the implementing procedures.

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The Site Emergency Coordinator-MCR, shall not delegate the following responsibilities:

1) Classification of the emergency.
2) Approval of required notifications made to the State/Counties and the NRC.
3) Establishment of on-site mission priorities in response to the emergency.
4) Approval of planned radiation exposures for HNP personnel in excess of 5 Rem TEDE or entry into radiation fields greater than 25 Rem/hr.
5) Review and approval of deviations from Technical Specifications or license conditions.
6) Authorization of the administration of Potassium Iodide to on-site emergency workers.
7) Approval of Protective Action Recommendations made to the State/Counties.
8) Termination of the emergency.

C. Plant Operations Director: The Plant Operations Director, located in the Main Control Room after activation of the Technical Support Center, is responsible to the Site Emergency Coordinator-TSC for providing direction to the Main Control Room Staff, the Fire Brigade, and the First Aid Teams (MERT). The POD is trained as a SAMG decision maker whose focus is on the operational aspect of the strategy developed by the TSC.

D. Site Incident Commander: A Site Incident Commander is established on all shifts. When a fire occurs, the Site Incident Commander is the on-scene commander for fighting the fire and directs the activities of the Fire Brigade.

The Site Incident Commander reports to the Site Emergency Coordinator-MCR or to the Plant Operations Director after activation of the Technical Support Center.

E. Fire Brigade: When a fire is announced, the Fire Brigade reports to the Site Incident Commander. If a fire occurs, the Fire Brigade reports to the Fire Staging Area where fire-fighting equipment is located, and then responds to the fire scene. The fire brigade is composed of on-shift personnel trained in fighting fires as described in Section 5.2.

F. First Aid Team (MERT): A First Aid Team (MERT) is established on all shifts. The First Aid Team (MERT) performs/coordinates emergency first aid and search and rescue activities. The First Aid Team (MERT) reports to the Site Emergency Coordinator-MCR or to the Plant Operations Director after activation of the Technical Support Center.

G. Emergency Communicator-MCR: Initially filled with on-shift personnel, is appointed by and reports to the Site Emergency Coordinator-MCR and is responsible for communicating with:

1) Off-site authorities (County, State, NRC, and so forth) to perform required notifications of the declaration, upgrading, termination of an emergency prior to the activation of the TSC and EOF.
2) The plant Emergency Response Organization (during off-hours) when HNP emergency facilities are being activated.
3) Local Immediate Response Organizations (medical, fire, law enforcement, and so forth) if their assistance is needed.

2.4.2 Technical Support Center A. Site Emergency Coordinator-TSC: The Site Emergency Coordinator-TSC is responsible for overall command and control of the on-site response to the emergency. The Site Emergency Coordinator is also responsible for providing guidance to the Technical Analysis Director, Radiological Control Director, Communications Director, Security Director, Plant Operations Director and the Emergency Repair Director.

Upon activation of the Technical Support Center the Site Emergency Coordinator-TSC relieves the Site Emergency Coordinator-MCR of the following major responsibilities:

1) Classification of the emergency.
2) Establishment of on-site mission priorities in response to the emergency.
3) Approval of planned radiation exposures for on-site personnel in excess of 5 Rem TEDE or entry into radiation fields greater than 25 Rem/hr.
4) Review and approval of deviations from Technical Specifications or license conditions. [7.0.U, Recommendation 5i]
5) Authorization of the administration of Potassium Iodide to on-site emergency workers.

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6) A trained SAMG decision maker whose focus is on the development and prioritization aspect of the SAMG strategy.
7) Termination of the emergency.

B. TSC-Senior Reactor Operator: The TSC-Senior Reactor Operator is located in the Technical Support Center and reports to the Site Emergency Coordinator-TSC and directs the TSC-ERFIS Operator. The TSC-Senior Reactor Operator is responsible for providing technical assistance related to plant conditions and operations and to perform monitoring and evaluations required for Severe Accident Management Guidelines.

C. TSC-ERFIS Operator: The Technical Support Center ERFIS Operator reports to the TSC-SRO and is located in the Technical Support Center. The position is responsible for providing/displaying any information from ERFIS requested by Technical Support Center personnel.

D. Technical Analysis Director: The Technical Analysis Director reports to the Site Emergency Coordinator-TSC and is located in the Technical Support Center. The Technical Analysis Director is responsible for providing direction to the Technical Support Center Accident Assessment Team, performing, monitoring and evaluation required for core cooling flow paths, Severe Accident Management Guidelines, and directing AAT members to evaluate strategies that maintain or restore core cooling flow paths and implementing Severe Accident Management Guidelines. [7.0.U, Recommendation 4]

E. TSC-Accident Assessment Team: The TSC-Accident Assessment Team reports to the Technical Analysis Director and is located in the Technical Support Center. The team is composed of a Shift Technical Advisor, Core Performance Engineer, Electrical/I&C Engineer, and Mechanical Engineer. They are responsible for providing recommendations to the Technical Analysis Director on problems as assigned.

F. Communications Director: The Communications Director, located in the Technical Support Center, reports to the Site Emergency Coordinator TSC. The Communications Director is responsible for ensuring notification and communications to Offsite Authorities including the NRC and providing direction to the Emergency Communicator-NRC, TSC-Telecomm/Computer Support, TSC Logkeeper and the Admin Team.

G. Emergency Communicator-NRC: The Emergency Communicator-NRC is located in the Technical Support Center and reports to the Communications Director. The Emergency Communicator-NRC is responsible for:

1) Generating required written notifications to the NRC in a timely manner.
2) Establishing contact with the NRC via the Emergency Telecommunications System and providing any requested information of the status of the emergency.

H. TSC-Telecomm/Computer Support: TSC-Telecomm/Computer Support personnel are located in the Technical Support Center and report to the Communications Director. They are responsible for providing technical assistance required in the areas of telecommunications or computer support.

I. TSC Admin Team: The TSC Admin Team is located in the Technical Support Center and is composed of a Librarian and Admin Support personnel. They report to the Communications Director and are responsible for providing any documents, prints or other clerical services as requested by personnel in the Technical Support Center.

J. TSC Logkeeper: The TSC Logkeeper is located in the Technical Support Center and reports to the Communications Director. The TSC Logkeeper is responsible for recording the major activities that occur in the Technical Support Center during an emergency.

K. Radiological Control Director: The Radiological Control Director is located in the Technical Support Center and reports to the Site Emergency Coordinator-TSC. The Chemistry Coordinator and the Radiological Control Coordinator, both located in the Operations Support Center, report to the Radiological Control Director. The Radiological Control Director is responsible for:

1) Providing direction to onsite health physics and chemistry emergency response actions.
2) Ensuring that the Site Emergency Coordinator and other Directors in the Technical Support Center are kept informed of radiological/chemical conditions on and off site.

L. TSC HP Technician: The TSC HP Technician, normally located in the Technical Support Center, reports to the Radiological Control Director and is responsible for providing radiological support and monitoring activities within the TSC.

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M. Security Director: The Security Director, normally located in the Technical Support Center, reports to the Site Emergency Coordinator-TSC and has the following major responsibilities:

1) Maintaining plant security in accordance with the provisions of the HNP Security Plan and Safeguards Contingency Plan.
2) Coordinating the accountability of personnel inside the Protected Area.
3) Providing Security Force personnel in support of emergency activities.

2.4.3 Operations Support Center A. Emergency Repair Director: The Emergency Repair Director, located in the Operations Support Center, reports to the Site Emergency Coordinator-TSC. The Emergency Repair Director is responsible for providing direction to the total on-site maintenance and equipment restoration effort from the Operations Support Center.

B. Damage Control Coordinator: The Damage Control Coordinator, located in the Operations Support Center, reports to the Emergency Repair Director. The Damage Control Coordinator is responsible for providing direction to the Damage Control Team Leaders, Maintenance Planners, and OSC Logkeeper.

C. Damage Control Team Leaders: The Damage Control Team Leaders are appointed by the Damage Control Coordinator. They are responsible to the Damage Control Coordinator for on-the-scene supervision of the Damage Control Teams to which they are assigned.

D. Damage Control Teams: The Damage Control Teams are dispatched by the Damage Control Coordinator, from their initial assembly point in the Operations Support Center, to the scene of an emergency repair or damage assessment requirement. The Damage Control Teams report to the on-scene Damage Control Team Leader and are composed of mechanical, instrument and control, and electrical maintenance personnel.

E. Maintenance Planners: Maintenance Planners, located in the Operations Support Center, report to the Damage Control Coordinator. The Maintenance Planners are responsible for developing plans for emergency repair, determining spare parts needed to make the repairs and estimating the amount of time required to perform the emergency repairs.

F. OSC Logkeeper: The OSC Logkeeper, located in the Operations Support Center, reports to the Damage Control Coordinator. The OSC Logkeeper is responsible for recording the major activities that occur in the Operations Support Center during an emergency.

G. Radiological Control Coordinator: The Radiological Control Coordinator, located in the Operations Support Center, is responsible to the Radiological Control Director for providing direction to the Radiological Control Teams during an emergency.

H. Radiological Control Teams: Radiological Control Teams report to the Radiological Control Coordinator and are composed of health physics personnel. They assemble initially in the Operations Support Center and are subsequently dispatched wherever personnel radiation control and decontamination functions are needed.

I. Chemistry Coordinator: The Chemistry Coordinator, located in the OSC, is responsible to the Radiological Control Director for providing direction to the Chemistry Team during an emergency.

J. Chemistry Team: Chemistry Teams report to the Chemistry Coordinator and are composed of plant chemistry personnel. They assemble initially in the Operations Support Center and are subsequently dispatched to sampling stations and the laboratory.

2.4.4 Emergency Operations Facility A. Emergency Response Manager: The Emergency Response Manager, located in the Emergency Operations Facility, is responsible for overall command and control of the HNP response to the emergency. The Emergency Response Manager is also responsible for providing guidance to the Technical Analysis Manager, Radiological Control Manager, Communications Manager, and the Admin and Logistics Manager.

Upon activation of the Emergency Operations Facility the Emergency Response Manager relieves the Site Emergency Coordinator-MCR of the following major responsibilities:

1) Approval of required notifications to the State/Counties.

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2) Approval of planned radiation exposures for off-site HNP personnel in excess of 5 Rem TEDE or entry into radiation fields greater than 25 Rem/hr.
3) Approval of the administration of Potassium Iodide to off-site HNP emergency workers.
4) Approval of Protective Action Recommendations.
5) Direct interface with offsite authorities.
6) Coordination of Dose Projection and Environmental Monitoring activities.
7) A trained SAMG decision maker whose focus is on the offsite consequences of the strategy recommended by the TSC. The ERM has the ultimate approval authority for strategy implementation.

B. EOF-Senior Reactor Operator: The EOF-Senior Reactor Operator is located in the Emergency Operations Facility and reports to the Emergency Response Manager. The EOF-Senior Reactor Operator is responsible for providing technical information and assistance related to plant conditions and operations.

C. Emergency Preparedness Advisor: The Emergency Preparedness Advisor, located in the Emergency Operations Facility, reports to the Emergency Response Manager in the EOF and advises the Emergency Response Manager and other Emergency Response Organization personnel on implementation of the Emergency Plan and implementing procedures.

D. News Coordinator: The News Coordinator, located in the Emergency Operations Facility, reports to the Emergency Response Manager. The News Coordinator has the responsibility for preparing and coordinating the approval of news releases.

E. Administrative and Logistics Manager: The Administrative and Logistics Manager, located in the Emergency Operations Facility, reports to the Emergency Response Manager and is responsible for direction of activities of the Administrative Team Leader and Admin Building Assembly Area Leader.

F. EOF Telecomm/Computer Support: EOF Telecommunications/Computer Support personnel are located in the EOF and report to the Administrative and Logistics Manager. They are responsible for providing technical assistance required in the areas of telecommunications or computer support.

G. Admin Team Leader: The Admin Team Leader, located in the Emergency Operations Facility, reports to the Administrative and Logistics Manager and is responsible for directing the actions of the Admin Team.

H. Admin Team: The Admin Team, located in the Emergency Operations Facility, consists of a Setup Leader, Librarian and Admin Support personnel. They report to the Admin Team Leader and are responsible for providing any documents, prints or other clerical services as requested by personnel in the Emergency Operations Facility.

I. EOF Logkeeper: The EOF Logkeeper is located in the Emergency Operations Facility and reports to the Admin Team Leader. The EOF Logkeeper is responsible for recording the major activities that occur in the Emergency Operations Facility during an emergency.

J. Assembly Area Leader: The Assembly Area Leader is responsible to the Admin and Logistics Manager, or prior to activation of this position, the Site Emergency Coordinator, for coordinating the activities in the Admin Building Assembly Area.

K. Technical Analysis Manager: The Technical Analysis Manager reports to the Emergency Response Manager and is responsible for direction of activities of the Emergency Operations Facility Accident Assessment Team.

L. EOF Accident Assessment Team: The EOF Assessment Team reports to the Technical Analysis Manager and is located in the Emergency Operations Facility. The team is composed of a Civil Engineer, Electrical Engineer, I&C Engineer, and Mechanical Engineer. They are responsible for providing recommendations to the Technical Analysis Manager on problems as assigned.

M. Radiological Control Manager: The Radiological Control Manager, located in the Emergency Operations Facility, reports to the Emergency Response Manager. The Radiological Control Manager is responsible for providing direction to the Dose Projection Team Leader, Technical Advisor and the EOF Health Physics Technician. The Radiological Control Manager is also responsible for:

1) Providing direction to offsite health physics emergency response actions.
2) Ensuring that the Emergency Response Manager and other Managers in the EOF are kept informed of radiological/chemical conditions on and off site.

N. Technical Advisor: The Technical Advisor, located in the Emergency Operations Facility, reports to the

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Radiological Control Manager. The Technical Advisor assists the Radiological Control Manager and staffs the HPN Line when requested by the NRC.

O. Dose Projection Team Leader: The Dose Projection Team Leader, located in the Emergency Operations Facility, reports to the Radiological Control Manager. The Dose Projection Team Leader provides guidance to the Environmental Field Coordinator and the Dose Projection Team.

P. Dose Projection Team: The Dose Projection Team reports to the Dose Projection Team Leader and is located in the Emergency Operations Facility. The Dose Projection Team is responsible for performing source term and offsite dose calculations.

Q. Environmental Field Coordinator: The Environmental Field Coordinator, located in the Emergency Operations Facility, is responsible to the Dose Projection Team Leader. The Environmental Field Coordinator is responsible for providing direction to the Environmental Monitoring Teams.

R. Environmental Monitoring Teams: Environmental Monitoring Teams report to the Environmental Field Coordinator after activation of the Emergency Operations Facility, or, prior to activation of the Emergency Operations Facility, to the Site Emergency Coordinator -MCR. Teams assemble at HE&EC and are subsequently dispatched in vehicles to the surrounding area. They are responsible for offsite plume tracking, monitoring and other sampling activities.

S. Communications Manager: The Communications Manager, located in the Emergency Operations Facility, reports to the Emergency Response Manager. The Communications Manager is responsible for ensuring notification and communication to offsite authorities and providing direction to the Emergency Communicator-State/County and the Representatives to the State and County EOCs.

T. Emergency Communicator-State/Counties: The Emergency Communicator-State/Counties, located in the Emergency Operations Facility, reports to the Communications Manager. The Emergency Communicator-State/Counties is responsible for conducting timely notification and transfer of emergency information to the State and Counties.

U. Emergency Communicator-Corporate Comm/JIC: The Emergency Communicator-Corporate Comm/JIC, located in the Emergency Operations Facility, reports to the Communications Manager. The Emergency Communicator-Corporate Comm/JIC is responsible for providing information to support public information emergency response activities.

V. Representatives to the State/County EOCs: The Representatives to the State/County EOCs are located at the following:

N.C. State EOC Joint Force Headquarters (JFHQ) building, 1636 Gold Star Drive, Raleigh North Carolina and is the principle Emergency Operations Center.

Wake County EOC Wake County Courthouse, Raleigh, N.C.

Chatham County EOC Emergency Operations Center, Pittsboro, N.C.

Harnett County EOC Emergency Operations Center, Lillington, N.C.

Lee County EOC Lee County Courthouse, Sanford, N.C.

Chatham County Alternate EOC 3760 Alston Bridge Rd., Siler City, NC Harnett County Alternate EOC 126 Alexander Dr., Lillington, NC Lee County Alternate EOC, 225 E. Weatherspoon, Sanford, NC These representatives act as technical liaisons to facilitate communications and the coordination of information flow between the Site Emergency Coordinator or Emergency Response Manager and State/local authorities. They report to the Communications Manager in the Emergency Operations Facility.

2.4.5 Joint Information Center A. Company Spokesperson: The Company Spokesperson, located in the Joint Information Center, reports to the Emergency Response Manager. The Company Spokesperson is responsible for providing guidance to the JIC Director, Admin Coordinator and Public Information Coordinator. The Company Spokesperson also has the following major responsibilities:

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1) Maintain command and control of the Joint Information Center.
2) Coordinates and directs responses to media inquiries.
3) Ensure that the composition and timeliness of Duke Energy News Releases are adequate.
4) Conduct periodic briefings with the news media.
5) Provide for timely exchange of information between other spokespersons.

B. Technical Specialist: The Technical Specialist, located in the Joint Information Center, reports to the Company Spokesperson. The Technical Specialist is responsible for obtaining and developing technical emergency information.

1) Gather information from the EOF for Duke Energy news media briefings.
2) Provide timely and accurate technical information to the media during formal briefings.

C. JIC Director: The JIC Director, located in the Joint Information Center, reports to the Company Spokesperson.

The JIC Director is responsible for the development and coordination of news releases and dissemination of information.

D. Administrative Coordinator: The Administrative Coordinator, located in the Joint Information Center, reports to the Technical Specialist. The Administrative Coordinator provides guidance to the Administrative Assistants and Media Badging Specialist.

E. Administrative Assistant: The Administrative Assistant, located in the Joint Information Center, reports to the Administrative Coordinator. The Administrative Assistant is responsible for providing administrative services and supplies to Joint Information Center personnel.

F. Media Badging Specialist: The Media Badging Specialist, located in the Joint Information Center, reports to the Administrative Coordinator. The Media Badging Specialist is responsible for controlling access to the Media Briefing Area and distributing information.

G. Public Information Coordinator: The Public Information Coordinator, located in the Joint Information Center, reports to the Company Spokesperson and interfaces with the Customer Service Center.

H. Customer Service Center: The Customer Service Center is responsible for staffing telephone lines to respond to calls from the media and public.

4.5.2.C. Possible recommendations issued by HNP at a General Emergency include, but are not limited to:

1) Evacuation of the general public within the two (2) mile radius and five (5) miles downwind. All other areas within the EPZ are sheltered (minimum PAR issued).
2) Evacuation of the general public within the five (5) mile radius and ten (10) miles downwind. All other areas within the EPZ are sheltered To:

2.4.1 Main Control Room A. Shift Manager (SM): Until an emergency is declared, the Shift Manager (SM) has the following responsibilities relating to the Emergency Plan:

1) Direct the activities of the Operations staff.
2) Recognize an off-normal condition as indicated by instrument readings or observation.
3) Implement any Emergency Operating Procedures.
4) Determine when an Emergency Action Level has been met or exceeded, declare an emergency, and assume the position of Emergency Coordinator-MCR.

B. Emergency Coordinator-MCR: The primary person assigned to the position of Emergency Coordinator-MCR during the initial stages of an emergency is the Shift Manager (SM). The assigned alternates are on-shift Licensed Senior Reactor Operators as

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designated in accordance with operations procedures. Once the Technical Support Center is activated the responsibilities of Emergency Coordinator-MCR are turned over to the Emergency Coordinator-TSC and the EOF Director in accordance with the implementing procedures.

The Emergency Coordinator-MCR, shall not delegate the following responsibilities:

1) Classification of the emergency.
2) Approval of required notifications made to the State/Counties and the NRC.
3) Establishment of on-site mission priorities in response to the emergency.
4) Approval of planned radiation exposures for HNP personnel in excess of 5 Rem TEDE or entry into radiation fields greater than 25 Rem/hr.
5) Review and approval of deviations from Technical Specifications or license conditions.
6) Authorization of the administration of Potassium Iodide to on-site emergency workers.
7) Approval of Protective Action Recommendations made to the State/Counties.
8) Termination of the emergency.

C. Site Incident Commander: A Site Incident Commander is established on all shifts. When a fire occurs, the Site Incident Commander is the on-scene commander for fighting the fire and directs the activities of the Fire Brigade. The Site Incident Commander reports to the Emergency Coordinator-MCR or to the Plant Operations Director after activation of the Technical Support Center.

D. Fire Brigade: When a fire is announced, the Fire Brigade reports to the Site Incident Commander. If a fire occurs, the Fire Brigade reports to the Fire Staging Area where fire-fighting equipment is located, and then responds to the fire scene. The fire brigade is composed of on-shift personnel trained in fighting fires as described in Section 5.2.

E. First Aid Team (MERT): A First Aid Team (MERT) is established on all shifts. The First Aid Team (MERT) performs/coordinates emergency first aid and search and rescue activities. The First Aid Team (MERT) reports to the Emergency Coordinator-MCR or to the Plant Operations Director after activation of the Technical Support Center.

F. Emergency Communicator-MCR: Initially filled with on-shift personnel, is appointed by and reports to the Emergency Coordinator-MCR and is responsible for communicating with:

1) Off-site authorities (County, State, NRC, and so forth) to perform required notifications of the declaration, upgrading, termination of an emergency prior to the activation of the TSC and EOF.
2) The plant Emergency Response Organization (during off-hours) when HNP emergency facilities are being activated.
3) Local Immediate Response Organizations (medical, fire, law enforcement, and so forth) if their assistance is needed.

2.4.2 Technical Support Center The TSC Organization Chart is show in Figure 2.4-2.

A. Emergency Coordinator/Assistant Emergency Coordinator:

The Emergency Coordinator reports to the EOF Director and supervises and directs the site ERO. The Assistant Emergency Coordinator reports to the Emergency Coordinator and manages the operation of the TSC. The Emergency Coordinator and Assistant Emergency Coordinator positions are equally qualified. Key responsibilities include:

1) Coordinate response activities with offsite response agencies (EM, ICP, Field Mon, etc.)
2) Verify that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing list has been completed
3) Coordinate ERO/facility shift turnover
4) Assume/maintain command and control
5) Transfer command and control

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6) Manage all onsite emergency response activities
7) Manage facility emergency response activities
8) Coordinate integration of the NRC site team
9) Prioritize and authorize requests for external assistance (technical, craft, admin, etc.)
10) Approve equipment, supply, and logistics expenditures for response to the event
11) Arrange for equipment and supply resources
12) Arrange for logistics support
13) Request Federal support and resources
14) Classify and declare emergencies
15) Assist with emergency classification
16) Approve and direct offsite emergency notifications to state and local authorities
17) Direct notifications and ENS communications with the NRC
18) Ensure flow of information within and between the emergency response facilities
19) Perform or direct emergency PA announcements
20) Ensure minimum staff is available (facility staffed)
21) Determine current/projected staff needs
22) Ensure facility staff is prepared to perform their activities (facility ready)
23) Activate the facility (facility activated)
24) Direct/coordinate facility relocation
25) Determine and direct site response priorities
26) Support determination of site response priorities
27) Determine and direct the actions for mitigation strategies and contingency plans
28) Coordinate between CR, OSC and TSC to set OSC Team task priorities
29) Direct/support site assembly, accountability and search & rescue activities
30) Establish and maintain facility accountability
31) Coordinate site evacuation
32) Approve use of KI
33) Approve offsite Protective Action Recommendations
34) Approve emergency exposures
35) Ensure habitability is established and maintained for occupied areas
36) Terminate the emergency event
37) Develop recovery plans
38) Authorize and direct extreme measures (FLEX, EDMG, SAMG, §50.54(x) or security controls)
39) Conduct facility briefs and updates
40) Provide input for facility briefs and updates
41) Review and approval of deviations from Technical Specifications or license conditions.

[7.0.U, Recommendation 5i]

B. Offsite Communicator The Offsite Communicator reports to the Emergency Coordinator. Key responsibilities include:

1) Perform offsite emergency notifications to state and local authorities
2) Distribute forms, reports, etc. as needed C. Log Keeper The Log Keeper reports to the Emergency Coordinator. Key responsibilities include:

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1) Maintain status and information boards/displays D. ICP Liaison The ICP Liaison position is only filled during a security related event in which the offsite agencies activate the ICP. The ICP Liaison reports to the Emergency Coordinator. Key responsibilities include:
1) Communicate with ICP to provide information and coordination E. Security Coordinator The Security Coordinator reports to the Assistant Emergency Coordinator. Key responsibilities include:
1) Manage assigned group emergency response activities
2) Request and coordinate emergency activities with law enforcement agencies
3) Develop requests and coordinate external assistance (technical, craft, admin, etc.)
4) Arrange for equipment and supply resources
5) Communicate with ICP to provide information and coordination
6) Provide security related information to the NRC
7) Participate with OSC Team dispatch and control
8) Direct/support site assembly, accountability and search & rescue activities
9) Establish and maintain accountability for security personnel
10) Provide support and logistics for site evacuation activities
11) Direct site access controls activities
12) Ensure radiological conditions are known for occupied areas
13) Support MERT activities
14) Coordinate security activities
15) Provide input for facility briefs and updates F. Site Evacuation Coordinator The Site Evacuation Coordinator reports to the Assistant Emergency Coordinator. Key responsibilities include:
1) Develop facility 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing list
2) Establish and maintain facility accountability
3) Coordinate site evacuation G. OAC Support The OAC Support position reports to the Assistant Emergency Coordinator. Key responsibilities include:
1) Monitor facility equipment (e.g., computer, communications) for proper operation
2) Activate ERDS or confirm ERDS Operation H. IT Support The IT Support position reports to the Assistant Emergency Coordinator. Key responsibilities include:
1) Monitor facility equipment (e.g., computer, communications) for proper operation I. Engineering Manager The Engineering Manager reports to the Emergency Coordinator. Key responsibilities include:
1) Develop facility 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing list
2) Manage assigned group emergency response activities
3) Develop requests and coordinate external assistance (technical, craft, admin, etc.)

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4) Arrange for equipment and supply resources
5) Monitor status and information boards/displays/systems
6) Perform event detection and assessment activities
7) Support determination of site response priorities
8) Support development of mitigation strategies and contingency plans
9) Analyze and develop extreme measures actions (FLEX, EDMG, SAMG, §50.54(x))
10) Provide input for facility briefs and updates J. Reactor Engineer The Reactor Engineer reports to the Engineering Manager. Key responsibilities include:
1) Communicate on assigned communication line and provide information to facility staff
2) Monitor status and information boards/displays/systems
3) Perform event detection and assessment activities
4) Support development of mitigation strategies and contingency plans
5) Provide analysis of core damage and fission product release potential.

K. Electrical Engineer The Electrical Engineer reports to the Engineering Manager. Key responsibilities include:

1) Monitor status and information boards/displays/systems
2) Perform event detection and assessment activities
3) Support development of mitigation strategies and contingency plans L. Mechanical Engineer The Mechanical Engineer reports to the Engineering Manager. Key responsibilities include:
1) Monitor status and information boards/displays/systems
2) Perform event detection and assessment activities
3) Support development of mitigation strategies and contingency plans M. Operations Manager The Operations Manager reports to the Emergency Coordinator. Key responsibilities include:
1) Monitor status of the Emergency Operations Procedures
2) Manage assigned group emergency response activities
3) Develop requests and coordinate external assistance (technical, craft, admin, etc.)
4) Arrange for equipment and supply resources
5) Assist with emergency classification
6) Support completion of the ENF to state and local authorities
7) Monitor status and information boards/displays/systems
8) Perform event detection and assessment activities
9) Support determination of site response priorities
10) Support development of mitigation strategies and contingency plans
11) Coordinate between CR, OSC and TSC to set OSC Team task priorities
12) Evaluate conditions and develop offsite Protective Action Recommendations
13) Analyze and develop extreme measures actions (FLEX, EDMG, SAMG, §50.54(x))
14) Provide input for facility briefs and updates N. Assistant Operations Manager The Assistant Operations Manager reports to the Operations Manager. Key responsibilities include:
1) Monitor status of the Emergency Operations Procedures

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2) Assist with emergency classification
3) Communicate on assigned communication line and provide information to facility staff
4) Monitor status and information boards/displays/systems
5) Maintain status and information boards/displays
6) Perform event detection and assessment activities
7) Support development of mitigation strategies and contingency plans
8) Coordinate between CR, OSC and TSC to set OSC Team task priorities
9) Provide input for facility briefs and updates O. NRC Communicator The NRC Communicator reports to the Operations Manager. Key responsibilities include:
1) Provide event data and plant information to the NRC via the ENS
2) Activate ERDS or confirm ERDS operation
3) Monitor status and information boards/displays/systems P. CR Operations Bridge The CR Operations Bridge reports to the Operations Manager. Key responsibilities include:
1) Communicate on assigned communication line and provide information to facility staff
2) Perform event detection and assessment activities
3) Support development of mitigation strategies and contingency plans
4) Communicate the activities of Ops personnel dispatched out of the CR to the OSC Q. RP Manager The RP Manager reports to the Emergency Coordinator. Key responsibilities include:
1) Manage assigned group emergency response activities
2) Develop requests and coordinate external assistance (technical, craft, admin, etc.)
3) Arrange for equipment and supply resources
4) Assist with emergency classification
5) Support completion of the ENF to state and local authorities
6) Maintain status and information boards/displays
7) Perform event detection and assessment activities
8) Monitor, evaluate and communicate conditions involving any release of radioactivity
9) Direct/perform dose assessment
10) Brief and dispatch the onsite/offsite radiation monitoring teams
11) Provide support and logistics for site assembly activities
12) Provide support and logistics for site evacuation activities
13) Evaluate the need for and ensure proper use of KI
14) Evaluate conditions and develop offsite Protective Action Recommendations
15) Ensure approved emergency exposure controls are issued
16) Direct personnel monitoring and decontamination activities
17) Ensure habitability is established and maintained for occupied areas
18) Establish contamination controls for occupied areas
19) Support MERT activities
20) Provide input for facility briefs and updates R. Dose Assessor The Dose Assessor reports to the RP Manager. Key responsibilities include:
1) Assist with emergency classification

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2) Provide event data and plant information to the NRC via the HPN
3) Communicate on assigned communication line and provide information to facility staff
4) Monitor status and information boards/displays/systems
5) Prepare for facility activation (rooms, work area, equipment, etc.)
6) Maintain status and information boards/displays
7) Monitor, evaluate and communicate conditions involving any release of radioactivity
8) Direct/perform dose assessment
9) Direct field monitoring team activities
10) Evaluate conditions and develop offsite Protective Action Recommendations
11) Establish facility ventilation and monitoring for habitability controls 2.4.3 Operations Support Center The OSC Organization Chart is show in Figure 2.4-3.

A. OSC Manager/Assistant OSC Manager The OSC Manager reports to the Emergency Coordinator. The Assistant OSC Manager reports to the OSC Manager. The OSC Manager and Assistant OSC Manager positions are equally qualified. Key responsibilities include:

1) Develop facility 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing list
2) Verify that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing list has been completed
3) Coordinate ERO/facility shift turnover
4) Manage facility emergency response activities
5) Develop requests and coordinate external assistance (technical, craft, admin, etc.)
6) Arrange for equipment and supply resources
7) Ensure flow of information within and between the emergency response facilities
8) Prepare for facility activation (rooms, work area, equipment, etc.)
9) Ensure minimum staff is available (facility staffed)
10) Determine current/projected staff needs
11) Ensure facility staff is prepared to perform their activities (facility ready)
12) Activate the facility (facility activated)
13) Direct/coordinate facility relocation
14) Support facility relocation
15) Support determination of site response priorities
16) Coordinate between CR, OSC and TSC to set OSC Team task priorities
17) Coordinate OSC Team dispatch and control
18) Participate with OSC Team dispatch and control
19) Direct/support site assembly, accountability and search & rescue activities
20) Establish and maintain facility accountability
21) Ensure habitability is established and maintained for occupied areas
22) Conduct facility briefs and updates
23) Provide input for facility briefs and updates B. Log Keeper The Log Keeper reports to the OSC Manager. Key responsibilities include:
1) Develop facility 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing list
2) Ensure minimum staff is available (facility staffed)
3) Maintain status and information boards/displays
4) Participate with OSC Team dispatch and control

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C. Maintenance Supervisor The Maintenance Supervisor reports to the OSC Manager. Key responsibilities include:

1) Manage assigned group emergency response activities
2) Develop requests and coordinate external assistance (technical, craft, admin, etc.)
3) Arrange for equipment and supply resources
4) Participate with OSC Team dispatch and control
5) Provide input for facility briefs and updates D. Operations Supervisor The Operations Supervisor reports to the OSC Manager. Key responsibilities include:
1) Manage assigned group emergency response activities
2) Develop requests and coordinate external assistance (technical, craft, admin, etc.)
3) Arrange for equipment and supply resources
4) Monitor status and information boards/displays/systems
5) Participate with OSC Team dispatch and control
6) Provide input for facility briefs and updates E. Operations Liaison The Operations Liaison reports to the Operations Supervisor. Key responsibilities include:
1) Communicate on assigned communication line and provide information to facility staff
2) Monitor status and information boards/displays/systems
3) Participate with OSC Team dispatch and control F. RP Supervisor The RP Supervisor reports to the OSC Manager. Key responsibilities include:
1) Manage assigned group emergency response activities
2) Develop requests and coordinate external assistance (technical, craft, admin, etc.)
3) Arrange for equipment and supply resources
4) Communicate on assigned communication line and provide information to facility staff
5) Monitor status and information boards/displays/systems
6) Perform radiological sampling and surveys
7) Record/review radiological sampling and survey data
8) Participate with OSC Team dispatch and control
9) Establish and maintain facility accountability
10) Track emergency worker exposure and evaluate the need for dose extensions
11) Coordinate the monitoring of site evacuees
12) Ensure habitability is established and maintained for occupied areas
13) Establish contamination controls for occupied areas
14) Provide input for facility briefs and updates G. Field Monitoring Team Member The Field Monitoring Team members initially report to the RP Supervisor, until turned over to the TSC Dose Assessor or EOF Field Team Coordinator. Key responsibilities include:
1) Communicate on assigned communication line and provide information to facility staff
2) Performs radiological sampling and surveys
3) Record/review radiological sampling and survey data
4) Identify airborne plumes or liquid effluents
5) Participate with OSC Team dispatch and control

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H. Chemistry Supervisor The Chemistry Supervisor reports to the OSC Manager. Key responsibilities include:

1) Manage assigned group emergency response activities
2) Develop requests and coordinate external assistance (technical, craft, admin, etc.)
3) Arrange for equipment and supply resources
4) Perform event detection and assessment activities
5) Perform chemical sampling and analysis
6) Record/review chemical sampling and analysis
7) Participate with OSC Team dispatch and control
8) Provide input for facility briefs and updates I. Operations and Craft Personnel Additional Ops, Maintenance, RP and Chemistry personnel report to their associated supervisor in the OSC. Response activities involve their current job tasks.
1) Participate with OSC Team dispatch and control J. Generation Supply Chain Liaison The Generation Supply Chain Liaison reports to the OSC Manager. Key responsibilities include:
1) Develop requests and coordinate external assistance (i.e., technical, craft, admin)
2) Arrange for equipment and supply resources
3) Arrange for logistics support
4) Prepare for facility activation (i.e., rooms, work area, equipment)
5) Participate with OSC Team dispatch and control
6) Serve as primary point of contact for SAFER and FLEX support K. Fire Brigade When conditions require activation of the emergency facilities, the on-shift Fire Brigade is incorporated into the Operational Support Center.

The Fire Brigade consists of a Shift Incident Commander, and a minimum of four fire brigade members who provide fire brigade, search and rescue, chemical/hazardous materials response, and confined space entry services. Fire Brigade members will be the on-shift operators, or other personnel qualified as Fire Brigade members. The Fire Brigade, when incorporated into the OSC, functions as a team under the direction of the Operations Supervisor. The Fire Brigade is staffed on a 24-hour basis.

L. Medical Emergency Response Team (MERT)

MERT provides first aid to plant personnel and is made up from personnel in the Security department. MERT members will be the on-shift security officers qualified in first aid. MERT is staffed on a 24-hour basis. Upon activation of the Emergency Response Facilities, the Medical Emergency Response Team reports to the OSC, as a unit, and provides medical response as well as their other Security duties.

2.4.4 Emergency Operations Facility (EOF)

The EOF Organization Chart is show in Figure 2.4-4.

A. EOF Director/Assistant EOF Director The EOF Director is the head of the ERO and directs the overall response. The Assistant EOF Director reports to the EOF Director and manages the operation of the EOF. The EOF Director and Assistant EOF Director positions are equally qualified. Key responsibilities include:

1) Coordinate response activities with offsite response agencies (i.e., EM, ICP, Field Mon)

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2) Verify that the 24-hour staffing list has been completed
3) Coordinate ERO/facility shift turnover
4) Perform position turnover when a shift change occurs
5) Assume/maintain command and control
6) Transfer command and control
7) Manage facility emergency response activities
8) Coordinate integration of the NRC site team
9) Prioritize and authorize requests for external assistance (i.e., technical, craft, admin)
10) Approve equipment, supply, and logistics expenditures for response to the event
11) Request Federal support and resources
12) Assist with emergency classification
13) Approve and direct offsite emergency notifications to state and local authorities
14) Ensure flow of information within and between the emergency response facilities
15) Perform or direct emergency PA announcements
16) Provide technical assistance for the development of news releases and statements
17) Ensure minimum staff is available (facility staffed)
18) Determine current/projected staff needs
19) Ensure facility staff is prepared to perform their activities (facility ready)
20) Activate the facility (facility activated)
21) Direct/coordinate facility relocation
22) Determine and direct the actions for mitigation strategies and contingency plans
23) Approve offsite Protective Action Recommendations
24) Terminate the emergency event
25) Develop recovery plans
26) Conduct facility briefs and updates B. Log Keeper The Log Keeper reports to the EOF Director. Key responsibilities include:
1) Distribute forms, reports, etc. as needed
2) Maintain status and information boards/displays C. Data Coordinator The Data Coordinator reports to the EOF Director. Key responsibilities include:
1) Monitor facility equipment (computer, communications, etc.) for proper operation D. Emergency Planner The Emergency Planner reports to the EOF Director. Key responsibilities include:
1) Coordinate information and activities with offsite agency personnel in the facility
2) Coordinate integration of the NRC site team
3) Support State/County EOC Liaisons
4) Support completion of the ENF to state and local authorities
5) Prepare for facility activation (rooms, work area, equipment, etc.)
6) Provide input for facility briefs and updates E. State and County Liaisons The State and County Liaisons are staffed by site personnel and report to the Emergency Planner. Key responsibilities include:
1) Coordinate information with government officials/agencies

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2) Report status of state and county emergency response activities from the EOCs F. Accident Assessment Manager The Accident Assessment Manager reports to the EOF Director. Key responsibilities include:
1) Develop requests and coordinate external assistance (i.e., technical, craft, admin)
2) Arrange for equipment and supply resources
3) Assist with emergency classification
4) Perform event detection and assessment activities
5) Evaluate conditions and develop offsite Protective Action Recommendations
6) Provide input for facility briefs and updates G. Accident Assessment Interface The Accident Assessment Interface reports to the Accident Assessment Manager. Key responsibilities include:
1) Monitor status of the Emergency Operations Procedures
2) Assist with emergency classification
3) Communicate on assigned communication line and provide information to facility staff
4) Monitor status and information boards/displays/systems
5) Maintain status and information boards/displays
6) Perform event detection and assessment activities
7) Provide analysis of core damage and fission product release potential
8) Evaluate conditions and develop offsite Protective Action Recommendations
9) Analyze and develop extreme measures actions (FLEX, EDMG, SAMG, §50.54(x))

H. Radiological Assessment Manager The Radiological Assessment Manager reports to the EOF Director. Key responsibilities include:

1) Manage assigned group emergency response activities
2) Develop requests and coordinate external assistance (i.e., technical, craft, admin)
3) Assist with emergency classification
4) Support completion of the ENF to state and local authorities
5) Communicate on assigned communication line and provide information to facility staff
6) Monitor status and information boards/displays/systems
7) Perform event detection and assessment activities
8) Monitor, evaluate and communicate conditions involving any release of radioactivity
9) Direct/perform dose assessment
10) Brief and dispatch the onsite/offsite radiation monitoring teams
11) Provide support and logistics for site evacuation activities
12) Evaluate conditions and develop offsite Protective Action Recommendations
13) Direct post-accident environmental sampling and exposure activities
14) Provide input for facility briefs and updates I. Dose Assessor The Dose Assessor reports to the Radiological Assessment Manager. Key responsibilities include:
1) Assist with emergency classification
2) Support completion of the ENF to state and local authorities
3) Provide event data and plant information to the NRC via the HPN

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4) Communicate on assigned communication line and provide information to facility staff
5) Monitor status and information boards/displays/systems
6) Prepare for facility activation (i.e., rooms, work area, equipment)
7) Monitor, evaluate and communicate conditions involving any release of radioactivity
8) Direct/perform dose assessment
9) Evaluate conditions and develop offsite Protective Action Recommendations J. Field Monitoring Coordinator The Field Monitoring Coordinator reports to the Radiological Assessment Manager. Key responsibilities include:
1) Maintain status and information boards/displays
2) Brief and dispatch the onsite/offsite radiation monitoring teams
3) Direct field monitoring team activities
4) Coordinate activities with the external agency field monitoring teams.
5) Coordinate the receipt, analysis, storage and transfer of field monitoring samples
6) Record/review radiological sampling and survey data K. Offsite Communicator The Offsite Communicator reports to the EOF Director. Key responsibilities include:
1) Provide event notification/information to industry groups (i.e., INPO, ANI)
2) Perform offsite emergency notifications to state and local authorities
3) Support completion of the ENF to state and local authorities
4) Distribute forms, reports, etc. as needed L. Services Manager The Services Manager reports to the EOF Director. Key responsibilities include:
1) Develop requests and coordinate external assistance (i.e., technical, craft, admin)
2) Arrange for equipment and supply resources
3) Provide event notification/information to industry groups (i.e., INPO, ANI)

M. Services Admin/Commissary The Services Admin / Commissary reports to the Services Manager. Key responsibilities include:

1) Develop facility 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing list
2) Manage assigned group emergency response activities
3) Arrange for logistics support
4) Provide administrative support for facility operation
5) Distribute forms, reports, et al, as needed 2.4.5 Nuclear Public Information Group The JIC Organization Chart is show in Figure 2.4-5.

A. Company Spokesperson (MC/Near Site JIC/Corporate JIC)

The Company Spokesperson reports to the EOF Director. Key responsibilities include:

1) Coordinate information with government officials/agencies
2) Coordinate information to the Incident Support Team
3) Approve/review news releases, statements and messages
4) Perform media briefings and interviews
5) Correct rumors in media briefings and interviews
6) Provide input for facility briefs and updates B. Information Gathering Lead (Near-Site JIC)

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The Information Gathering Lead reports to the Corporate Communications Lead PIO (a corporate non-nuclear position not part of the site emergency plan). Key responsibilities include:

1) Manage assigned group emergency response activities
2) Coordinate distribution of news releases, statements and messages
3) Coordinate development of a communications strategy
4) Assist the Company Spokesperson in gathering information for media briefings and interviews
5) Coordinate the conduct of media briefings and interviews
6) Coordinate information flow between the station, corporate JIC and Federal, State &

local PIOs

7) Perform rumor control activities C. Media Monitor (Near Site JIC)

The Media Monitor reports to the Information Gathering Lead. Key responsibilities include:

1) Monitor media outlets for event related information
2) Coordinate monitoring activities with public information personnel
3) Perform rumor control activities
4) Monitor facility equipment (computer, communications, etc.) for proper operation D. JIC Technical Liaison (Near Site JIC)

The JIC Technical Liaison reports to the Information Gathering Lead. Key responsibilities include:

1) Communicate on assigned communication line and provide information to facility staff
2) Provide technical assistance for the development of news releases and statements
3) Provide support for the development of the chronology of events
4) Provide site event and response information for public information staff
5) Perform rumor control activities
6) Provide input for facility briefs and updates E. News Writer (EOF)

The News Writer reports to the Corporate Communications Lead PIO (a corporate non-nuclear position not part of the site emergency plan). Key responsibilities include:

1) Develop news releases, statements and messages
2) Coordinate distribution of news releases, statements and messages F. EOF Technical Liaison (EOF)

The EOF Technical Liaison reports to the Corporate Communications Lead PIO (a corporate non-nuclear position not part of the site emergency plan). Key responsibilities include:

1) Communicate on assigned communication line and provide information to facility staff
2) Provide technical assistance for the development of news releases and statements
3) Provide site event and response information for public information G. Media Center Coordinator (Media Center)

The Media Center Coordinator reports to the Logistics Lead. Key responsibilities include:

1) Arrange for equipment and supply resources
2) Arrange for logistics support
3) Coordinate distribution of news releases, statements and messages
4) Register personnel at the assigned location

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5) Coordinate accommodation of news media personnel
6) Monitor facility entrance areas
7) Prepare for facility activation (rooms, work area, equipment, etc.)

H. Site JIC Manager (Near Site JIC)

The Site JIC Manager reports to the Corporate Communications Lead PIO (a corporate non-nuclear position not part of the site emergency plan). Key responsibilities include:

1) Develop facility 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing list
2) Manage facility emergency response activities
3) Coordinate integration of the NRC site team
4) Ensure flow of information within and between the emergency response facilities
5) Coordinate information flow between the station, corporate JIC and Federal, State &

local PIOs

6) Prepare for facility activation (rooms, work area, equipment, etc.)
7) Ensure minimum staff is available (facility staffed)
8) Ensure facility staff is prepared to perform their activities (facility ready)
9) Activate the facility (facility activated)
10) Develop recovery plans
11) Conduct facility briefs and updates I. Logistics Lead (Near Site JIC)

The Logistics Lead reports to the Site JIC Manager. Key responsibilities include:

1) Coordinate ERO/facility shift turnover
2) Manage assigned group emergency response activities
3) Arrange for logistics support
4) Make staffing notifications
5) Coordinate JIC security and media badging
6) Prepare for facility activation (rooms, work area, equipment, etc.)
7) Determine current/projected staff needs
8) Provide administrative support for facility operation J. Admin Support (Near Site JIC)

The Admin Support position reports to the Logistics Lead. Key responsibilities include:

1) Coordinate distribution of news releases, statements and messages K. Government Liaison (Near Site JIC)

The Government Liaison reports to the Logistics Lead. Key responsibilities include:

1) Coordinate information and activities with offsite agency personnel in the facility
2) Coordinate information with government officials/agencies
3) Arrange for logistics support
4) Coordinate distribution of news releases, statements and messages
5) Coordinate information flow between the utility, corporate JIC and Federal, State and local PIOs L. Registration Liaison (Near Site JIC)

The Registration Liaison reports to the Logistics Lead. Key responsibilities include:

1) Register personnel at the assigned location
2) Monitor facility entrance areas
3) Prepare for facility activation (rooms, work area, equipment, etc.)

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4.5.2 Protective Action Recommendations (PARs)

A. Protective action guidelines for the plume pathway EPZ are based on NUREG-0654 Supplement 3, "Criteria for Protective Action Recommendations for Severe Accidents."

B. Plant conditions, projected dose and dose rates, and/or field monitoring data are evaluated to develop PARs for the purpose of preventing or minimizing exposure to the general public. PARs are made to the State and County agencies that are responsible for implementing protective actions for the general public wherever PAGs are exceeded. PARs are approved by the EOF Director. In an emergency which requires immediate protective actions be taken prior to activation of the emergency facilities, notification approval is given by the EC-MCR directly to the State and County agencies.

4.5.2.C. Possible recommendations issued by HNP at a General Emergency include, but are not limited to:

1) Evacuation of the general public within the two (2) mile radius and five (5) miles downwind.
2) Evacuation of the general public within the five (5) mile radius and ten (10) miles downwind. (This specific change was evaluated under EREG 2172381) , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

Licensing Basis of the Structure, Positions and Responsibilities of Augmentation Personnel ERO:

HNP Emergency Plan revision 68 reflects the current NRC approved augmenting ERO and is used as the basis for the detailed comparison and evaluation provided in enclosures 1, 2, and 3.

The proposed changes included a review of the following HNP emergency plan licensing basis documents:

  • NRC approval of Emergency Plan changes in HNP amendment 160 dated August 21, 2017 This review concludes that changes described do not adversely affect the licensing basis of the emergency plan.

List Commitments Associated with the Change:

A search to identify site specific commitments related to the ERO positions and their assigned responsibilities was performed. No site specific commitments regarding any position or associated responsibility were identified.

Licensing Basis of the EOF for Harris Nuclear Plant was adjusted in HNP amendment 160 dated August 21, 2017. The adjustment of the response time requirements for augmented ERO was also approved in this same amendment. The proposed changes to the Emergency Plan PLP-201 revision 68 implement these adjusted licensing basis for the adjusted augmentation time limits and for the Duke fleet Common EOF in Charlotte NC.

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RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.
c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The listed changes to the HNP Emergency Plan have been reviewed and determined to meet the regulatory requirements and will adhere to the requirements as amended via HNP license amendment 160 dated August 21, 2017.

Given that the changes associated with the adoption of the Common EOF and response times have already been approved by the NRC in HNP license amendment 160; the balance of this effectiveness evaluation will be limited to the non-editorial changes to the Emergency Plan associated with the changes to ERO position titles, responsibilities, and actions.

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Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

The number of ERO responders for facility and response time changes resulting from the adoption of the standard ERO establish a closer relationship between risk significant / key functions and the positions assigned those functions. The objective of the changes is to ensure that those functions and their processes are linked directly to the augmented minimum staffing positions to allow for optimum relief of on shift personnel and less complicated response execution following facility activation.

Refer to enclosures 2 and 3 for a detailed review of the differences between the current HNP augmenting ERO and the standard augmenting ERO, and the evaluation of those changes from the organizational hierarchy, position and response, and task-by-task levels.

The adoption of the standard augmenting ERO into the HNP emergency plan implementing procedures: (1) provides a response organization defined by specific structure and responsibilities, which is consistent with regulations and industry guidance, and (2) maintains an efficient augmentation capability for both minimum staffing and full staffing positions.

The adoption of the standard augmenting ERO into the HNP emergency plan implementing procedures does not alter the licensing basis and continues to meet the regulatory requirements of 10CFR50.47(b)(1), (b)(2), (b)(7), and 10CFR50 Appendix E, Section IV.A. This change does not alter, add or remove previous site specific commitments with regards to the augmenting ERO.

The adoption of a fleet standard recovery organization and plan into the HNP emergency plan implementing procedures provides a flexible recovery organization based on the complexity of the event or recovery plan. This new recovery organization and plan is based on the current recovery organization and plan in place at HNP which has been evaluated in numerous drills and exercises. The adoption of a fleet standard recovery organization into the HNP emergency plan implementing procedures does not alter the licensing basis and continues to meet the regulatory requirements of 10CFR50.47(b)(13). This change does not alter, add or remove previous site specific commitments with regards to the recovery organization and plan.

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Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

The following portion of planning standard §50.47(b)(1) is associated with the proposed changes:

Primary responsibilities for emergency response by the nuclear facility licensee have been assigned, and each principal response organization has staff to augment its initial response on a continuous basis.

The functions for §50.47(b)(1) related to this change are:

a. Responsibility for emergency response is assigned.
b. The response organization has the staff to respond and augment on a continuing basis (24/7 staffing) in accordance with the E-plan.

The following portions of §50 Appendix E,Section IV.A are associated with the proposed changes:

The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

1. A description of the normal plant operating organization.
2. A description of the onsite emergency response organization (ERO) with a detailed discussion of:
a. Authorities, responsibilities, and duties of the individual(s) who will take charge during an emergency;
b. Plant staff emergency assignments;
c. Authorities, responsibilities, and duties of an onsite emergency coordinator who shall be in charge of the exchange of information with offsite authorities responsible for coordinating and implementing offsite emergency measures.
3. A description, by position and function to be performed, of the licensee's headquarters personnel who will be sent to the plant site to augment the onsite emergency organization.
4. Identification, by position and function to be performed, of persons within the licensee organization who will be responsible for making offsite dose projections, and a description of how these projections will be made and the results transmitted to State and local authorities, NRC, and other appropriate governmental entities.
5. Identification, by position and function to be performed, of other employees of the licensee with special qualifications for coping with emergency conditions that may arise. Other persons with special qualifications, such as consultants, who are not employees of the licensee and who may be called upon for assistance for emergencies shall also be identified. The special qualifications of these persons shall be described.
6. A description of the local offsite services to be provided in support of the licensee's emergency organization.

The NUREG-0654 Part II.A elements for §50.47(b)(1) related to this change are:

1.d. Each organization shall identify a specific individual by title who shall be in charge of the emergency response.

4. Each principal organization shall be capable of continuous (24-hour) operations for a protracted period. The individual in the principal organization who will be responsible for assuring continuity of resources (technical, administrative, and material) shall be specified by title.

The following portion of planning standard §50.47(b)(2) is associated with the proposed changes:

, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

The function for §50.47(b)(2) related to this change is:

b. Process for timely augmentation of on shift staff is established and maintained.

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The following portions of §50 Appendix E,Section IV.A are associated with the proposed changes:

The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

2. A description of the onsite emergency response organization (ERO) with a detailed discussion of:
a. Authorities, responsibilities, and duties of the individual(s) who will take charge during an emergency;
b. Plant staff emergency assignments;
c. Authorities, responsibilities, and duties of an onsite emergency coordinator who shall be in charge of the exchange of information with offsite authorities responsible for coordinating and implementing offsite emergency measures.
3. A description, by position and function to be performed, of the licensee's headquarters personnel who will be sent to the plant site to augment the onsite emergency organization.
4. Identification, by position and function to be performed, of persons within the licensee organization who will be responsible for making offsite dose projections, The NUREG-0654 Part II.B elements for §50.47(b)(2) related to this change are:
3. Each licensee shall identify a line of succession for the emergency coordinator position and identify the specific conditions for higher level utility officials assuming this function.
4. Each licensee shall establish the functional responsibilities assigned to the emergency coordinator and shall clearly specify which responsibilities may not be delegated to other elements of the emergency organization.

Among the responsibilities which may not be delegated shall be the decision to notify and to recommend protective actions to authorities responsible for offsite emergency measures.

5. Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table B-1 entitled, Minimum Staffing Requirements for Nuclear Power Plant Emergencies. The licensee must be able to augment on-shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table B-1.
7. Each licensee shall specify the corporate management, administrative, and technical support personnel who will augment the plant staff as specified in the table entitled "Minimum Staffing Requirements for Nuclear Power Plant Emergencies," (Table B-1)

The following portion of planning standard §50.47(b)(7) is related to the change in adopting the standard augmenting ERO:

Information is made available to the public on a periodic basis on how they will be notified and what their initial actions should be in an emergency (e.g., listening to a local broadcast station and remaining indoors), the principal points of contact with the news media for dissemination of information during an emergency (including the physical location or locations) are established in advance, and procedures for coordinated dissemination of information to the public are established.

The function for §50.47(b)(7) related to this change are:

b. Coordinated dissemination of public information during emergencies is established.

The NUREG-0654 Part II.G elements for §50.47(b)(5) related to this change are:

4.a Each principal organization shall designate a spokesperson who should have access to all necessary information.

The following portion of planning standard §50.47(b)(13) is associated with the change in adopting the standard recovery organization and plan:

General plans for recovery and reentry are developed.

The function for §50.47(b)(13) related to this change are:

a. Plans for recovery and reentry are developed.

There are no applicable portions of §50 Appendix E, associated with the proposed changes

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The NUREG-0654 Part II.M elements for §50.47(b)(13) related to this change are:

M.1 Each organization, as appropriate, shall develop general plans and procedures for reentry and recovery and describe the means by which decisions to relax protective measures (e.g., allow reentry into an evacuated area) are reached. This process should consider both existing and potential conditions.

M.2 Each licensee plan shall contain the position/title, authority and responsibilities of individuals who will fill key positions in the facility recovery organization. This organization shall include technical personnel with responsibilities to develop, evaluate and direct recovery and reentry operations.

M.3 Each licensee and State plan shall specify means for informing members of the response organizations that a recovery operation is to be initiated, and of any changes in the organizational structure that may occur.

M.4 Each plan shall establish a method for periodically estimating total population exposure.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

1. Capability Assessment All emergency response related functions and tasks performed by the current HNP augmenting ERO have been dispositioned against the standard ERO positions as documented in enclosures 2 and 3. Changes to ERO task assignments categorized as deviations were evaluated and determined not to degrade the capability to perform their particular function.

Additionally, all ERO tasks for each position have been formally defined, indexed to their corresponding planning standard, and listed in the body of the emergency plan. These tasks can now be readily adopted into the ERO systematic approach to training (SAT) based qualification process and easily associated with the drill and exercise evaluation performance objectives and demonstration criteria. Thus, the capability to determine performance vs.

process issues and feedback to training of task level items is significantly improved.

2. Timeliness Assessment The standard augmenting ERO, with minor modification, is based on the current augmenting ERO in place at CNS, MNS and ONS which has been evaluated in numerous drills and exercises. There are no changes to the on-shift ERO as part of the standard augmenting ERO initiative.

The aspect of timeliness with regard to the ability of any position to perform their assigned responsibilities was further evaluated by a review of the impact of any new tasks assigned to a position by a process similar to that used in the on-shift staffing study task analysis (it was assumed there was no timeliness impact for positions that were not assigned new tasks or were only assigned new tasks which were determined to be undocumented and were actually performed by the position. New tasks are categorized as deviations). The aspects of overburden and overlap were considered in the determination of whether there was a potential adverse impact on timeliness to any assigned task. No position was identified with task overburden or overlap with regard to the addition of any responsibilities.

To adopt the standard ERO, the HNP ERO number of 75 minute response positions was increased in the Notification and Communications functional area (State/County) and reduced in the area of middle level ERF supervisors primarily in the Plant System Engineering, Repair, and Corrective Actions functional area. Accident Analysis engineers and repair and corrective action craft personnel minimum staffing requirements were not altered, which maintains the ability to perform those functions in a timely manner.

Adoption of the standard augmenting ERO will allow HNP to utilize the common EOF that is staffed by personnel in the corporate office. This will provide a significant pool of personnel, from senior management to craft level, previously assigned to the EOF which are now available for response positions in the HNP TSC or OSC. This will provide the opportunity to improve augmentation of the 75 minute minimum staffing positions for the site ERO.

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The adoption of the standard ERO made changes to the functional procedures for Field Monitoring, Classification, Protective Action Recommendations (PARs), and Notification.

  • Classification - The EAL scheme, based on NEI 99-01 rev. 6, is not changing. Therefore, this is not a Reduction in Effectiveness (RIE)
  • PARs - PARs are still based on NUREG-0654 Supplement 3. Current PAR flow charts were moved to new Fleet PAR procedures so this is not a RIE.
  • Notification - The ENF is not changing and HNP is still using WebEOC and DEMNET to transmit the information so this is not a RIE.
  • Field Monitoring - HNP will still have the capability, radiological equipment, and communication methods.

The coordination of team activities will continue to be performed from the EOF, only from a different location with capable communications, and back-up systems available. Therefore this is not a RIE.

Proposed changes described under the 'Standard ERO Changes" are in conjunction with the common EOF LAR submittal, and a program initiative undertaken by Duke Energy to standardize the augmenting ERO positions, functions and responsibilities (tasks), and procedures across the fleet. The proposed changes do not affect the emergency planning functions associated with 10 CFR 50.47(b) described in Part IV of this evaluation.

Based on the above, the adoption of the standard augmenting ERO will continue to maintain or improve the capability and timeliness of the HNP augmenting ERO to respond to an event and effectively perform their assigned tasks.

The changes described provide additional assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure protection of the public health and safety; and
  • effectively use response equipment and emergency response procedures These changes support the Harris Nuclear Plant Emergency Plan, PLP-201 by ensuring that procedures used during response to a classified emergency are available. Effective use of these procedures helps ensure emergency response capabilities described in the Harris Nuclear Plant Emergency Plan are adequately maintained and demonstrated.

The changes described do not reduce the effectiveness of the Harris Nuclear Plant Emergency Plan, as written and approved; and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

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Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4). If CFAM approval is NOT required, then mark the CFAM signature block as not applicable (N/A) to indicate that signature is not required.

Preparer Name (Print): Preparer Signature: Date:

Jamey Sharlow signed electronically in CAS 01/04/18 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 01/04/18 Approver (EP Manager) Name (Print): Approver Signature: Date:

Gregg Simmons signed electronically in CAS 01/04/18 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.6, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:____2172381_______________ CNS CR3 HNP MNS 5AD #:_____2163338________________ ONS RNP GO Document and Revision PEP-110, rev 28 Emergency Classification and Protective Action Recommendations Part I. Description of Proposed Change:

This screening and evaluation will review specific changes not covered by EREG 2163340. EREG 2163340 was performed prior to the latest changes identified in this description of changes. The changes identified here will be incorporated in revision 28 of PEP-110 Emergency Classification and Protective Action Recommendations. Both EREGS (2172381 and 2163340) will screen and evaluate all changes identified and will be cross referenced together to maintain the total revision screen and evaluation.

The description of activities that is being reviewed by this screening and evaluation are:

Section 3.3.3.a changed from:

For Rapidly Progressing Severe Accident (RPSA)

  • Evacuate 2 mile radius and 10 miles downwind
  • Shelter remaining subzones to For Rapidly Progressing Severe Accident (RPSA)
  • Evacuate 2 mile radius and 10 miles downwind Section 3.3.3.c changed from:

If no RPSA, HAB, OR known offsite impediment is present:

  • Evacuate 2 mile radius and 5 miles downwind
  • Shelter remaining subzones to If no RPSA, HAB, OR known offsite impediment is present:
  • Evacuate 2 mile radius and 5 miles downwind

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Section 3.3.4.b changed from:

If no RPSA, HAB, known offsite impediment, OR short term release is present AND General Emergency conditions still exist:

  • Evacuate 2 mile radius and 5 miles downwind
  • Shelter remaining subzones to If no RPSA, HAB, known offsite impediment, OR short term release is present AND General Emergency conditions still exist:
  • Evacuate 2 mile radius and 5 miles downwind Section 4.2.2 changed from:

Evacuation of a 2 mile radius and 10 miles downwind (with sheltering of all other Subzones) will be recommended for plant conditions which meet the following Rapidly Progressing Severe Accident (RPSA) criteria:

to Evacuation of a 2 mile radius and 10 miles downwind will be recommended for plant conditions which meet the following Rapidly Progressing Severe Accident (RPSA) criteria:

Section 4.3.3.a changed from:

IF General Emergency conditions still exist, THEN evacuate a two mile radius and five miles downwind. Shelter the remaining subzones.

to IF General Emergency conditions still exist, THEN evacuate a two mile radius and five miles downwind. - Protective Action Recommendation Process (Sheet 1 of 3)

Changed block wording from:

Table 1

  • Evacuate 2 mile radius and 10 miles downwind
  • Shelter remaining subzones to
  • Evacuate 2 mile radius and 10 miles downwind Table 3
  • Evacuate 2 mile radius and 5 miles downwind
  • Shelter remaining subzones to
  • Evacuate 2 mile radius and 5 miles downwind

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Changed block wording from:

Table 3

  • Evacuate 2 mile radius and 5 miles downwind
  • Shelter remaining zones to
  • Evacuate 2 mile radius and 5 miles downwind - Protective Action Recommendation Process (Sheet 3 of 3)

Changed Table 1 from:

Table 1 Rapidly Progressing Severe Accident (RPSA) 2 Mile Radius and 10 Miles Downwind Wind Direction (From °) Evacuate Subzones Shelter Subzones 011°-034° A, H, I, J, K B, C, D, E, F, G, L, M, N 035°-056° A, I, J, K, M B, C, D, E, F, G, H, L, N 057°-079° A, I, J, K, L, M B, C, D, E, F, G, H, N 080°-101° A, J, K, L, M B, C, D, E, F, G, H, I, N 102°-124° A, J, K, L, M, N B, C, D, E, F, G, H, I 125°-146° A, B, L, M, N C, D, E, F, G, H, I, J, K 147°-191° A, B, E, L, M, N C, D, F, G, H, I, J, K 192°-214° A, B, E, N C, D, F, G, H, I, J, K, L, M 215°-236° A, B, C, E, F D, G, H, I, J, K, L, M, N 237°-259° A, B, C, E, F, G D, H, I, J, K, L, M, N 260°-281° A, B, C, D, F, G, H E, I, J, K, L, M, N 282°-304° A, C, D, F, G, H B, E, I, J, K, L, M, N 305°-326° A, C, D, F, G, H, K B, E, I, J, L, M, N 327°-347° A, D, G, H, I, K B, C, E, F, J, L, M, N 348°-010° A, D, H, I, K B, C, E, F, G, J, L, M, N to Table 1 Rapidly Progressing Severe Accident (RPSA) 2 Mile Radius and 10 Miles Downwind Wind Direction (From °) Evacuate Subzones 011°-034° A, H, I, J, K 035°-056° A, I, J, K, M 057°-079° A, I, J, K, L, M 080°-101° A, J, K, L, M 102°-124° A, J, K, L, M, N 125°-146° A, B, L, M, N 147°-191° A, B, E, L, M, N 192°-214° A, B, E, N 215°-236° A, B, C, E, F 237°-259° A, B, C, E, F, G 260°-281° A, B, C, D, F, G, H 282°-304° A, C, D, F, G, H 305°-326° A, C, D, F, G, H, K 327°-347° A, D, G, H, I, K 348°-010° A, D, H, I, K

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Changed Table 2 from:

Table 2 Shelter - 2 Mile Radius and 5 Miles Downwind Wind Direction (From °) Shelter Subzones No Action Subzones 327° - 010° A,D,K B,C,E,F,G,H,I,J,L,M,N 011° - 056° A,K B,C,D,E,F,G,H,I,J,L,M,N 057° - 124° A,K,L B,C,D,E,F,G,H,I,J,M,N 125° - 191° A,B,L C,D,E,F,G,H,I,J,K,M,N 192° - 214° A,B C,D,E,F,G,H,I,J,K,L,M,N 215° - 259° A,B,C D,E,F,G,H,I,J,K,L,M,N 260° - 281° A,C B,D,E,F,G,H,I,J,K,L,M,N 282° - 304° A,C,D B,E,F,G,H,I,J,K,L,M,N 305° - 326° A,D B,C,E,F,G,H,I,J,K,L,M,N To Table 2 Shelter - 2 Mile Radius and 5 Miles Downwind Wind Direction Shelter Subzones (From °)

327° - 010° A,D,K 011° - 056° A,K 057° - 124° A,K,L 125° - 191° A,B,L 192° - 214° A,B 215° - 259° A,B,C 260° - 281° A,C 282° - 304° A,C,D 305° - 326° A,D Changed Table 3 from:

Table 3 Shelter - 2 Mile Radius and 5 Miles Downwind Wind Direction (From °) Evacuate Subzones Shelter Subzones 327° - 010° A,D,K B,C,E,F,G,H,I,J,L,M,N 011° - 056° A,K B,C,D,E,F,G,H,I,J,L,M,N 057° - 124° A,K,L B,C,D,E,F,G,H,I,J,M,N 125° - 191° A,B,L C,D,E,F,G,H,I,J,K,M,N 192° - 214° A,B C,D,E,F,G,H,I,J,K,L,M,N 215° - 259° A,B,C D,E,F,G,H,I,J,K,L,M,N 260° - 281° A,C B,D,E,F,G,H,I,J,K,L,M,N 282° - 304° A,C,D B,E,F,G,H,I,J,K,L,M,N 305° - 326° A,D B,C,E,F,G,H,I,J,K,L,M,N

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To Table 3 Shelter - 2 Mile Radius and 5 Miles Downwind Wind Direction (From °) Evacuate Subzones 327° - 010° A,D,K 011° - 056° A,K 057° - 124° A,K,L 125° - 191° A,B,L 192° - 214° A,B 215° - 259° A,B,C 260° - 281° A,C 282° - 304° A,C,D 305° - 326° A,D , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear power Plant Units 1 and 2 13.3.2.10 Protective Response Standard A range of protective actions have been developed for the plume exposure pathway emergency planning zone for emergency workers and the public. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway emergency planning zone appropriate to the locale have been developed.

Evaluation The plan establishes the means and times to alert and notify onsite personnel of an emergency, and identifies the assembly areas adjacent to each of the gate houses. Personnel will be monitored for contamination at the assembly area.

If it is necessary to evacuate further, evacuation routes and means of transportation are identified. Holding areas for additional decontamination will be identified if necessary. Supervisors will account for all persons evacuated from within the protected area at the assembly area and report missing persons to appropriate supervision within 30 minutes. Security search procedures will be implemented to locate missing persons. The plan provides individual respiratory protection, protective clothing, and physician-supervised radio-protective drugs for the emergency workers. The applicant will provide the state and local governments with appropriate information necessary to make a decision concerning public protective measures. The applicant will also provide an independent recommendation for protective actions for the population at risk based on the Protective Action Guides provided in Table 4.5-l for plume exposure and Table 4.5-2 for ingestion EPZ. The information in these tables is consistent with EPA 520/l-75-001 and the FDA guidelines on contamination of human food and animal feed.

The plan provides for prompt notification of state and local authorities upon declaration of an emergency. Alerting, warning, and notifying the population at-risk will be accomplished by sirens and supplemented by radio and television announcements, sound trucks, bullhorns, and knocking on doors. Aircraft and patrol boats will alert people on Lake Jordan and the Shearon Harris main reservoir. Public warning will be accomplished per the NCERP when the state and local governments deem it appropriate.

The plan includes a map showing local emergency planning zones, population by zones, and evacuation routes,

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but does not show radiological sampling or monitoring points, or relocation and shelter areas.

PLP-201 Emergency Plan , Rev. 3 4.5 Protective Actions for the Public 4.5.1 Protective Action Guides

a. For incidents involving actual or imminent releases of radioactive material to the atmosphere, protective action recommendations will be based upon core and containment conditions as indicated Figure 4.5-1or based upon the protective action guidelines indicated in Table 4. 5-1.
b. For incidents involving contamination of food, water, or milk, protective action recommendations will be consistent with the guidance of the U. S. Food and Drug Administration (FDA) published in the Federal Register, Vol. 43, No. 242, December 15, 1978. The FDA guidance is summarized in Table 4.5-2.

4.5.2 CP&L Recommendations to Local Authorities The decision to implement protective actions for the off-site population at risk is the responsibility of the State and local governments. Detailed procedures for public protective actions are contained in the North Carolina Emergency Response Plan in Support of the SHNPP.

The decision to evacuate or remain (in shelter) will be based on an evaluation of many factors including the imminence and duration of the passing plume, the protection afforded by dwellings, public fallout shelters, and other structures that might provide protection from surface deposited radio nuclides and from a gamma cloud source in the 10-mile EPZ.

The local housing consists primarily. of wood framed dwellings, one and two stories, that are over ten years old*.

Very few houses have basements. There are a number of brick or brick veneer dwellings of later construction and several parks of house trailers. The representative protection factors for surface deposited radionuclides and for a gamma cloud source are, respectively, for wood frame houses with no basements (2.5 and 1.1) and for masonry houses with no basement (5 and 1.7).

Carolina Power and Light Company will provide the State and local governments with recommendations for protective actions for the public based on the guidance contained in Figure 4.5-1, in which recommendations are based upon the plant conditions, or on projected offsite doses in relation to the protective action guides contained in Table 4.5-l.

PLP-201 Emergency Plan, Rev 67 4.5.2 Protective Action Recommendations (PARs)

A. Protective action guidelines for the plume pathway EPZ are based on NUREG 0654 Supplement 3, "Criteria for Protective Action Recommendations for Severe Accidents."

B. Plant conditions, projected dose and dose rates, and/or field monitoring data are evaluated to develop PARs for the purpose of preventing or minimizing exposure to the general public. PARs are made to the State and County agencies that are responsible for implementing protective actions for the general public wherever PAGs are exceeded. PARs are approved by the Emergency Response Manager. In an emergency which requires immediate protective actions be taken prior to activation of the emergency facilities, notification approval is given by the SEC-CR directly to the State and County agencies.

C. Possible recommendations issued by HNP at a General Emergency include, but are not limited to:

1) Evacuation of the general public within the two (2) mile radius and five (5) miles downwind. All other areas within the EPZ are sheltered (minimum PAR issued).
2) Evacuation of the general public within the five (5) mile radius and ten (10) miles downwind. All other areas within the EPZ are sheltered.
3) Consideration of the use of KI (potassium iodide).

4.5.3 Ingestion Pathway Protective Measures HNP is required to issue PARs wherever PAGs are exceeded, but the State is responsible for specifying long term protective measures to be used throughout the ingestion pathway. These measures include the methods for protecting the public from exposure due to deposited radioactive materials and the consumption of contaminated water and foodstuffs.

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RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.
c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

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The adoption of the standard augmenting ERO will continue to maintain or improve the capability and timeliness of the HNP augmenting ERO to respond to an event and effectively perform their assigned tasks. HNP continues to maintain the capability to provide protective action recommendations to the offsite agencies and allow them to develop Protective Action Guidelines in a timely manner using the recommendation. Removing the "Shelter Subzones" from the process continues to maintain the functions while streamlining the process for the offsite agencies. The offsite agencies will still be able to recommend "sheltering" to the public, if they deem it necessary based on the severity of the accident. This will be accomplished though the Protective Action Guideline process.

The removal of the "shelter subzones" was agreed to by the state and counties during a task force meeting held 12/12/2017.

These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2
  • PLP-201, Emergency Plan, Revision 67 Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

10 CFR Part 50, Appendix E does not contain any supporting requirements.

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Evaluation HNP will continue to have adequate methods for assessing the actual or potential offsite consequences of a radiological emergency condition and protect the public as the accident progresses. The changes described maintains compliance with the applicable sections of 10CFR50.47(b).

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Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

Function A range of public PARs is available for implementation during emergencies.

Element NUREG 0654 II.J.7 Each licensee shall establish a mechanism for recommending protective actions to the appropriate State and local authorities. These shall include Emergency Action Levels corresponding to projected dose to the population-at-risk, in accordance with Appendix 1 and with the recommendations set forth in Tables 2.1 and 2.2 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-520/1-75-001). As specified in Appendix 1, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

The adoption of the standard augmenting ERO will continue to maintain or improve the capability and timeliness of the HNP augmenting ERO to respond to an event and effectively perform their assigned tasks. HNP continues to maintain the capability to provide protective action recommendations to the offsite agencies and allow them to develop Protective Action Guidelines in a timely manner using the recommendation. Removing the "Shelter Subzones" from the process continues to maintain the functions while streamlining the process for the offsite agencies. The offsite agencies will still be able to recommend "sheltering" to the public, if they deem it necessary based on the severity of the accident. This will be accomplished though the Protective Action Guideline process.

The removal of the "shelter subzones" was agreed to by the state and counties during a task force meeting held 12/12/2017.

The changes described do not affect the emergency planning functions listed in Part IV associated with 10 CFR 50.47(b) because the changes ensure adequate personnel, as well as emergency facilities and equipment to support the emergency response are provided and maintained to protect the emergency worker and the general public. The changes do not affect supporting requirements described in 10 CFR 50, Appendix E.IV. The changes continue to ensure that adequate provisions shall be made and described for emergency facilities and equipment and the changes continue to ensure the organization for coping with radiological emergencies is described.

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The changes described provide additional assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure the protection of the public
  • effectively use response equipment and emergency response procedures to evaluate conditions and protect the public.

These changes support the HNP Emergency Plan, by ensuring that procedures used during response to a classified emergency are available. Effective use of these procedures helps ensure emergency response functions as described in the Emergency Plan are adequately maintained and demonstrated. Some functions identified in this procedure were relocated to applicable fleet procedures to standardize ERO task and functions across the Duke Energy Fleet. This procedure will continue to be used by the HNP Main Control Room to analyze and provide protective Action Recommendations to the Site and the general pubic.

The changes described maintain the functions as described in the HNP Emergency Plan, as written and approved; and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4). If CFAM approval is NOT required, then mark the CFAM signature block as not applicable (N/A) to indicate that signature is not required.

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 01/03/18 Reviewer Name (Print): Reviewer Signature: Date:

Jamey Sharlow signed electronically in CAS 01/03/18 Approver (EP Manager) Name (Print): Approver Signature: Date:

Greg Simmons signed electronically in CAS 01/03/18 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.6, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:___2163280__________________ CNS CR3 HNP MNS 5AD #:______2163278_____________ ONS RNP GO Document and Revision PEP-310 rev 39 Notifications and Communications Part I. Description of Proposed Change:

Deleted attachment 13, INPO/ANI/Global Risk Management Notification Form and updated references to attachments throughout the body of the procedure. (responsibility moved to AD-EP-ALL-0103, Attachment 12 step 2.2.1.c) Renumbered attachments.

Step 4.3.2 changed from:

Any qualified ERO Communicator shall make an accelerated call to the NRC using Attachment 16.

to Any qualified ERO member shall make an accelerated call to the NRC using Attachment 15.

Step 4.6.1 NOTE changed from:

A qualified Emergency Communicator-NRC (EC-NRC) or SRO must be available to continuously communicate with the NRC via the Emergency Telecommunications System (ETS) or commercial telephone line within one hour of the initial event declaration.

to A qualified NRC Communicator or SRO must be available to continuously communicate with the NRC via the Emergency Telecommunications System (ETS) or commercial telephone line within one hour of the initial event declaration.

Step 4.9.1 (New step 4.8.1) changed from:

WHEN the EOF is activated, THEN the Admin and Logistics Manager (ALM) shall AUGMENT the existing MCR Staff with the following additional personnel, while continuing with this procedure:

to AUGMENT the existing MCR Staff with the following additional personnel, while continuing with this procedure:

Step 4.9.3 (New step 4.8.3) changed from:

TSC and EOF administrative personnel should post information as follows:

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to TSC and EOF personnel should post information as follows:

Step 4.9.4 (New step 4.8.4) changed from:

TSC-EP-NET Operator and EOF-EP-NET Operator will:

to TSC and EOF OAC Support will: Request for Offsite Support step 5 changed from Notify EP Duty Specialist of the following information to Notify EP Duty Manager (contact information located on the Site Duty Roster) of the following information 1 page 1 changed from:

Communicating the Emergency Notification Form (ENF) to the Off-Site Agencies NOTE:

For non-functioning Telecomm systems, refer to EPL-001, Emergency Phone List, for alternate means of contacting State and Counties.

NOTE:

Notify the Enterprise Help Desk (PICASSO) to report a telecomm problem.

NOTE:

State/County notifications are usually performed by the MCR-Emergency Communicator or EOF-State/County Emergency Communicator To access the WebEOC Emergency Notification Form (ENF)

1. If already logged in to WebEOC, go to the "Emergency Notification Messages" panel and Click "view" in the appropriate EN Form column.
a. The "Emergency Notification Fax Management" panel will open with the "Government Agencies Notified" auto-populated
b. Go to step 3
2. If not logged in to WebEOC, then Log on to computer using your ID and password
a. Access Duke Application Environment (DAE) on the desktop:
b. Select Shortcuts tab
c. Type WebEOC in search box, then Enter
d. Click WebEOC
e. Click Run Application
f. In the Position: field, using the pull-down menu, select your ERO position.
g. Click OK, the WebEOC Control Panel will open.
h. On the Control Panel under the Boards header, select EN Form the Emergency Notification Messages panel will open.
i. Click "view" in the appropriate EN Form column.

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to Communicating the Emergency Notification Form (ENF) to the Off-Site Agencies NOTE:

For non-functioning Telecomm systems, refer to EPL-001, Emergency Phone List, and CSD-EP-ALL-0104-01, Fleet Emergency Telephone Directory, for alternate means of contacting State and Counties.

NOTE:

Notify the Enterprise Help Desk (PICASSO) to report a telecomm problem.

NOTE:

State/County notifications are usually performed by the Emergency Communicator or Offsite Communicator.

To access the WebEOC Emergency Notification Form (ENF)

1. IF already logged in to WebEOC, THEN GO TO the "Emergency Notification Messages" panel and CLICK "view" in the appropriate EN Form column.
a. The "Emergency Notification Fax Management" panel will open with the "Government Agencies Notified" auto-populated.
b. GO TO step 3.
2. IF not logged in to WebEOC, THEN LOG ON to computer using your ID and password.
a. ACCESS Duke Application Environment (DAE) on the desktop.
b. SELECT Shortcuts tab.
c. TYPE WebEOC in search box and THEN PRESS Enter.
d. CLICK WebEOC .
e. CLICK Run Application.
f. In the Position: field, using the pull-down menu, SELECT your ERO position.
g. CLICK OK, the WebEOC Control Panel will open.
h. On the Control Panel under the Boards header, SELECT EN Form; the Emergency Notification Messages panel will open.
i. CLICK View in the appropriate EN Form column. 1 page 2 changed from:

Contacting State and Counties NOTE:

The State and County Authentication Code Words are located in the EC-MCRs position notebook, in the Key locker at the Auxiliary Control Panel (ACP) and in the Emergency Response Facility (EOF) Supply Cabinet. An automated version is also contained in WebEOC.

NOTE:

Notification to off site agencies shall be completed within 15 minutes of an emergency declaration or event termination. If this time will be challenged, it is permissible to contact the State and Counties on the phone and take roll call after an emergency has been declared, but prior to receiving the emergency message.

3. If requested by the State, provide the authentication code word.
4. Prior to making the notification call, review the ENF.
a. Go to Step 7 and annotate (1) the classification of emergency, (2) has been declared for initial notification (3) remains in effect for follow up notification.

(4) Protective Action Recommendations

b. Go to step 11 and annotate the message number.
5. Using DEMNET, use the "HNP Notify" button on the DEMNET display. This initiates a group call to the Warning

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Points and EOCs.

6. Wait for the initial response and say, This is the Harris Nuclear Plant, stand by for an emergency message.
7. After the responses cease, say, This is the Harris Nuclear Plant, An Unus ua l E ve nt ha s be e n de cla re d/ re m a ins in e ffe ct An Ale rt ha s be e n de cla re d/re m a ins in e ffe ct A S ite Are a Em e rge nc y ha s be e n declared/remains in effect A G e ne ra l Em e rge nc y ha s be e n de cla re d/re m a ins in e ffe ct; P rote ctive Action re com m e nda tions a re evacuate subzones and shelter subzones _______________

Em e rge nc y E ve nt ha s be e n te rm ina te d

8. Record the current time and date (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock). ___________________________ (This is ENF Notification time) to Contacting State and Counties NOTE:

The State and County Authentication Code Words are located in Emergency Communicator's position notebook, in the Key locker at the Auxiliary Control Panel (ACP) and in the Emergency Response Facility (EOF) Supply Cabinet.

An automated version is also contained in WebEOC.

NOTE:

Notification to off site agencies shall be completed within 15 minutes of an emergency declaration or event termination. If this time will be challenged, it is permissible to contact the State and Counties on the phone and take roll call after an emergency has been declared, but prior to receiving the emergency message.

3. Prior to making the notification call, REVIEW the ENF.
a. GO TO Step 9 and ANNOTATE the following:

(1) The classification of emergency (2) has been declared for initial notification (3) remains in effect for follow up notification.

(4) Protective Action Recommendations

b. GO TO Step 11 and ANNOTATE the message number.

NOTE:

Steps 4 through 10 are completed in quick succession.

4. Using DEMNET, USE the "HNP Notify" button on the DEMNET display.
5. WHEN the first agency answers/comes on the line, RECORD the current time and date (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock).
6. MARK which agencies you have on the phone as they join the line.

S ta te W a ke County Cha tha m County Ha rne tt C ounty Le e County

7. IF one or more organizations did not join the line, THEN CONTINUE with the notification process.
8. WHEN agencies join the line, PERFORM the following:
a. PRESS and HOLD the push to talk (PTT) button in the receiver.
b. SAY This is the Harris Nuclear Plant; stand by for an emergency message.
c. RELEASE PTT button when not speaking.

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9. Determine which agencies you have on the phone by taking roll call.

S ta te W a ke County Cha tha m County Ha rne tt C ounty Le e County

10. If one or more organizations did not respond to roll call, then continue with the notification process.
11. Determine which agencies have received the WebEOC Emergency Notification Form. Say, Emergency Notification Message Number was sent using WebEOC. Please confirm a legible copy has been received by answering to roll call.

S ta te W a ke County Cha tha m County Ha rne tt C ounty Le e County

a. IF anyone has not yet received their fax or WebEOC copy, THEN WAIT to allow the agency to retrieve the fax.
b. IF any agency responds that they are having difficulty reading the ENF or still has not received a fax, THEN REQUEST that agency to remain on the line at the end of the notification.

(1) Refer to Step 15 to read the ENF to the agency remaining on the phone.

c. If requested by the State, supply an authentication code word.

(1) RECORD Authentication number provided by State: ______________

(2) If using WebEOC for Authentication, then ENTER the Authentication number in the AUTHENTICATION field on the "Emergency Notification Fax Management" panel (a) CLICK on the "Get Authentication Code" button; the corresponding authentication code words will automatically appear (b) RESPOND to the State with the authentication code words (3) If using the State and County Authentication Code Words List, RESPOND to the State with the corresponding word from the list of authentication code words to

9. After the responses cease, SAY This is the Harris Nuclear Plant, An Unus ua l E ve nt ha s be e n de cla re d/ re m a ins in e ffe ct An Ale rt ha s be e n de cla re d/re m a ins in e ffe ct A S ite Are a Em e rge nc y ha s be e n de c la re d/re m a ins in e ffe ct A G e ne ra l Em e rge nc y ha s be e n de cla re d/re m a ins in e ffe ct; P rote ctive Action re com m e nda tions a re evacuate subzones and shelter subzones _______________

Em e rge nc y E ve nt ha s be e n te rm ina te d."

10. IF all agencies have joined the line, THEN RECORD the current time and date (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock).

_____________________________________________________ (This is the official ENF Notification time.)

11. DETERMINE which agencies have received the WebEOC Emergency Notification Form. SAY Emergency Notification Message Number was sent using WebEOC. Please confirm a legible copy has been received by answering to roll call and state your name.

S ta te

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W a ke County Cha tha m County Ha rne tt C ounty Le e County

a. IF anyone has not yet received their fax or WebEOC copy, THEN WAIT to allow the agency to retrieve the fax.
b. IF any agency responds that they are having difficulty reading the ENF or still has not received a fax, THEN REQUEST that agency to remain on the line at the end of the notification.
c. IF requested by the State, THEN SUPPLY an authentication code word.

(1) RECORD Authentication number provided by State: ______________

(2) If using WebEOC for Authentication, THEN ENTER the Authentication number in the AUTHENTICATION field on the "Emergency Notification Fax Management" panel (a) CLICK on the "Get Authentication Code" button; the corresponding authentication code words will automatically appear (b) RESPOND to the State with the authentication code words.

(3) IF using the State and County Authentication Code Words List, THEN RESPOND to the State with the corresponding word from the list of authentication code words. 1 page 4 changed from:

12. Say Are there any questions?
a. If necessary, correct any errors or clarify misunderstood information.
13. Perform the roll call as appropriate. Say "Respond to roll call with your name."

S ta te W a ke County Cha tha m County Ha rne tt C ounty Le e County

14. When completed, say, "This is the end of the emergency notification. You may leave the network. This is the Harris Nuclear Plant, out."
15. If any agency previously responded that they are having difficulty reading the ENF or still have not received a fax, then perform the following:
a. Read the entire form beginning at Line 1 to the responding locations as follows:

(1) Identify each line by number before communicating the content.

(2) Spell difficult words.

b. Say "Are there any questions?"

(1) If necessary, correct any errors or clarify misunderstood information.

c. Say "Copies of this notification will be sent by fax."
16. If a fax needs to be sent to any agency/location, then notify Communications Manager.
17. If one or more organizations did not respond to roll call, then contact missing agency(ies) using DEMNET or commercial phones.
a. Inquire if ENF fax was received.
b. If fax was not received, then resend fax or provide information manually.
18. Enter the Notification Time and date recorded in step 8 into the WebEOC Notification Time and Date field on the "Emergency Notification Fax Management" panel.

to

12. SAY Are there any questions?

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a. If identified, CORRECT any errors or CLARIFY misunderstood information.
13. WHEN completed, SAY "This is the end of the emergency notification. You may leave the network. This is the Harris Nuclear Plant, out."
14. IF one or more organizations did not respond to roll call, THEN PERFORM the following:
a. CONTACT missing agency(ies) using DEMNET or commercial phones.

Agency Phone Alternate Phone NC State Warning Point 800-858-0368 828-466-5501 Chatham County Warning Point 919-542-2911 919-545-8162 Harnett County Warning Point 910-893-9111 910-893-0630 Lee County Warning Point 919-775-5531 919-775-8268 Wake County Warning Point 919-856-6911 919-856-7033

b. RECORD current date and time. ______________________________ (This is the official ENF Notification time.)
15. IF any agency previously responded that they are having difficulty reading the ENF OR still have not received a fax, THEN PERFORM the following:
a. READ the entire form, beginning at Line 1, to the responding locations as follows:

(1) IDENTIFY each line by number before communicating the content.

(2) SPELL difficult words.

b. SAY "Are there any questions?"

(1) If identified, CORRECT any errors or CLARIFY misunderstood information.

c. SAY "Copies of this notification will be sent by fax."
d. WHEN completed, SAY "This is the end of the emergency notification. You may leave the network. This is the Harris Nuclear Plant, out."
e. FAX copies of ENF to agencies that did not receive initial fax. 1 page 5 changed from:
19. Enter the first and last names of the roll call into the WebEOC Government Agencies Notified "Received By" column on the "Emergency Notification Fax Management" panel.
a. Click on the Date/Time button to auto-populate the Date/Time field.
20. Click Save.
21. In Off-Site Communications module of WebEOC, add entry (initial or follow-up) of notification.
22. If performed from the EOF, then on the Communications Room board, add entry (initial or follow-up) of notification.

to

16. WHEN all agencies have responded AND have received the ENF, THEN PERFORM the following:
a. In WebEOC, CLICK EN Form.
b. SELECT Notification Management for the Current Message.
c. CLICK View.
d. SCROLL to the bottom of the screen to Government Agencies Notified.
e. TYPE in the first and last names recorded in Step 11 for each agency.

(1) CLICK on the Date/Time button to auto-populate the Date/Time field.

(2) CLICK Update.

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f. SCROLL to the top of the screen and CLICK Save. 2 - Instructions for State/County Notification Manual Method 2 page 1 changed from:

Communicating the Emergency Notification Form (ENF) to the Off-Site Agencies Contacting State and Counties NOTE:

For non-functioning Telecomm systems refer to EPL-001, Emergency Phone List, for alternate means of contacting State and Counties.

NOTE:

Notify the Enterprise Help Desk (PICASSO) to report a telecomm problem.

NOTE:

The State and County Authentication Code Words are located in the EC-MCRs position notebook, in the Key locker at the Auxiliary Control Panel (ACP) and in the Emergency Response Facility (EOF) Supply Cabinet. An automated version is also contained in WebEOC.

1. If requested by the State, provide the authentication code word.
2. Prior to making the notification call, review the ENF.
a. Go to Step 5 and annotate (1) the classification of emergency (2) has been declared for initial notification (3) remains in effect for follow up notification (4) Protective Action Recommendations
3. Using DEMNET, use the "HNP Notify" button on the DEMNET display. This initiates a group call to the Warning Points and EOCs.
4. Wait for the initial response and say: "This is the Harris Nuclear Plant, stand by for an emergency message.
5. After the responses cease, say, This is the Harris Nuclear Plant, An Unus ua l E ve nt ha s be e n de cla re d/ re m a ins in e ffe ct An Ale rt ha s be e n de cla re d/re m a ins in e ffe ct A S ite Are a Em e rge nc y ha s be e n de c la re d/re m a ins in e ffe ct A General Emergency has been declared/remains in effect; Protective Action recommendations are evacuate subzones and shelter subzones _______________

Em e rge nc y e ve nt ha s be e n te rm ina te d

6. Record the current time and date (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock) on line 2 of the ENF.

to Communicating the Emergency Notification Form (ENF) to the Off-Site Agencies Contacting State and Counties NOTE:

For non-functioning Telecomm systems refer to EPL-001, Emergency Phone List, and CSD-EP-ALL-0104-01, Fleet Emergency Telephone Directory, for alternate means of contacting State and Counties.

NOTE:

The State and County Authentication Code Words are located in the Emergency Communicator's position notebook, in the Key locker at the Auxiliary Control Panel (ACP) and in the Emergency Response Facility (EOF)

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Supply Cabinet. An automated version is also contained in WebEOC.

1. If requested by the State, THEN PROVIDE the authentication code word.
a. RECORD Authentication number provided by State: _________________.
b. IF using the State and County Authentication Code Words List, THEN RESPOND to the State with the corresponding word from the list of authentication code words.
2. Prior to making the notification call, REVIEW the ENF.
a. GO TO Step 8 and ANNOTATE the following:

(1) the classification of emergency (2) has been declared for initial notification (3) remains in effect for follow up notification (4) Protective Action Recommendations

b. GO TO Step 11 and ANNOTATE the message number.
c. GO TO Step 13 and ANNOTATE the Protective Action Recommendations.

NOTE:

Steps 3 through 9 are completed in quick succession.

3. Using DEMNET, USE the "HNP Notify" button on the DEMNET display.
4. WHEN the first agency answers/comes on the line, RECORD the current time and date (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock).
5. MARK which agencies you have on the phone as they join the line.

S ta te W a ke County Cha tha m County Ha rne tt C ounty Le e County

6. IF one or more organizations did not join the line, THEN CONTINUE with the notification process. 2 page 2 changed from:
7. Determine which agencies you have on the phone by taking roll call.

S ta te W a ke County Cha tha m County Ha rne tt C ounty Le e County

8. If one or more organizations did not respond to roll call, then continue with the notification process.
9. Say, "This is the Harris Nuclear Plant, Please record the following information on an Emergency Notification Form." (Pause to allow the locations to retrieve a form).
10. Say Line 1, Emergency Notification message number ____________________
11. Say, Line 4, (classification)

An Unus ua l E ve nt ha s be e n de cla re d/ re m a ins in e ffe ct An Ale rt ha s be e n de cla re d/re m a ins in e ffe ct A S ite Are a Em e rge nc y ha s be e n de c la re d/re m a ins in e ffe ct A G e ne ra l Em e rge nc y ha s be e n de cla re d/re m a ins in e ffe ct

12. Say Line 5, Protective Action recommendations are evacuate subzones and shelter the subzone which this recommendation applies

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13. Read the entire form beginning at line 1 to the responding locations as follows:
a. Identify each line by number before communicating the content.
b. Spell difficult words.
c. Complete reading the remainder of the form (from line 3).
d. Print and enter your name on line 17 of the form for "Notified By:"

to

7. WHEN agencies join the line, THEN PERFORM the following:
a. PRESS and HOLD the push to talk (PTT) button in the receiver.
b. SAY This is the Harris Nuclear Plant; stand by for an emergency message.
c. RELEASE PTT button when not speaking.
8. After the responses cease, SAY This is the Harris Nuclear Plant, An Unus ua l E ve nt ha s be e n de cla re d/ re m a ins in e ffe ct An Ale rt ha s be e n de cla re d/re m a ins in e ffe ct A S ite Are a Em e rge nc y ha s be e n de c la re d/re m a ins in e ffe ct A G e ne ra l Em e rge nc y ha s be e n declared/remains in effect; Protective Action recommendations are evacuate subzones _____________ and shelter subzones _______________

Em e rge nc y E ve nt ha s be e n te rm ina te d."

9. IF all agencies have joined the line, THEN RECORD the current time and date (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> clock).

_____________________________________________________ (This is the official ENF Notification time.)

10. SAY "This is the Harris Nuclear Plant, Please record the following information on an Emergency Notification Form." (PAUSE to allow the locations to retrieve a form.)
11. SAY Emergency Notification Message Number ____________________________
12. SAY "Line 3, (Emergency Classification)."

An Unus ua l E ve nt ha s be e n de cla re d/ re m a ins in e ffe ct An Ale rt ha s be e n de cla re d/re m a ins in e ffe ct A S ite Are a Em e rge nc y ha s be e n de c la re d/re m a ins in e ffe ct A G e ne ra l Em e rge nc y ha s be e n de cla re d/re m a ins in e ffe ct

13. SAY "Line 6, Protective Action recommendations are evacuate subzones _____________ and shelter subzones _______________."
14. READ the entire form beginning at line 1 to the responding locations as follows:
a. IDENTIFY each line by number before communicating the content.
b. SPELL difficult words.
c. COMPLETE reading the remainder of the form (from line 3).
d. PRINT and ENTER your name on line 17 of the form for "Notified By:" 2 page 3 changed from:
14. Say, Are there any questions?
a. If necessary, correct any errors or clarify misunderstood information.
15. Say, Copies of this notification will be sent to you via Fax.
16. Say, "Respond to roll call with your name.
a. Call roll and record the information below. Identify the applicable location for each agency.

S ta te W a ke County Cha tha m County Ha rne tt County

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Le e County

17. End the call by saying, This is the end of the emergency notification. You may leave the network. Harris Nuclear Plant out.
18. If performed from the MCR, fax the Emergency Notification Form to the WPs, EOCs, TSC and EOF using the button labeled DEL.
19. If performed from the TSC or EOF, fax a copy of the ENF to the applicable WPs and/or EOCs utilizing the applicable rapid dial buttons.
20. If one or more organizations did not respond to roll call, then contact missing agency(ies) using DEMNET or commercial phones.
a. Inquire if ENF fax was received.
b. If fax was not received, then resend fax or provide information manually.
21. In Off-Site Communications module of WebEOC, add entry (initial or follow-up) of notification.
22. If performed from the EOF, then on the Communications Room board, add entry (initial or follow-up) of notification.

to

15. SAY Are there any questions?
a. IF identified, CORRECT any errors or CLARIFY misunderstood information.
16. SAY "Copies of this notification will be sent by fax."
17. SAY "Respond to roll call with your name.
a. CALL roll and RECORD the information below.

S ta te W a ke County Cha tha m County Ha rne tt C ounty Le e County

18. END the call by saying This is the end of the emergency notification. You may leave the network. Harris Nuclear Plant out.
19. IF performed from the MCR, THEN FAX the Emergency Notification Form to the WPs, EOCs, TSC, and EOF using the button labeled DEL.
20. IF performed from the TSC or EOF, THEN FAX a copy of the ENF to the applicable WPs or EOCs utilizing the applicable rapid dial buttons.
21. IF one or more organizations did not respond to roll call, THEN PERFORM the following:
a. CONTACT missing agency(ies) using DEMNET or commercial phones.

Agency Phone Alternate Phone NC State Warning Point 800-858-0368 828-466-5501 Chatham County Warning Point 919-542-2911 919-545-8162 Harnett County Warning Point 910-893-9111 910-893-0630 Lee County Warning Point 919-775-5531 919-775-8268 Wake County Warning Point 919-856-6911 919-856-7033

b. RECORD current date and time. ______________________________ (This is the official ENF Notification time.)
22. In Off-Site Communications module of WebEOC, ADD entry (initial or follow-up) of notification.
23. IF performed from the EOF, THEN ADD entry (initial or follow-up) of notification on the Communications Room board.

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<< 10 CFR 50.54(q) Effectiveness Evaluation Form >> , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

(Planning Standard 2)

NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.2 Onsite Emergency Organization Standard On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of responsive capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.

Evaluation Station staff personnel have been assigned emergency positions with responsibilities and duties commensurate with their normal activities.

PLP-201 Emergency Plan, Rev. 3 2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 General The plant emergency organization is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest number of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities.

Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time PLP-201 Emergency Plan, Rev 67 2.0 ORGANIZATION AND RESPONSIBILITIES 2.2 Emergency Organization (Excerpts only)

The plant Emergency Response Organization (ERO) is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest numbers of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities.

Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time

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(Planning Standard 5)

NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear power Plant Units 1 and 2 13.3.2.5 Notification Methods and Procedures Standard Procedures have been established for notification by the licensee of state and local response organizations and for notification of emergency personnel by all response organizations; the content of initial and followup messages to response organizations and the public have been established and means to provide early notification and clear instructions to the populace within the plume exposure pathway emergency planning zone have been established.

Evaluation Immediately upon declaring an emergency, the SEC activates the emergency plan and initiates the procedures for notification of onsite emergency organization. The SEC also fills out the "Immediate Notification Form," contained in Annex F of the plan, and provides it to the Emergency Communicator. Using the Automatic Ring Down (ARD) phone, within 15 minutes, the Emergency Communicator will read the message simultaneously to all counties within the EPZ and the state warning point for all emergency classifications, except for the Unusual Event class for which the time is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

PLP-201 Emergency Plan , Rev. 3 4.2 Notification

b. The Emergency communicator will use the Automatic Ring Down (ARD) phone to simultaneously notify the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, manned, State and County warning points with the notification message. This message will be read to all counties and the state within 15 minutes for all emergency classifications.

PLP-201 Emergency Plan, Rev 67 4.2 Notification A. The Emergency Communicator will use the electronic Emergency Notification Form (ENF) on WebEOC, hard copy ENF contained in PEP-310, or the Selective Signaling System phone to simultaneously notify the 24-hour-per-day, staffed, State Warning Point, State EOC and County Warning Points with the notification message. Emergency Operations Centers will be notified upon activation at the State and Counties in lieu of the Warning Points. This message will be initiated to all Counties and the State within 15 minutes for all emergency classifications.

RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents,

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such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.

c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this procedure revision were made to reflect the changes for the EOF relocation to Charlotte and the changes made for Standard ERO. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2

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Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR50.47(b)(2), Onsite Emergency Organization On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

10 CFR 50, Appendix E, Section IV. A. Organization (applicable excerpts only)

The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

2. A description of the onsite emergency response organization (ERO) with a detailed discussion of:
a. Authorities, responsibilities, and duties of the individual(s) who will take charge during an emergency;
b. Plant staff emergency assignments;
c. Authorities, responsibilities, and duties of an onsite emergency coordinator who shall be in charge of the exchange of information with offsite authorities responsible for coordinating and implementing offsite emergency measures.
3. A description, by position and function to be performed, of the licensee's headquarters personnel who will be sent to the plant site to augment the onsite emergency organization.
7. By June 23, 2014, identification of, and a description of the assistance expected from, appropriate State, local, and Federal agencies with responsibilities for coping with emergencies, including hostile action at the site. For purposes of this appendix, "hostile action" is defined as an act directed toward a nuclear power plant or its personnel that includes the use of violent force to destroy equipment, take hostages, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force.

10 CFR 50.47(b)(5)Emergency Notifications Procedures have been established for notification, by the licensee, of State and local response organizations and for notification of emergency personnel by all organizations; the content of initial and follow-up messages to response organizations and the public has been established; and means to provide early notification and clear instruction to the populace within the plume exposure pathway Emergency Planning Zone have been established.

10CFR50 Appendix E IV. Content of Emergency Plans D. Notification Procedures

3. A licensee shall have the capability to notify responsible State and local governmental agencies within 15 minutes after declaring an emergency. The licensee shall demonstrate that the appropriate governmental authorities have the capability to make a public alerting and notification decision promptly on being informed by the licensee of an emergency condition.

The changes identified in this revision continue to comply with 10 CFR 50.47(b)(2)-Onsite Emergency Organization and 10 CFR 50.47(b)(5)Emergency Notifications and 10CFR50 Appendix E.IV - Content of Emergency Plans. HNP retains the capability required by regulation to notify the responsible State and local government agencies within 15 minutes of declaring an emergency.

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Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR50.47(b) (2), Onsite Emergency Organization The regulation at 10 CFR 50.47(b)(2) states the following:

On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

Function The process for timely augmentation of on-shift staff is established and maintained.

10 CFR 50, Appendix E, Section IV. A. Organization (applicable excerpts only)

The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

2. A description of the onsite emergency response organization (ERO) with a detailed discussion of:
a. Authorities, responsibilities, and duties of the individual(s) who will take charge during an emergency;
b. Plant staff emergency assignments;
c. Authorities, responsibilities, and duties of an onsite emergency coordinator who shall be in charge of the exchange of information with offsite authorities responsible for coordinating and implementing offsite emergency measures.
3. A description, by position and function to be performed, of the licensee's headquarters personnel who will be sent to the plant site to augment the onsite emergency organization.
7. By June 23, 2014, identification of, and a description of the assistance expected from, appropriate State, local, and Federal agencies with responsibilities for coping with emergencies, including hostile action at the site. For purposes of this appendix, "hostile action" is defined as an act directed toward a nuclear power plant or its personnel that includes the use of violent force to destroy equipment, take hostages, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force.

Element NUREG-0654/FEMA-REP-1 Rev 1, II, B. Onsite Emergency Organization (applicable excerpts only)

5. Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site.
6. Each licensee shall specify the interfaces between and among the onsite functional areas of emergency activity, licensee headquarters support, local services support, and State and local government response organization.

Standard 10 CFR 50.47(b)(5), Emergency Notifications The regulation at 10 CFR 50.47(b)(5) states the following:

Procedures have been established for notification, by the licensee, of State and local response organizations and for notification of emergency personnel by all organizations; the content of initial and follow-up messages to response organizations and the public has been established; and means to provide early notification and clear instruction to the populace within the plume exposure pathway Emergency Planning Zone have been established.

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Function The emergency planning functions defined for this planning standard:

(1) Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up notifications.

10CFR50 Appendix E IV. Content of Emergency Plans D. Notification Procedures

3. A licensee shall have the capability to notify responsible State and local governmental agencies within 15 minutes after declaring an emergency. The licensee shall demonstrate that the appropriate governmental authorities have the capability to make a public alerting and notification decision promptly on being informed by the licensee of an emergency condition.

Elements NUREG-0654/FEMA-REP-1 Rev 1, II, E. Notification Methods and Procedures Criteria (applicable excerpts only )

Each organization shall establish procedures which describe mutually agreeable bases for notification of response organizations consistent with the emergency classification and action level scheme set forth in Appendix 1. These procedures shall include means for verification of messages. The specific details of verification need not be included in the plan.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

The changes in this revision meet the NRC approved LAR RA-16-0002 for a Duke Common EOF and changes made for the standard ERO structure - position changes, position title changes, and moving functions from one position to another position in that standard ERO structure.

The changes identified in this revision continue to comply with NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear power Plant Units 1 and 2 Section 13.3.2.5 Notification Methods and Procedures, PLP-201 Emergency Plan , Rev. 3 section 4.2 Notification, and PLP-201 Emergency Plan, Rev 67 section 4.2 Notification.

HNP retains the function required by regulation to notify the responsible State and local government agencies within 15 minutes of declaring an emergency. HNP also retains the ability to augment the on shift staff as directed by this procedure. These changes do not reduce the effectiveness of the emergency plan or reduce the function of the Emergency Plan notify the ERO and the Offsite Agencies of an emergency at HNP.

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Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 11/28/17 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 11/29/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Jamey Sharlow signed electronically in CAS 11/29/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:____2166201________ CNS CR3 HNP X MNS 5AD #:______2166200______ ONS RNP GO Document and Revision ERO Training Program EPM-200 REV 022 Part I. Description of Proposed Change:

EPM-200 ERO Training Program is being revised to reflect changes required for the transition to the common EOF and the Standard ERO.

In conjunction with the common EOF, an initiative was undertaken by Duke Energy to standardize the augmenting ERO positions, functions and responsibilities (tasks) across the fleet. This involves changes to the current Harris Nuclear Plant (HNP) augmenting ERO, based on the number of responder and their titles identified in the site emergency plan and implementing procedures. Included in the standard ERO initiative is the development of fleet standard ERO checklists, procedures and forms.

This initiative makes no changes to the on-shift ERO.

The table of contents was revised to reflect the changes made throughout the procedure.

Re-numbered steps throughout based on revision.

Throughout the procedure, titles were changed to reflect the new nomenclature.

Revised section 4.7 to removed a staff member's ERO requirements as part of their Performance Development Plan.

Revised section 4.9 to reflect maintaining five ERO teams versus four. Removed note referencing attachment 4, which is being deleted.

Revised section 5.3.1.b.removing the Plant Operations Director (POD). This position was changed to the Control Room Ops Bridge in the Standard ERO. The Ops Bridge responsibilities are now contained in AD-EP-ALL-0105 and in AD-EP-ALL-0500.

Removed section 5.3.2 for the Technical Support Center (TSC) personnel. The roles and responsibilities for the TSC are now contained in AD-EP-ALL-0105 and in AD-EP-ALL-0500.

Removed section 5.3.3 for the Operational Support Center (OSC) personnel. The roles and responsibilities for the OSC are now contained in AD-EP-ALL-0106 and in AD-EP-ALL-0500.

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Removed section 5.3.4 for the Emergency Operations Facility (EOF) personnel. The roles and responsibilities for the EOF are now contained in AD-EP-ALL-0103 and in AD-EP-ALL-0500.

Removed section 5.3.5 for the Joint Information Center (JIC) personnel. The roles and responsibilities for the JIC are now contained in AD-EP-ALL-0108 and in AD-EP-ALL-0500.

Revised section 5.4 removing Sections 5.4.1 to Section 5.4.2. AD-EP-ALL-0500 provides the new framework.

Removed attachments 1 to 4. Information in these Attachments is superseded by AD-EP-ALL-0500. , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No X Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

NUREG-1038 Safety Evaluation Report Related to the Operation of Shearon Harris Nuclear power Plant, Units 1 and 2, section 13.3.2.15 Radiological Emergency Response training.

Standard Radiological emergency response training is provided to those who may be called upon to assist in an emergency.

Evaluation The Emergency Plan Training Program, as described in Corporate Emergency Plan Implementation Procedures, CEPEP-19, ensures that the individuals who may be called on to assist in an emergency will be trained. Initial training and annual retraining are provided. Provisions have been made to train offsite response organizations, such as hospital ambulances and police and fire personnel, who may be called upon to provide assistance.

Training will include site-access procedures and the identity by position/title of the person in the Shearon Harris organization who will control the support activity.

The plan provides for specialized training for individuals assigned specific responsibilities in the emergency plan, such as Red Cross multi-media training for first aid team members.

The followings items require resolution:

(1) The plan should incorporate the information from CEPIP-19 in sufficient detail to allow evaluation of the plan.

(2) The Damage Control Teams, described in Section 2.4.4 of the Shearon Harris plan as part of the emergency organization, are not listed as receiving any training in the plan or in CEPIP-19. The specific training and retraining needs for this group should be detailed in the plan.

From NUREG 1038 Supplement 1:

The applicant's response to these issues is as follows:

(1) The applicant has provided details of the training to be provided to specific categories of emergency response personnel in the revised plan. The plan specifies that initial training and annual retraining will be provided. It also provides assistance with the training of offsite emergency response personnel according to the radiological emergency plan. and supplemental training as related to Shearon Harris. The Emergency Plan Training Program is-described in detail Procedure PEP-403 and in the Plant Emergency Plan Training Program Lesson Plans.

(2) The applicant has specifically addressed the training of Damage Control Team personnel in Section 5.2.3.7 of the revised plan

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On the basis of its evaluation of the applicant's response, the staff finds the applicants training program acceptable.

PLP-201, Emergency Plan, Rev 3 5.2. Emergency Plan Training Program 5.2.1 General Requirements The Emergency Plan Training Program, described in detail in the Emergency Plan Implementation Procedure PEP-403, assures training of individuals who may be called on to assist in an emergency. Initial training and annual retraining is provided. Responsibilities for implementing the training program are also contained in PEP-403.

5.2.2 Training Objectives The primary objectives of the training program are to:

a) Familiarize appropriate individuals with the Plan and the procedures that implement the Plan b) Instruct individuals and their alternates in their duties and responsibilities c) Periodically present significant changes in the scope or contents of the Plan or procedures which implement the Plan d) Provide annual refresher training to ensure that personnel are familiar with their duties and responsibilities assigned by the Plan and procedures which implement the Plan 5.2.3 Training Course Descriptions The Emergency Plan Training Program makes provisions for training the categories of personnel listed in the following paragraphs in order to perform the specific tasks within their assigned responsibilities in the Emergency Plan 5.2.3.1 General Employee Training Each individual authorized unescorted access to the Protected Area is provided with information concerning evacuation alarms and procedures used at the SHNPP in the event of an emergency and also receives initial orientation on the basic principles of radiological safety.

5.2.3.2 Site Emergency Coordinator Those personnel who may be assigned to perform the functions of the Site Emergency Coordinator will receive training in the following areas:

  • Emergency organization and responsibilities
  • Emergency facility location, layout, organization, and functions
  • Emergency communications systems and data displays

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  • Emergency classifications and emergency action levels
  • Protective actions for on-site personnel and the public
  • Interfaces with other emergency facilities and organizations
  • Personnel emergency exposure limits
  • Procedures for notification of plant personnel and outside agencies
  • Procedures for relief of position and turnover of off-site responsibilities to the Emergency Response Manager
  • Record keeping requirements 5.2.3.3 Senior Control Operators and Shift Technical Advisors The Senior Control Operators and Shift Technical Advisors receive training in the following areas:
  • Emergency operating procedures
  • Emergency facility location, layout, organization, and functions
  • Control Room communications systems and data displays
  • Emergency classifications and emergency action levels
  • Dose projection procedures and protective action recommendations for the public
  • Control Room interfaces with the TSC, EOF and other facilities/organizations
  • Emergency procedures during use of Auxiliary Control Panel
  • Emergency notification procedures
  • On-site alerting, warning, and evacuation procedures
  • Record keeping requirements 5.2.3.4 TSC Staff Personnel The Plant Operations Director, the Emergency Repair Director, the Logistics Support Director, the Radiological Control Director, and other staff and team leaders in the TSC receive training in the following areas:
  • Emergency facility location, layout, organization, and functions
  • TSC communications systems and data displays
  • Emergency classifications and emergency action levels
  • Protective actions for on-site personnel
  • TSC interfaces with other facilities and organizations
  • Record keeping requirements
  • Offsite protective action recommendations

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5.2.3.5 Emergency Communicator The Emergency Communicator training includes:

  • Use of emergency communications systems and equipment
  • Emergency notification procedures
  • Emergency organization
  • Emergency team rosters and call-in procedures
  • Outside agencies and notification procedures
  • Record keeping requirements 5.2.3.6 Radiological Emergency Teams The Dose Projection Teams, Environmental Monitoring Teams, Personnel Protection and Decontamination Teams and Plant Monitoring Teams receive instruction in the following areas in addition to the specific training required to perform their assigned function:
  • The functions performed by each radiological emergency team
  • The range of radiological condit1ons that may be encountered
  • Emergency classifications and emergency exposure limits
  • Emergency facility location, layout, and functions
  • Description, storage location, and application of emergency supplies
  • and equipment
  • Geographic familiarity of site. environs, and roads for use by
  • off-site teams
  • Communications systems and their use
  • Specific procedures relating to the team function
  • Record keeping requirements 5.2.3.7 Damage Control Team Personnel Damage Control Team Personnel receive training in the following areas in addition to general employee emergency plan training:
  • Emergency classifications and emergency exposure limits
  • Emergency facilities and their locations and functions
  • Site communications systems and their use
  • Description, storage location, and application of emergency supplies and equipment 5.2.3.8 Emergency Security Team The Emergency Security Team training includes:
  • Personnel accountability procedures
  • Site access and egress control procedures
  • Deployment of security personnel
  • Evacuation and perimeter control
  • On-site traffic control

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  • Applicable communication links and methods Training topics are selected in accordance with job assignments per the SHNPP Security Personnel Training &

Qualification Plan and Implementing Procedures supporting the SHNPP Security Plan.

5.2.3.9 Fire Brigade Fire Brigade training is in accordance with commitments contained in Section 9.5.1 of the FSAR. This training includes:

  • Use of fire suppression equipment
  • Personnel protection equipment
  • Fire fighting in radiation areas
  • Emergency worker exposure guides
  • Emergency facilities, their locations and functions
  • Site communications systems and their use
  • Access and egress control for offsite fire departments Offsite fire agreements 5.2.3.10 First Aid Team Personnel First Aid Team Personnel will receive training in the following areas in addition to general employee emergency plan training:
  • Red Cross Multi-media First Aid
  • Emergency classifications
  • Emergency facilities and their locations and functions
  • Site communications systems and their use
  • Description, storage location, and use of First Aid supplies and *
  • equipment
  • Procedures for First Aid and rescue
  • Procedures for transporting injured (contaminated or not) off-site 5.2.3.11 Accident Assessment Team Personnel Personnel on the Accident Assessment Team will receive training in the following areas:
  • Emergency action levels and emergency classifications
  • TSC Staff Personnel training items
  • Plant systems training courses 5.2.3.12 EOF Personnel The Emergency Response Manager, Technical Analysis Manager, Administrative and Logistics Manager, and Radiological Control Manager, and their staffs receive training in the following areas.
  • Emergency facility location, layout, organization, and functions

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  • EOF communications systems and data displays
  • Emergency Classifications
  • Protective actions for the public
  • EOF interfaces with other facilities and organizations
  • Record keeping requirements 5.2.3.13 CP&L Media Personnel Personnel who may fill positions in the Plant Media Center receive training in the following areas:
  • Emergency classification
  • Notification procedures
  • Emergency facilities, functions, and interfaces
  • Media center job functions
  • Basics of nuclear power plants 5.2.3.14 Corporate Emergency Operating Center Personnel Corporate Emergency Operating Center personnel will receive training in the following areas:
  • Emergency facility location and functions
  • Emergency classifications
  • Communications systems 5.2.3.15 Off-Site Organization Training of off-site organizations is described in their respective radiological emergency plans. Additional training provided by CP&L for hospital, ambulance, rescue, police, and fire personnel is described in Plan Emergency Plan Training Program Lesson Plans and PEP-403. Such training will include the procedures for notification, basic radiation protection, and their expected roles. For those local services support organizations who may enter the site, training by CP&L will also include site access procedures and the identity {by position and title) of the individual in the SHNPP organization who will control the organization's support activities. Carolina Power & Light Company will assist these off-site organization's in performing their radiological emergency response training as related to SHNPP as requested.

Training of medical support personnel at the agreement hospitals will include basic training on the nature of radiological emergencies, diagnosis and treatment, and follow-up medical care.

PLP-201, Emergency Plan, Rev 67 5.2 Emergency Response Organization Training Program 5.2.1 General Requirements HNP ensures the training of appropriate company personnel to support the Harris Plant Emergency Plan. Initial training and annual retraining is provided for the following categories of personnel:

A. Directors, Coordinators, and Managers in the Emergency Response Organization.

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B. Personnel responsible for accident assessment.

C. Radiological monitoring teams and radiological analysis personnel D. Damage Control Teams E. First Aid Team (MERT), Search and Rescue, and Fire Brigade Teams F. Personnel responsible for transmission of emergency information and instruction G. Personnel responsible for communicating with the media and public H. Offsite medical support personnel I. Local support services personnel, including emergency management personnel J. Police, security and offsite fire-fighting personnel who may be required to assist at the plant Company personnel not assigned to the site are utilized and trained as members of the program.

Individuals assigned to First Aid Teams (MERT) will include courses equivalent to the Red Cross Multimedia First Aid Course.

Designated ERO positions are also required to be qualified in the use of appropriate respiratory equipment.

Plant Access Training is provided to all personnel before they have unrestricted access to the Protected Area. This training includes general knowledge of alarms and actions required for non-ERO member during a declared emergency.

Site specific emergency response training shall be offered to offsite emergency organizations and local support services individuals who may be called upon to provide assistance to HNP in the event of an emergency. Training will include site access procedures and the identity (by position and title) of the individual in the HNP ERO who will control their organizations' support activities. Training for hospital personnel, ambulance/rescue, police and fire departments shall also include the procedures for notification, basic radiation protection, and their expected roles.

5.2.2 Conduct of Training The Manager - Emergency Preparedness is responsible for the overall content and administration of the emergency plan training program.

EPM-200, ERO Training Program, will include knowledge based and/or performance based training and evaluation components.

A. Knowledge based training may be provided in a classroom setting or self directed study modules and document reviews. Examination and/or interviews will be given for initial qualifications to ensure trainee has a good base knowledge of the ERO and their assigned responsibilities.

B. Performance based training and evaluations will be conducted for most ERO members (exceptions are made for pool personnel whose normal job functions closely matches their emergency functions and they are directed by qualified ERO Managers or Coordinators, such as operations, E&RC, maintenance, administrative and security pool personnel). This is done during conduct of exercises, drills or walkthroughs and documented on ERO qualification record forms.

Review The differences in PLP-201, Revision 3, and PLP-201, Revision 67 have been determined to meet the regulatory requirements of the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

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RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.
c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes being made to EPM-200 support the transition to a fleet common ERO and the common Emergency Operations Facility (EOF) in Charlotte, NC. New fleet procedures incorporate procedure content that is being removed from this procedure.

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These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the applicable planning standards as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2
  • PLP-201, Emergency Plan, Revision 67 Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(15)

a. The regulation at 10 CFR 50.47(b)(15) states the following:

Radiological emergency response training is provided to those who may be called on to assist in an emergency.

10 CFR Part 50 Appendix E Section IV.F.1 F. Training

1. The program to provide for: (a) The training of employees and exercising, by periodic drills, of emergency plans to ensure that employees of the licensee are familiar with their specific emergency response duties, and (b) The participation in the training and drills by other persons whose assistance may be needed in the event of a radiological emergency shall be described. This shall include a description of specialized initial training and periodic retraining programs to be provided to each of the following categories of emergency personnel:
i. Directors and/or coordinators of the plant emergency organization; ii. Personnel responsible for accident assessment, including control room shift personnel; iii Radiological monitoring teams; iv. Fire control teams (fire brigades);
v. Repair and damage control teams; vi. First aid and rescue teams; vii. Medical support personnel;

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viii. Licensee's headquarters support personnel; ix. Security personnel.

The adoption of a fleet standard procedure for emergency response organization training at HNP ensures that radiological emergency response training is provided to those who may be called on to assist in an emergency, including periodic drill participation, to meet the requirements of 10CFR50.47(b)(15) and 10CFR50 Appendix E, Section IV.F.

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Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR 50.47(b) (15)

Radiological emergency response training is provided to those who may be called on to assist in an emergency.

Function Regulatory Guide 1.219 describes the following planning function for this standard:

Training is provided to emergency responders.

Elements NUREG-0654 describes the following elements for this standard:

1. Each organization shall assure the training of appropriate individuals.
2. The training program for members of the onsite emergency organization shall, besides classroom training, include practical drills in which each individual demonstrates ability to perform his assigned emergency function.

During the practical drills, on-the-spot correction of erroneous performance shall be made and a demonstration of the proper performance offered by the instructor.

4. Each organization shall establish a training program for instructing and qualifying personnel who will implement radiological emergency response plans. The specialized initial training and periodic retraining programs (including the scope, nature and frequency) shall be provided in the following categories:
a. Directors or coordinators of the response organizations;
b. Personnel responsible for accident assessment;
c. Radiological monitoring teams and radiological analysis personnel;
d. Radiological monitoring teams and radiological analysis personnel;
e. Repair and damage control/correctional action teams (onsite);
f. First aid and rescue personnel;
g. Local support services personnel including Civil Defense/Emergency Service personnel;
h. Medical support personnel;
i. Licensee's headquarters support personnel
j. Personnel responsible for transmission of emergency information and instructions.
5. Each organization shall provide for the initial and annual retraining of personnel with emergency response responsibilities.

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Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Revised section 4.7 to removed a staff member's ERO requirements as part of their Performance Development Plan. Step 4.7.4.b was removed. The Performance Development Plan program is no longer governed at the site level. Performance objectives are generated at the Fleet level and are identical to all individuals within the company. This is a removal of an administrative step and does not affect the effectiveness of the emergency plan.

Revised section 4.9 to reflect maintaining five ERO teams versus four.

  • The number of individual ERO teams was increased to five to reflect the Fleet Standard ERO standard.

Revised section 5.3.1.b.removing the Plant Operations Director (POD) position.

  • This position was changed to the Control Room Operations Bridge in the Standard ERO as described in AD-EP-ALL-0500. Attachment 4.

Removed section 5.3.2 for the Technical Support Center (TSC) personnel.

  • The roles and responsibilities for the TSC are listed in AD-EP-ALL-0105 and in AD-EP-ALL-0500, Attachment 4.

Removed section 5.3.3 for the Operational Support Center (OSC) personnel.

  • The roles and responsibilities for the OSC are listed in AD-EP-ALL-0106 and in AD-EP-ALL-0500, Attachment 4.

Removed section 5.3.4 for the Emergency Operations Facility (EOF) personnel.

  • The roles and responsibilities for the EOF are listed in AD-EP-ALL-0103 and in AD-EP-ALL-0500. HNP will no longer be employing a near site Emergency Operations Facility. The Common EOF will be staffed to support HNP in the event of an emergency.

Removed section 5.3.5 for the Joint Information Center (JIC) personnel.

  • The roles and responsibilities for the JIC are listed in AD-EP-ALL-0108 and in AD-EP-ALL-0500.

Revised section 5.4 removing Sections 5.4.1 to Section 5.5.2.

  • This section listed the individual training modules needed for ERO training. AD-EP-ALL-0500 provides the new framework. The new Fleet procedure gives description on the individual training classes needed for each position in Attachment 4.

Removed attachments 1 to 4. Information is superseded by AD-EP-ALL-0500 or other Fleet level procedures.

  • Attachment 1 reflects a table of the HNP ERO qualification requirements. This is superseded by Fleet Procedure AD-EP-ALL-0500, Attachment 4.
  • Attachment 2 is used for student feedback. A standard student feedback form is in AD-TQ-ALL-0400 as Attachment 5.

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  • Attachment 3 gives information on identifying new ERO members and checklist to complete. This is now governed by AD-EP-ALL-0500 and the individual Position Specific Guides.
  • Attachment 4 lists the current HNP ERO positions. These are superseded by the new ERO positions as listed in AD-EP-ALL-0500, Attachment 4.

These changes are being made to ensure compliance with the implementation of Fleet Standard ERO and Common EOF. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the requirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E.

Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes X No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes X No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes X No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current X

Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

David Stih signed electronically in CAS 1/2/18 Reviewer Name (Print): Reviewer Signature: Date:

Jamey Sharlow signed electronically in CAS 1/2/18 Approver (EP Manager) Name (Print): Approver Signature: Date:

Greg Simmons signed electronically in CAS 1/3/18 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

X to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect. X QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:___2166189_______ CNS CR3 HNP MNS 5AD #:_____2166186_______ ONS RNP GO Document and Revision Emergency Equipment Inventory EPM-420 Rev 18 Part I. Description of Proposed Change:

EPM-420 Emergency Equipment Inventory is being revised to reflect changes required for the transition to a common EOF.

Removed attachments for the EOF. The HNP local EOF is being replaced by a common fleet EOF.

The Joint Information Center (JIC) inventory checklist has also been revised to support the relocation of the JIC from a conference room at the Customer Service Center that required extensive setup when used to a dedicated area in the Regional Headquarters Building in Raleigh.

Added review signature lines to the attachments to require responsible organization management review.

Added remarks throughout the attachments to require validation that applicable equipment is operable and that expiration dates are not expired or will not expire during the quarter.

Removed controlled documents from the attachments. These documents are distributed and controlled by the controlled document process.

Removed the position specific books that are being replaced with fleet standard controlled documents.

Revised the attachments to reflect removal and addition of items required for the inventory.

  • Removed flashlights from on-site kits that had both flashlights and lanterns.
  • Removed clocks from the kits.
  • Removed batteries from the kits that are readily available throughout the site.
  • Removed table position name plates that are being replaced with signage for the common ERO positions.
  • Removed rad rope, duct tape and step off pads from the Main Control Room kit. These items are readily available throughout the site.

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  • Removed work coveralls and paper coveralls from the on-site kits. These items are readily available throughout the site.
  • Removed pens, markers and like items from on-site kits. These items are readily available throughout the site.
  • Replaced forms in the Field Monitoring and Boat Shed Kits with the new fleet procedure forms.
  • Revised the Joint Information Center (JIC) Kit to reflect the items needed for the JIC to perform kits Emergency Plan functions. The JIC is being relocated to a facility that will allow it to be always set up and in a ready status. , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No X Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

NUREG-1038 Safety Evaluation Report Related to the Operation of Shearon Harris Nuclear power Plant, Units 1 and 2 Section 13.3.2.8 Emergency Facility and Equipment Standard Adequate emergency facilities and equipment to support the emergency response provided and maintained.

Evaluation Emergency facilities to support an emergency response have been established as follows:

(1) The control room (CR) contains those controls, instruments, and communications facilities necessary for operation of the plant under both normal and emergency conditions. The ventilation system, shielding, and the structure's Integrity are designed to permit continuous occupancy during postulated accidents. Storage is provided for food and water sufficient for 7 days.

(2) The TSC is located within the plant protected area in the fuel-handling building, approximately 400 feet (walking distance) from the CR. Traffic between the TSC and CR is entirely within buildings that are equipped with HEPA and charcoal filters and are built to seismic Category I, tornado, and missile safety-related criteria, with radiation protection equivalent to the CR. The TSC will have all the necessary equipment and supplies when fully functional to operate as the command center for the SEC and his staff.

(3) The OSC is located in the service building inside the protected area and functions as an assembly and dispatch area for all emergency teams.

(4) The EOF is located in the Shearon Harris Emergency and Environmental Center (SHEEC), approximately 2 miles from the plant, with space for approximately 70 people including 10 NRC personnel. The EOF is designed to have the same habitability as the CR, and will be provided with industrial security to maintain readiness and to restrict access during an emergency. The EOF is activated by the ERM when it is adequately staffed to perform offsite notification, environmental monitoring, and dose protection functions. The EOF has emergency equipment and supplies to perform as the command center for the ERM with plant system drawings, three Emergency Response Facility Information System (ERFIS) consoles displaying plant data, the Safety Parameter Display System (SPOS), the Radiological Monitoring System (RMS), dose projections, all pertinent emergency plans, telecopies, photocopies, and maps.

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(5) The Plant Media Center is also located at the SHEEC. The Site Public Information Coordinator directs the activities of the center to provide (1) a controlled point of contact and physical location near the plant for the news media and (2) immediate access to accurate emergency information generated by all involved agencies.

(6) The Corporate Emergency Operation Center (CEOC) and the Corporate Headquarters Media Center are located at the Corporate Headquarters and Civic Center in Raleigh, approximately 16 miles northeast of the plant on Highway 1.

(7) The North Carolina State Emergency Operations Center (SEOC) is also located in Raleigh at the Division of Emergency Management Headquarters.

The emergency response facilities appear to be adequately staffed, and the response times designated for the various staffing levels agree with the guide-lines of Table B-l of NUREG-0654.

The ERFs were evaluated as interim facilities in accordance with applicable portions of 10 CFR 50 and NUREG-0654 and found to be adequate. The applicant stated in a letter dated April 15, 1983, in response to Generic Letter 82-33, that the final facilities will be completed before fuel load, and then will be evaluated in accordance with Supplement 1 to NUREG-0737.

The plan states that equipment and systems for seismic monitoring, radiation monitoring, meteorological instrumentation, fire detection, gross failed fuel, loose parts monitoring, and security systems will be installed. The plan further states that additional information can be found in noted sections of the FSAR. A summary of the FSAR information should be included in the Emergency Plan so the emergency plan can stand as an independent document.

The fixed and mobile laboratory facilities available for support of SHNPP are discussed in Section 13.3.2.3 above.

The applicant's radiological monitoring program meets the staff's requirements.

A permanent meteorological monitoring station containing wind speed, direction and temperature differential instrumentation is located on the site. Provisions have been made to acquire back-up meteorological data from the National Weather-Service at the Raleigh-Durham Airport, a first order station operating 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day. The staff has reviewed the meteorological program and finds that it satisfies the planning standard on an interim basis; it will be evaluated during the Emergency Preparedness Implementation Analysis.

The plan provides in the implementing procedures a resource list for the inventory and calibration of emergency equipment and supplies. The plan also specifies the frequency of inventory and calibration.

The following items require resolution:

(1) The plan does not indicate if arrangements have been made to obtain or have access to seismic and hydrologic data from offsite sources.

(2) The plan implies that the OSC has the capacity to handle assigned personnel and equipment but fails to address the subject. Table 3.1-1 does not indicate the availability of portable lighting or cameras in the OSC emergency supply kits.

(3) The plan does not discuss in any detail which emergency facility will be established as the central point for receipt and analysis of all radiological samples.

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PLP-201 Emergency Plan Revision 3 3.1 General The purpose of emergency response facilities is to provide centralized locations for organized command and control of on-site activities, and off-site activities performed by the Company such as environmental monitoring.

Each emergency response organization is provided with a location from where they may direct or perform the activities for which they are responsible while providing for coordination of activities with other organizations.

Adequate emergency facilities, communications, and equipment to support emergency response are provided and maintained. Carolina Power & Light Company (CP&l) Emergency Plans include provision for emergency response facilities as follows:

  • Control Room
  • Operational Support Center (OSC)
  • Emergency Operations Facility (EOF)
  • Plant Media Center (PMC)
  • Corporate Emergency Operation~ Center (CEOC) 3.2 Control Room 3.2.3 Emergency Equipment and Supplies
a. Main Control Board
b. Emergency Response Facility Information System (ERFIS)
c. Safety Parameter Display System (SPDS) (Part of ERFIS)
d. Measurement and Indication of Regulatory Guide 1.97 (Rev. 2) variables (ERFIS)
e. Radiation Monitoring System (RMS)
f. Fire Detection System (adjacent room)
g. Seismic Monitoring Cabinet
h. Gross Failed Fuel Detector Console
i. Food and Water Storage for seven days
j. Basic medical supplies, kitchen and sanitary facilities
k. Reliable voice communications with the TSC, OSC, EOF, NRC Operations Centers and State and local government 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> warning points.
l. Respirators and anti-Cs
m. See Table 3.1-1 3.3 Technical Support Center (TSC)
3. 3. 3 Emergency Equipment and Supplies
a. Reliable voice communications with the Control Room, EOF, OSC, NRC Operations Center and State and local government 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> warning points as described in Section 3.8 which follows

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b. Four ERFIS consoles capable of displaying plant data, SPDS, RMS and dose projections as discussed in Section 3.9.1.
c. Mechanical systems, electrical systems drawings; Plant Operating Manual; FSAR; Corporate, plant, state & local emergency plans; photocopier, telecopier (also Document Control Library nearby)
d. Decontamination and monitoring area
e. Survey meter, area radiation monitor and constant air monitors f. Maps showing evacuation routes, evacuation areas, preselected radiological sampling and monitoring points, relocation centers in host areas, and shelter areas
g. Maps showing population distribution around the nuclear facility by evacuation areas (See Annex H)
h. See Table 3.1-1 3.4 Operational Support Center (OSC) 3.4.3 Emergency Equipment and Supplies
a. Reliable voice communications with the Control Room, EOF and TSC
b. Supplies and equipment as shown in Table 3.1-1 3.5 Emergency Operations Facility (EOF) 3.5.3 Emergency Equipment and Supplies
a. Reliable voice communications with the TSC, Control Room, OSC, NRC Operations Centers and State and local government 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> warning points as described in Section 3.8
b. Three ERFIS consoles capable of displaying plant data, SPDS, RMS and dose projections as discussed in Section 3.9.1
c. Mechanical Systems, Electrical Systems Drawings; Plant Operating Manual; FSAR; Corporate, Plant, State &

Local Emergency Plans; telecopier; photocopier

d. Decontamination and monitoring area
e. Survey meter, dosimeters and TLDs
f. Maps showing evacuation routes, evacuation areas. preselected radiological sampling and monitoring points, relocation centers in host areas, and shelter areas
g. Maps showing population distribution around the nuclear facility by evacuation areas
h. Additional equipment as discussed in Section 3.7.2.
i. See Table 3.1-1 3.6 Plant Media Center (PMC) 3.6.3 Emergency Equipment and Supplies

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a. Provided with additional telephone lines for media use
b. Provide equipment for document reproduction, telecopying, communications, and television electrical connections Table 3.1-1 Typical Emergency Supplies Available For Emergency Facilities Supplies Control Tech. Plant OSC EOF Room Support Media Center Center A supply of food and water adequate for 7 days Protective Clothing (Anti-Cs)

High and low range portable radiation survey instruments Air Sampling Equipment Emergency personnel monitoring equipment such as high and low range self-reading dosimeters and TLDs Area Maps Miscellaneous contamination control supplies such as signs, tags, rope, tape, various forms, etc First Aid Kit Portable Communications Equipment Radio Radio* Radio*

Remotes Remotes Remotes Full Face Respirators Environmental Monitoring Kit Self-contained breathing equipment Battery-Powered Lanterns Megaphone Polaroid Camera Decontamination Supplies Mechanical systems & electrical systems drawings, Plant Operation Manual, FSAR, Corporate, State &

Local Emergency Plans Copy of Plant Emergency Plan and Procedures (b) 10-mile EPZ Area maps (c)

Copy of Plant Emergency Plan and Procedures

  • Portable transceivers can be supplied to any emergency center

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PLP-201 Emergency Plan Revision 67 3.1 General The purpose of emergency response facilities is to provide centralized locations for organized command and control of on-site activities and off-site activities performed by the Company such as environmental monitoring.

Different groups within the Emergency Response Organization are provided with a location from where they may direct or perform the activities for which they are responsible while providing for coordination of activities with other organizations.

Adequate emergency facilities, communications, and equipment to support emergency response are provided and maintained. Duke Energy Emergency Plans include provision for emergency response facilities as follows:

  • Main Control Room (MCR)
  • Operations Support Center (OSC)
  • Emergency Operations Facility (EOF)
  • Joint Information Center (JIC) 3.2 Main Control Room 3.2.3 Emergency Equipment and Supplies A. Main Control Board.

B. Emergency Response Facility Information System (ERFIS).

C. Safety Parameter Display System (SPDS is part of ERFIS).

D. Measurement and Indication of Regulatory Guide 1.97 (Rev. 2) variables (ERFIS).

E. Radiation Monitoring System (RMS).

F. Fire Detection System (adjacent room).

G. Seismic Monitoring Cabinet.

H. Gross Failed Fuel Detector Console.

I. Kitchen and sanitary facilities.

J. Reliable voice communications with the TSC, OSC, EOF, NRC Operations Centers, and State and local government 24-hour warning points and State EOC.

K. See Table 3.1-1.

3.3 Technical Support Center 3.3.3 Emergency Equipment and Supplies A. Reliable voice communications with the Main Control Room, EOF, OSC, NRC Operations Center and State and

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local government 24-hour warning points and State EOC as described in Section 3.8 which follows.

B. Video System capable of displaying ERFIS information (such as, plant data, SPDS, and RMS) as discussed in Section 3.9.1.

C. All reference materials, including Mechanical and Electrical Systems Drawings; Controlled Procedure Manual; FSAR; Corporate, Plant, State, and Local Emergency Plans, are available.

D. Decontamination and monitoring area.

E. Survey meter and area radiation monitor.

F. Photocopier equipment and reliable facsimile transmission capability to the EOF and NRC Operations Center.

G. See Table 3.1-1.

3.4 Operations Support Center 3.4.3 Emergency Equipment and Supplies A. Reliable voice communications with the Main Control Room, EOF, and TSC.

B. Supplies and equipment as shown in Table 3.1-1.

3.5 Emergency Operations Facility 3.5.3 Emergency Equipment and Supplies A. Reliable voice communications with the TSC, Main Control Room, OSC, NRC Operations Centers and State and local government 24-hour warning points and State EOC as described in Section 3.8.

B. Video system capable of displaying ERFIS information (such as, plant data, SPDS, and RMS) as discussed in Section 3.9.1. ERFIS HMI Display terminals are continuously disconnected from ERFIS except during drills and emergencies to meet the cyber security rule. Procedure PEP-240, Activation and Operation of the Technical Support Center, directs telecommunications and computer support to connect and verify ERFIS is communicating to the EOF when the TSC is activated. This configuration helps eliminate potential cyber threats when the EOF is not activated.

C. All Reference materials, including Mechanical and Electrical Systems Drawings; Controlled Procedure Manual; FSAR; Corporate, Plant, State, and Local Emergency Plans, are available.

D. Decontamination and monitoring area.

E. Survey meter and dosimetry.

F. Maps showing evacuation routes, evacuation areas, preselected radiological sampling and monitoring points, relocation centers in host areas, and shelter areas.

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G. Photocopier equipment and reliable facsimile transmission capability to the TSC and NRC Operations Center.

H. Additional equipment as discussed in Section 3.8.2.

I. See Table 3.1-1.

Table 3.1-1 Typical Emergency Supplies Available For Emergency Facilities Supplies MCR TSC JIC OSC EOF 7 Day supply of food and water.

Protective Clothing (Anti-Cs)

Air Sampling equipment Full face respirators Self-contained breathing equipment High and low range portable radiation survey instruments Emergency personnel monitoring dosimetry Contamination control supplies such as signs, tags, rope, tape, various forms Decontamination supplies (a) (a)

Portable Communications Equipment Radio Radio Radio (a)

Remotes Remotes Remotes Battery-Powered Lanterns Camera Mechanical and electrical systems drawings, Controlled Procedure Manual, FSAR, Corporate, State & Local Emergency Plans (b) 10-mile EPZ Area maps (c)

Copy of Plant Emergency Plan and Procedures Environmental Monitoring Kits (d)

Potassium Iodide Tablets Indicates equipment/supplies available in this facility (a)

Portable radio transceivers can be supplied to any emergency facility (b)

Figure 1.5-2 of Emergency Plan in the MCR, wall maps in other facilities.

(c)

Procedures Only (d)

Stored near the Harris E&E Center Review RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An

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emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.

b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.
c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this procedure revision were made to reflect changes required for the transition to a common EOF and standard ERO structure.

EPM-420 is being revised to remove inventory checklists for the near site EOF and Alternate EOF because those facilities are being deactivated and the functions moved to the common EOF in Charlotte. Other changes are being made to the inventory checklists to remove items that no longer need to be included in the inventories.

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HNP will continue to have access to the equipment and supplies required by regulations. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2
  • PLP-201, Emergency Plan, Revision 67 Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(8)

Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

10 CFR 50 Appendix E IV.E Emergency Facilities and Equipment Adequate provisions shall be made and described for emergency facilities and equipment, including:

1. Equipment at the site for personnel monitoring;
2. Equipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment;
3. Facilities and supplies at the site for decontamination of onsite individuals; EPM-420 is being revised to remove inventory checklists for the near site EOF and Alternate EOF because those facilities are being deactivated and the functions moved to the common EOF in Charlotte.

The Joint Information Center (JIC) inventory checklist has also been revised to support the relocation of the JIC from a conference room at the Customer Service Center that required extensive setup when used to a dedicated area in the Regional Headquarters Building in Raleigh. Since this new location is dedicated for the JIC, the inventory list was revised.

Other changes are being made to the inventory checklists to remove items that no longer need to be included in the inventories and to reflect changes required to move to a standard ERO structure. An enhancement to the checklists to require validation that applicable equipment is operable and that expiration dates are not expired or will not expire during the quarter will help to ensure that the equipment remains functional and that dates do not expire. Also added line management review/approval to the inventory checklists, which will help to ensure that plant management is aware of emergency response facility equipment status.

HNP will continue to have access to the required supplies and equipment in the emergency response facilities to perform their functions as required by regulations and commitments.

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Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Planning Standard 10 CFR 50.47(b)(8)

Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

Planning Function Regulatory Guide 2.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors identifies the following standard for this standard:

4.8.b(2) Adequate equipment is maintained to support emergency response.

Planning Elements NUREG-0654 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants identifies the following elements for this standard:

Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

9. Each licensee shall provide for an onsite operations support center (assembly area) which shall have adequate capacity, and supplies, including, for example, respiratory protection, protective clothing, portable lighting, portable radiation monitoring equipment, cameras and communications equipment for personnel present in the assembly area.
10. Each organization shall make provisions to inspect, inventory and operationally check emergency equipment/instruments at least once each calendar quarter and after each use. There shall be sufficient reserves of instruments/equipment to replace those which are removed from emergency kits for calibration or repair.

Calibration of equipment shall be at intervals recommended by the supplier of the equipment.

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Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

EEPM-420 Emergency Equipment Inventory is being revised to reflect changes required for the transition to a common EOF.

Removed attachments for the EOF. The HNP local EOF is being replaced by a common fleet EOF.

The Joint Information Center (JIC) inventory checklist has also been revised to support the relocation of the JIC from a conference room at the Customer Service Center that required extensive setup when used to a dedicated area in the Regional Headquarters Building in Raleigh.

The EOF and JIC are being relocated to new locations. These moves support a fleet initiative for a common ERO structure. As a result, the equipment in the near site EOF and Alternate EOF is no longer needed and has been removed form this procedure. The JIC inventory has been adjusted to reflect a relocation from a conference room in the Customer Service Center that required extensive setup when used to a dedicated JIC in the Regional Headquarters Building.

Added review signature lines to the attachments to require responsible organization management review.

Added remarks throughout the attachments to require validation that applicable equipment is operable and that expiration dates are not expired or will not expire during the quarter.

The addition of line management review and validation that equipment is functional and within the required dates will help to ensure that equipment remains ready for an emergency and that line management has an awareness of emergency response facility equipment status.

Removed controlled documents from the attachments. These documents are distributed and controlled by the controlled document process.

Removed the position specific books that are being replaced with fleet standard controlled documents.

Controlled documents have their own process and therefore do not need to be included in the facility inventory.

There are also readily available libraries that have required hard copies of documents. Also, the positon books that were in use prior to moving to the common ERO were not controlled documents. The common ERO documents that are replacing the position books are now controlled documents.

Revised the attachments to reflect removal and addition of items required for the inventory.

  • Removed flashlights from on-site kits that had both flashlights and lanterns.
  • Removed clocks from the kits.
  • Removed batteries from the kits that are readily available throughout the site.
  • Removed table position name plates that are being replaced with signage for the common ERO positions.
  • Removed rad rope, duct tape and step off pads from the Main Control Room kit. These items are readily available throughout the site.
  • Removed work coveralls and paper coveralls from the on-site kits. These items are readily available throughout the site.

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  • Removed pens, markers and like items from on-site kits. These items are readily available throughout the site.
  • Replaced forms in the Field Monitoring and Boat Shed Kits with the new fleet procedure forms.

These changes remove items from the checklists that are readily available throughout the site. In addition, forms and signage are being replaced with the new procedure forms and signage for the common ERO.

The emergency planning function for the changes being made to this procedure that adequate equipment is maintained to support emergency response remains intact.

The changes being made to this procedure does not affect compliance with planning standard 10 CFR 50.47(b)(8) because HNP continues to have the equipment and supplies required by regulation in the emergency response facilities.

Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes X No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes X No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes X No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current X

Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

David Stih signed electronically in CAS 11/30/17 Reviewer Name (Print): Reviewer Signature: Date:

Jamey Sharlow signed electronically in CAS 11/30/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Greg Simmons signed electronically in CAS 12/05/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

X to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect. X QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:_____2165978_________ CNS CR3 HNP MNS 5AD #:_______2165976_________ ONS RNP GO Document and Revision PEP-240, REV SUP Activation and Operation of the Technical Support Center Part I. Description of Proposed Change:

Procedure is being superseded by AD-EP-ALL-0105, Activation and Operation of the Technical Support Center.

Commitments have been addressed as follows:

  • 6.1.1, CR 352310 is determined not to meet the definition of a commitment; however, this information is addressed in Attachment 16, Item 2.1.8, of AD-EP-ALL-0105.
  • 6.1.2, IER L1-11-2, is addressed in the following steps in AD-EP-ALL-0105: 7.1.1; Attachment 9, Step 2.1.2.
  • 6.1.3, IER L2-11-39, is addressed in the following steps in AD-EP-ALL-0105: 5.3.1.f, 7.1.3; Attachment 1 Step 1.3.1 note, Step 1.3.4, Step 1.3.5, Step 1.3.5.a.
  • 6.1.4, IER L1-13-10, is addressed in the following steps in AD-EP-ALL-0105: 7.1.2.c; Attachment 1, Step 3.7.1. , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

Planning Standard 1 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.1 Assignment of Responsibility (Organization Control)

Standard Primary responsibilities for emergency response by the nuclear facility licensee and by state and local organizations within the emergency planning zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Evaluation The plan identifies the specific individual and his successors who shall be in charge of the emergency response.

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PLP-201 Emergency Plan, Rev. 3 2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 General The plant emergency organization is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest number of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time.

PLP-201 Emergency Plan, Rev 67 2.0 ORGANIZATION AND RESPONSIBILITIES 2.2 Emergency Organization (Excerpts only)

The plant Emergency Response Organization (ERO) is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest numbers of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time Planning Standard 2 13.3.2.2 Onsite Emergency Organization Standard On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of responsive capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.

Evaluation The Shift Foreman for Unit 1 or the Shift Operating Supervisor for Units 1 and 2 will assume the position of Site Emergency Coordinator until relieved by the Plant General Manager, with authority to act on behalf of the company.

When the EOF is activated, the ERM assumes the responsibility for overall emergency response, and the Site Emergency Coordinator concentrates on onsite response. The Site Emergency Coordinator/Emergency Response Manager will not delegate the responsibility to notify and recommend protective actions to offsite authorities. The Site Emergency Coordinator may not delegate the responsibility to determine the classification of the emergency.

The duties and responsibilities of these two positions are clearly defined and the line of succession for each is

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specified in terms of normal staff positions.

Station staff personnel have been assigned emergency positions with responsibilities and duties commensurate with their normal activities.

PLP-201 Emergency Plan, Rev. 3 2.4.2 Site Emergency Coordinator The Site Emergency Coordinator, located in either the Control Room or the Technical Support Center, shall perform the following functions:

a. Coordinate and direct the activities of emergency response personnel in the Control Room, Technical Support Center, Operational Support Center and elsewhere on the plant site.
b. Designate an individua1 to be in charge of the Control Room.
c. Classify the emergency.
d. Ensure required notifications are made in a timely fashion.
e. Order the activation of the Technical Support Center, the Operational Support Center, and the Emergency Operations Facility when required.
f. Order the evacuation of nonessential personnel from the site when conditions warrant.
g. Keep the Emergency Response Manager (when the EOF is activated), the CEOC Manager (when the CEOC fs activated), the Nuclear Regulatory Commission, and appropriate State and local agencies informed as to the status of the plant and radiological effects off site.
h. Recommend protective actions which should be taken by the public to off-site government authorities until relieved of this responsibility by the Emergency Response Manager.
i. When contacted by the State, after an initial notification of an emergency, brief the State on the plant conditions and actions being taken.
j. Until the EOF is activated, provide updates to the State on the emergency condition and recommendations for protective actions at approximately 60 minute intervals, or if necessary, more frequently.
k. Request additional material, manpower, and equipment as necessary.
l. Ensure adequate manning, access control, and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> functional continuity of the Control Room, the Technical Support Center, and the Operational Support Center, when activated.
m. In the absence of the Plant General Manager and the. Environmental and Radiation Control Manager, approve planned personnel exposures in excess of 3Rem or entry into radiation fields greater than 100 R/hr.
n. Authorizes the Radiological Control Director to administer radio protective drugs (potassium iodide) to emergency workers in consultation with appropriate medical authority 2.4.3 Plant Operations Director The Plant Operations Director, located in the Technical Support Center, is responsible to the Site Emergency Coordinator for providing direction to the Accident Assessment Team, the Control Room Staff, the fire Brigade, and the First Aid Teams.

Specifically, the Plant Operations Director shall:

a. Direct the Accident Assessment Team and Central Room personnel in determining the nature and extent of emergencies pertaining to equipment and plant facilities.
b. Ensure immediate corrective actions are carried out by the Control Room personnel to minimize the consequences of the emergency.
c. Ensure adequate manning of the Control Room.
d. Coordinate recommendations to the Site Emergency Coordinator from the Accident Assessment Team.
e. Ensure that a trained computer console operator is stationed in the TSC and that data plotters stationed at the status boards fin the TSC.
f. Organize and direct rescue operations of injured personnel by the First Aid Team or search and rescue team.
g. Ensure fire brigade act1ons are in accordance with the F1re Plan and fire area preplans.
h. Request support from the Technical Analysis Manager, as necessary, after the EOF is activated.

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2.4.3.1 Accident Assessment Team Leader The Accident Assessment Team Leader reports to the Plant Operations Director and is located in the Technical Support Center.

The Accident Assessment Team Leader shall:

a. Supervise the total on-site technical staff effort. Acquire sufficient technical personnel to provide assistance throughout the emergency.
b. Monitor and evaluate vital plant parameters during an emergency to determine the overall condition of safety related systems, the core, and fission product barriers.
c. Monitor emergency conditions for changes in Emergency Action Level status and recommend to the Plant Operations Director any changes in the emergency classification when conditions so indicate.
d. Develop special procedures needed to reduce the consequences of an emergency condition.

2.4.3.2 Accident Assessment Team The Accident Assessment Team reports to the Accident Assessment Team Leader and is located in the Technical Support Center. The Team is composed of a Shift Technical Advisor and representatives from the various engineering disciplines in the plant's Technical Support Group.

2.4.4 Emergency Repair Director The Emergency Repair Director, located in the Technical Support Center. is responsible to the Site Emergency Coordinator for providing direction to the Damage Control Team Coordinator, Damage Control Team Leaders and the Operational Support Center (OSC) Leader. The Emergency Repair Director shall:

a. Direct the total on-site maintenance and equipment restoration effort.
b. Identify and develop required steps or procedures that need to be implemented to reduce the consequences of and recover from an emergency situation.
c. Define preferred and alternate ingress and egress routes in coordination with the Radiological Control Director.
d. Ensure that equipment is maintained during an emergency.

2.4.4.1 Damage Control Team Coordinator The Damage Control Team Coordinator located in the TSC is responsible to the Emergency Repair Director for performing damage control functions as follows:

a. Determine damage control needs based on accident assessment reports, equipment out of service reports, etc.
b. Dispatch damage control teams located in the OSC to the plant after properly briefing the Teams on the mission to be performed.
c. Direct and monitor the activities of the Damage Control Teams through their Damage Control Team Leaders.
d. Maintain a list of personnel assigned to Damage Control Teams and the locations of the Teams.
e. Report to the Emergency Repair Director the status of repair and restoration work being performed.

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2.4.5 Logistics Support Director The Logistics Support Director, located in the Technical Support Center, is responsible to the Site Emergency Coordinator for providing direction to the Site Communication Systems Coordinator, the Support Services Coordinator, the Security Team Leader, and the Assembly Area Leaders.

The Logistics Support Director shall:

a. Render the Technical Support Center operational upon determination by the Site Emergency Coordinator ti1at the TSC shall be activated.
b. Render the EOF operational upon the determination by the Site Emergency Coordinator that the EOF shall be activated.
c. Direct a staff in the TSC to carry out adm1n1strat1ve functions during an emergency.
d. Assist the Site Emergency Coordinator in arranging for shift reliefs and continual manning of the plant emergency staff.
e. Arrange for food and sleeping facilities for on-site emergency workers. *
f. Coordinate requests for materials, equipment, and supplies.
g. Arrange for additional services and provide new and/or modified contracts for services to be procured.
h. Ensure communications equipment is used to support the emergency and that all non-emergency communications are terminated.
i. Coordinate plant logistical requests through the Administrative and Logistics Manager when the EOF is activated.

2.4.5.1 Site Communications Systems Coordinator The Site Communications Systems Coordinator, located in the Technical Support Center, is responsible to the Logistics Support Director for the following actions:

a. Perform emergency repairs to on-site communications equipment necessary before off-site assistance arrives.
b. Assist on-site personnel with any communications equipment problems.
c. Provide general liaison and support necessary for expediting the efforts of the Corporate Systems Communications Coordinator. Assist the Administrative and Logistics Manager after the Emergency Operations Facility is activated.

2.4.5.2 Support Services Coordinator The Support Services Coordinator, located in the Technical Support Center, is responsible to the Logistics Support Director for the following actions:

a. Identify what materials and supplies are available on site and time necessary for delivery of other materials and supplies from off site to ensure supplies are not depleted and uninterrupted work can continue.
b. Coordinate and expedite requests for additional materials and supplies from the Logistics Support Director.

2.4.5.3 Emergency Security Team Leader The Emergency Security Team Leader, located in the Technical Support Center, reports to the Logistics Support Director and is responsible for the following activities:

a. Maintain plant security in accordance with the provisions of the SHNPP Security Plan and Safeguards Contingency Plan.
b. Assist the Assembly Area Leader(s) in the accounting of personnel.
c. Identify to the Logistics Support Director any non-routine security procedures and/or contingency conditions that are in effect or that require a response.
d. Provide Personnel, as available, for search teams for missing personnel. Identify areas and routes for searching in coordination with the Radiological Control Director.
e. Effect liaison with local law enforcement agencies.
f. Provide necessary members of the security force to maintain security at the EOF when activated.
g. Ensure the locations of security personnel are verified frequently.

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h. Generate periodic listings of personnel within the Protected Area.

2.4.6 Radiological Control Director The Radiological Control Director, located in the Technical Support Center, is responsible to the Site Emergency Coordinator for providing direction to the Dose Projection Team Leader, the Environmental Monitoring Team Leader, the Personnel Protection and Decontamination Team Leader and the Plant Monitoring Team Leader.

The Radiological Control Director shall:

a. Provide technical and administrative direction to the Plant Monitoring Team, Personnel Protection & Decontamination Team (PP&DT), Environmental Monitoring Team (until EOF is activated), and Dose Projection Team (until EOF is activated).
b. Coordinate initial off-site environmental monitoring and dose assessment efforts until such activities can be directed by the EOF.
c. Direct the Dose Projection Team and Plant Monitoring Team to accumulate, tabulate and evaluate data on plant conditions such as meteorological and radiation monitoring readings, hazardous material surveys, and other pertinent data.
d. Ensure use of protective clothing, respiratory protection, and access control within the plant as deemed appropriate to control personnel exposures.
e. Ensure that appropriate bioassay procedures have been implemented for on-site personnel when a radioactivity incident has occurred.
f. Ensure that personnel are decontaminated, if necessary.
g. Assist in the transfer of contaminated injured personnel and nonessential personnel.
h. Determine appropriate on-site personnel evacuation routes and alternate assembly areas when deemed necessary.
i. Coordinate and compare dose-assessment and monitoring results with the State {Department of Human Resources -

SER) until the EOF is activated.

j. Assist the counties by providing TLDs and providing a representative to assist in reading and analyzing dosage, when requested.
k. Manages administration of radio protective drugs (potassium iodide) to emergency workers in consultation with appropriate medical authority when authorized by the Site Emergency Coordinator.

2.4.6.1 Dose Projection Team Leader The Dose Projection Team Leader, located in the Technical Support Center, is responsible to the Radiological Control Director for directing the activities of the Dose Projection Team. Once the Emergency Operations Facility is activated, the dose projection function will be transferred to the Radiological Control Manager in the EOF.

The Dose Projection Team Leader shall:

a. Assign personnel to perform dose projection and source term calculations.
b. Interface with the Corporate Meteorology Center or the National Weather Service to obtain meteorological forecasts.*
c. Monitor source term data and meteorology data used by the Emergency Response Facility Information System (ERFIS) and Radiation Monitoring System (RMS) for reasonableness and identify any suspect parameters to the Radiological Control Director.
d. Assist in the orderly transfer of the dose assessment function to the EOF.

2.4.6.2 Dose Projection Team The Dose Projection Team Reports to the Dose Projection Team Leader and is located in the Dose Projection Room in the Technical Support Center. The Dose Projection Team is composed of health physics personnel.

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2.4.6.3 Environmental Monitoring Team Leader The Environmental Monitoring Team Leader, located in the Technical Support Center, is responsible to the Radiological Control Director for providing direction to the Environmental Monitoring Teams. Upon activation of the Technical Support Center, at least two Environmental Monitoring Teams will be deployed. Upon activation of the Emergency Operations Facility, the control and coordination of the environmental monitoring function will transfer to the EOF.

The Environmental Monitoring Team Leader shall:

a. Direct the activities of Environmental Monitoring Teams by positioning them such that representative samples and surveys of the plume, if any, can be made.
b. Advise team members of expected radiological conditions and protective gear to be worn.
c. Collect and evaluate Environmental Monitoring Teams sample and survey data.
d. Provide the results of environmental samples and surveys to the Radiological Control Director and the Dose Projection Team Leader.
e. Assist in the orderly transfer of the environmental monitoring function to the EOF.
f. Coordinate the use of the mobile laboratory.
g. Maintain a list of personnel assigned to each Environmental Monitoring Team and of Team locations.

2.4.6.5 Plant Monitoring Team Leader The Plant Monitoring Team Leader, located in the Technical Support Center, is responsible to the Radiological Control Director for providing direction to the Plant Monitoring Team during an emergency.

The Plant Monitoring Team Leader shall:

a. Provide personnel to conduct in-plant radiological surveys.
b. Assign personnel to operate the Post Accident Sampling System and obtain and analyze other samples as requested by the Radiological Control Director.
c. Monitor the Radiation Monitoring System and maintain a record of significant and unusual area radiation levels.
d. Assist the Dose Projection Team by developing the radiological source term from Radiation Monitoring System data, in-plant surveys, and samples.
e. Maintain personnel accountability of the Plant Monitoring Teams.

2.4.6.7 Personnel Protection and Decontamination Team Leader The Personnel Protection and Decontamination Team (PP&DT) Leader, located in the Technical Support Center. is responsible to the Radiological Control Director for providing direction to the PP&DT during an emergency.

The PP&DT Leader shall:

a. Assign personnel to accompany Damage Control Teams and reentry teams to provide health physics surveys.
b. Ensure that radiation levels in the TSC, OSC, and evacuation assembly areas are monitored.
c. Decontaminate contaminated personnel and/or on-site areas and equipment as necessary.
d. Administer radioprotective drugs under the direction of the Radiological Control Director.
e. Ensure that temporary access control is provided for radiation areas where necessary. Establish control points, monitoring points, and decontamination areas.
f. Establish temporary dosimetry issue areas where necessary.
g. Establish protective gear requirements for all on-site emergency personnel.
h. Assist the First Aid Team and notify the Radiological Control Director when transportation of a contaminated injured person is required
i. Maintain accountability of PP&DT members when they are outside the OSC.

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PLP-201 Emergency Plan, Rev 67 2.4.2 Technical Support Center A. Site Emergency Coordinator-TSC: The Site Emergency Coordinator-TSC is responsible for overall command and control of the on-site response to the emergency. The Site Emergency Coordinator is also responsible for providing guidance to the Technical Analysis Director, Radiological Control Director, Communications Director, Security Director, Plant Operations Director and the Emergency Repair Director.

Upon activation of the Technical Support Center the Site Emergency Coordinator-TSC relieves the Site Emergency Coordinator-MCR of the following major responsibilities:

1) Classification of the emergency.
2) Establishment of on-site mission priorities in response to the emergency.
3) Approval of planned radiation exposures for on-site personnel in excess of 5 Rem TEDE or entry into radiation fields greater than 25 Rem/hr.
4) Review and approval of deviations from Technical Specifications or license conditions. [7.0.U, Recommendation 5i]
5) Authorization of the administration of Potassium Iodide to on-site emergency workers.
6) A trained SAMG decision maker whose focus is on the development and prioritization aspect of the SAMG strategy.
7) Termination of the emergency.

B. TSC-Senior Reactor Operator: The TSC-Senior Reactor Operator is located in the Technical Support Center and reports to the Site Emergency Coordinator-TSC and directs the TSC-ERFIS Operator. The TSC-Senior Reactor Operator is responsible for providing technical assistance related to plant conditions and operations and to perform monitoring and evaluations required for Severe Accident Management Guidelines.

C. TSC-ERFIS Operator: The Technical Support Center ERFIS Operator reports to the TSC-SRO and is located in the Technical Support Center. The position is responsible for providing/displaying any information from ERFIS requested by Technical Support Center personnel.

D. Technical Analysis Director: The Technical Analysis Director reports to the Site Emergency Coordinator-TSC and is located in the Technical Support Center. The Technical Analysis Director is responsible for providing direction to the Technical Support Center Accident Assessment Team, performing, monitoring and evaluation required for core cooling flow paths, Severe Accident Management Guidelines, and directing AAT members to evaluate strategies that maintain or restore core cooling flow paths and implementing Severe Accident Management Guidelines. [7.0.U, Recommendation 4]

E. TSC-Accident Assessment Team: The TSC-Accident Assessment Team reports to the Technical Analysis Director and is located in the Technical Support Center. The team is composed of a Shift Technical Advisor, Core Performance Engineer, Electrical/I&C Engineer, and Mechanical Engineer. They are responsible for providing recommendations to the Technical Analysis Director on problems as assigned.

F. Communications Director: The Communications Director, located in the Technical Support Center, reports to the Site Emergency Coordinator TSC. The Communications Director is responsible for ensuring notification and communications to Offsite Authorities including the NRC and providing direction to the Emergency Communicator-NRC, TSC-Telecomm/Computer Support, TSC Logkeeper and the Admin Team.

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G. Emergency Communicator-NRC: Emergency Communicator-NRC is located in the Technical Support Center and reports to the Communications Director. The Emergency Communicator-NRC is responsible for:

1) Generating required written notifications to the NRC in a timely manner.
2) Establishing contact with the NRC via the Emergency Telecommunications System and providing any requested information of the status of the emergency.

H. TSC-Telecomm/Computer Support: TSC-Telecomm/Computer Support personnel are located in the Technical Support Center and report to the Communications Director. They are responsible for providing technical assistance required in the areas of telecommunications or computer support.

I. TSC Admin Team: The TSC Admin Team is located in the Technical Support Center and is composed of a Librarian and Admin Support personnel. They report to the Communications Director and are responsible for providing any documents, prints or other clerical services as requested by personnel in the Technical Support Center.

J. TSC Logkeeper: The TSC Logkeeper is located in the Technical Support Center and reports to the Communications Director. The TSC Logkeeper is responsible for recording the major activities that occur in the Technical Support Center during an emergency.

K. Radiological Control Director: The Radiological Control Director is located in the Technical Support Center and reports to the Site Emergency Coordinator-TSC. The Chemistry Coordinator and the Radiological Control Coordinator, both located in the Operations Support Center, report to the Radiological Control Director. The Radiological Control Director is responsible for:

1) Providing direction to onsite health physics and chemistry emergency response actions.
2) Ensuring that the Site Emergency Coordinator and other Directors in the Technical Support Center are kept informed of radiological/chemical conditions on and off site.

L. TSC HP Technician: The TSC HP Technician, normally located in the Technical Support Center, reports to the Radiological Control Director and is responsible for providing radiological support and monitoring activities within the TSC.

M. Security Director: The Security Director, normally located in the Technical Support Center, reports to the Site Emergency Coordinator-TSC and has the following major responsibilities:

1) Maintaining plant security in accordance with the provisions of the HNP Security Plan and Safeguards Contingency Plan.
2) Coordinating the accountability of personnel inside the Protected Area.
3) Providing Security Force personnel in support of emergency activities.

Planning Standard 9 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.9 Accident Assessment Standard Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency are in use.

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Evaluation The plan identifies the four emergency classes and discusses basic tests or criteria that must be considered in classifying the emergency (such as, radioactivity release, core damage, plant degradation).

The classification of the events is implemented through EALs, which are specific sets of plant conditions, instrument readings, and events coinciding with the initiating conditions associated with one of the emergency classes. The EALs are outlined in Figure 4.1-1, and will be discussed in detail in the plant emergency procedures, including specific instrument readings, plant system and effluent parameters, and equipment status indications corresponding to the initiating conditions of each emergency class.

The plan provides the onsite capability and resources to provide initial values and continuing assessment for the duration of an emergency such as the post-accident sampling system (PASS) and radiation monitoring systems.

The details of these systems--such as types, ranges, and location of monitors--and the PASS are discussed in appropriate sections of the FSAR.

Annex B of the plan describes the technical basis of the dose projection program, including calculation of source terms, dose conversion factors, atmospheric dispersion, and assumptions and limitations. The methodology and techniques for determining source terms and dose assessments will be detailed in plant emergency procedure 361.

Meteorological data from the onsite station is presented to the control room, the TSC, and the EOF via computer.

In case of off-scale or inoperable instrumentation, the cross reference in Annex B refers to PEP 361. There is no discussion of this contingency in the plan. The plan provides for environmental monitoring teams that will be activated in accordance with appropriate PEPS, equipped with company vehicles and sampling equipment, and capable of tracking the plume, obtaining and analyzing air samples, and sampling liquid effluents. The field monitoring equipment has the capability of measuring radioiodine in the vicinity of the plant site as low as 5x10-8 uCi/cc.

PLP-201 Emergency Plan, Rev. 3 4.4.4 Environmental Monitoring

a. Activation of Environmental Monitoring Teams will be in accordance with plant emergency procedures (PEP).
b. Environmental sampling and monitoring points are specified in Plant Emergency procedures.
c. At least two Environmental Monitoring Teams will initially be activated upon activation of the TSC.

Additional teams from the Shearon Harris Energy & Environmental Center can be called upon for support as needed.

d. The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments, and by obtaining and analyzing air samples.
e. The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents, such as the cooling tower blowdown.
f. Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency to ensure that a cumulative dose record is obtained.

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PLP-201 Emergency Plan, Rev 67 4.4.4 Environmental Monitoring

a. Environmental sampling and monitoring points are specified in environmental monitoring procedures.
b. Environmental Monitoring Teams will be activated in accordance with Table 2.2-1 and the appropriate implementing procedures. Additional teams can be called upon for support as needed.
c. The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments and by obtaining and analyzing air samples.
d. The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents, such as the cooling tower blowdown.
e. Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency to ensure that a cumulative dose record is obtained.

Planning Standard 10 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.10 Protective Response Standard A range of protective actions have been developed for the plume exposure pathway emergency planning zone for emergency workers and the public. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway emergency planning zone appropriate to the locale have been developed.

Evaluation The plan establishes the means and times to alert and notify onsite personnel of an emergency, and identifies the assembly areas adjacent to each of the gate houses. Personnel will be monitored for contamination at the assembly area. If it is necessary to evacuate further, evacuation routes and means of transportation are identified.

Holding areas for additional decontamination will be identified if necessary. Supervisors will account for all persons evacuated from within the protected area at the assembly area and report missing persons to appropriate supervision within 30 minutes. Security search procedures will be implemented to locate missing persons. The plan provides individual respiratory protection, protective clothing, and physician-supervised radioprotective drugs for the emergency workers.

PLP-201 Emergency Plan, Rev. 3 4.6.1 On-Site Alerting, Warning, and Notification The Plant Public Address (PA) System will be used to alert and notify on-site personnel of an emergency condition with 15 minutes. This includes the Protected Area, any construction areas, the parking lots, the cooling tower area, intake structure, cement plant and construction lay down areas. Security personnel with portable loudspeakers may be used to augment the PA system and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify personnel of those actions which should be taken.

The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this plan.

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4.6.3.1 Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. CP&L radiation and contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.4 of this plan. The radiation control facilities located in the Waste Processing Building (on the 261' and 286' level) include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area and radiation Control area.

Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level}. Additional personnel decontamination areas are located at radiation control areas at the north end of the Reactor Auxiliary Building (on the 261' level) and in the Turbine Building (on the 261' level). Radiation control and procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located near the first aid room in the Administration Building and at the SHE&E Center. Radiologically controlled areas can expanded by roping off areas and/or establishing access control points to maintain personnel exposure to As Low As Reasonably Achievable (ALARA) guidelines.

4.6.3.3 Use of Protective Equipment and Supplies During the course of ar. emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiologically Controlled Area. Measures that will be considered are:

  • Distribution of respirators;
  • Use of protective clothing; and
  • Use of thyroid blocking agents (Potassium Iodide).

The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures. Under the direction of a qualified Physician, administration of potassium iodide (KI), a radioprotective drug, to emergency response personnel may also be employed to mitigate the consequences of inhalation of radioiodines. Procedures for the administration of radioprotective drugs to employees are described in the plant emergency procedures.

PLP-201 Emergency Plan, Rev 67 4.6.1 On-Site Alerting, Warning, and Notification The Plant Public-Address (PA) System will be used to alert and notify on-site personnel of an emergency condition within 15 minutes. Security personnel with portable loudspeakers may be used to augment the PA system and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify personnel of those actions which should be taken. The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this Plan.

4.6.3 Radiological Exposure Control A. Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. HNP contamination control limits are shown in Table 4.6-1.

Emergency exposure guidance is given in Section 4.6.3.D of this plan. The radiation control facilities located in the Waste Processing Building include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area. Additional areas where equipment is decontaminated are located

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in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level). Radiation control and radiation control procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located in the Turbine Building and at the Harris Energy & Environmental Center. Radiation Control Areas can be expanded by roping off areas and/or establishing access control points to maintain personnel exposure As Low As Reasonably Achievable (ALARA).

B. Exposure Records for Emergency Workers Emergency workers will receive self reading pocket dosimeters (SRPDs) or equivalent and TLD badges. Dose records will be maintained by the Radiological Control Coordinator in accordance with PEP-330. TLDs are read at McGuire Island. They are capable of staffing 24-hour a day.

C. Use of Protective Equipment and Supplies During the course of an emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiation Control Area. Measures that will be considered are:

  • Use of process or engineering controls.
  • Distribution of respirators.
  • Use of protective clothing.
  • Use of thyroid blocking agents (Potassium Iodide).

The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures. Procedures for the administration of radioprotective drugs to employees are described in the plant emergency procedures.

Planning Standard 11 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.11 Radiological Exposure Control Standard Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Workers and lifesaving Activity Protective Action Guides.

Evaluation The plan provides for a radiation protection program for controlling radiological exposures in the event of an emergency. Emergency exposure guidelines, consistent with EPA Emergency Workers and Lifesaving Activity Protective Action Guides are specified for several categories of emergency workers. The plan specifies that the Plant General Manager or the Radiological Control Director may authorize emergency exposures in excess of 10 CFR 20 limits. In their absence, the Site Emergency Coordinator may grant such approval. The plan provides for 24-hour-a-day radiation safety controls to contain the spread of loose contamination and to monitor personnel exposure. Dose records will be maintained automatically utilizing the computerized Radiological Information Management System (RIMS).

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Action levels for determining the need for decontamination are summarized in Table 4.6-l of the plan from the Plant Operations Manual Procedure ERC-101. The applicant will establish the means for radiological decontamination of emergency personnel wounds, supplies, instruments, and equipment, and for waste disposal in Plant Emergency Procedure 393.

PLP-201 Emergency Plan, Rev 3 4.6.3.1 Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. CP&L radiation and contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.4 of this plan. The radiation control facilities located in the Waste Processing Building (on the 261' and 286' level) include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area and radiation Control area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level}. Additional personnel decontamination areas are located at radiation control areas at the north end of the Reactor Auxiliary Building (on the 261' level) and in the Turbine Building (on the 261' level). Radiation control and procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located near the first aid room in the Administration Building and at the SHE&E Center. Radiologically controlled areas can expanded by roping off areas and/or establishing access control points to maintain personnel exposure to As Low As Reasonably Achievable (ALARA) guidelines.

PLP-201 Emergency Plan, Rev 67 4.6.3 Radiological Exposure Control A. Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. HNP contamination control limits are shown in Table 4.6-1.

Emergency exposure guidance is given in Section 4.6.3.D of this plan. The radiation control facilities located in the Waste Processing Building include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level). Radiation control and radiation control procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located in the Turbine Building and at the Harris Energy & Environmental Center. Radiation Control Areas can be expanded by roping off areas and/or establishing access control points to maintain personnel exposure As Low As Reasonably Achievable (ALARA).

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RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies.

These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.

c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this procedure revision were made to reflect the changes for the EOF relocation to Charlotte and the changes made for Standard ERO. PEP-240 Activation and Operation of the Technical Support Center is being superseded by AD-EP-ALL-0105, Activation and Operation of the Technical Support Center.

Commitments identified in PEP-240 have been relocated to AD-EP-ALL-0105. HNP continues to maintain the capability to staff facilities, have specific responsibilities assigned to personnel, Assess an emergency, and provide protective actions onsite as needed during an emergency. These changes do not reduce the effectiveness of the

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emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2
  • PLP-201, Emergency Plan, Revision 67 Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(1), Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

b. Plant staff emergency assignments 10 CFR 50.47(b)(2), Onsite Emergency Organization On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

2. A description of the onsite emergency response organization (ERO) with a detailed discussion of:
a. Authorities, responsibilities, and duties of the individual(s) who will take charge during an emergency;
b. Plant staff emergency assignments;
c. Authorities, responsibilities, and duties of an onsite emergency coordinator who shall be in charge of the exchange of information with offsite authorities responsible for coordinating and implementing offsite emergency measures.

10 CFR 50.47(b)(9), Emergency Assessment Capability Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

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10 CFR Part 50, Appendix E Section IV.E, Emergency Facilities and Equipment Adequate provisions shall be made and described for emergency facilities and equipment, including:

2. Equipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment; 10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

10 CFR Part 50, Appendix E does not contain any supporting requirements 10 CFR 50.47(b)(11), Emergency Radiological Exposure Control Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides.

10 CFR Part 50, Appendix E Section IV.E. Emergency Facilities and Equipment Adequate provisions shall be made and described for emergency facilities and equipment, including:

1. Equipment at the site for personnel monitoring;
3. Facilities and supplies at the site for decontamination of onsite individuals; Evaluation Duke Energy nuclear stations will continue to have the capability to activate and perform the functions of a Technical Support Center. The changes described maintains compliance with the applicable sections of 10CFR50.47(b) and 10CFR50 Appendix E.

Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR 50.47(b)(1) Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Function Two emergency planning functions have been defined for this planning standard:

(1) Responsibility for emergency response is assigned.

(2) The response organization has the staff to respond and to augment staff on a continuing basis (i.e., 24/7 support) in accordance with the emergency plan.

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Element NUREG 0654 II. Section A.

Primary responsibilities for emergency response by the nuclear facility licensee, and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

NUREG 0654 II. Section J

7. Each licensee shall establish a mechanism for recommending protective actions to the appropriate State and local authorities. These shall include Emergency Action Levels corresponding to projected dose to the population-at-risk, in accordance with Appendix 1 and with the recommendations set forth in Tables 2.1 and 2.2 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-520/1-75-001). As specified in Appendix 1, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone.

Standard 10 CFR 50.47(b)(2), Onsite Emergency Organization On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

Function The process for timely augmentation of on-shift staff is established and maintained.

Element NUREG 0654 II. Section B.

5. Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table B-1 entitled, "Minimum Staffing Requirements for Nuclear Power Plant Emergencies." The minimum on-shift staffing levels shall be as indicated in Table B-1. The licensee must be able to augment on-shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table B-1. The implementation schedule for licensed operators, auxiliary operators and the shift technical advisor on shift shall be as specified in the July 31, 1980 letter to all power reactor licensees. Any deficiencies in the other staffing requirements of Table B-1 must be capable of augmentation within 30 minutes by September 1, 1981, and such deficiencies must be fully removed by July 1, 1982.
6. Each licensee shall specify the interfaces between and among the onsite functional areas of emergency activity, licensee headquarters support, local services support, and State and local government response organization. This shall be illustrated in a block diagram and shall include the onsite technical support center and the operational support (assembly) center and the licensee's near-site Emergency Operations Facility (EOF)
7. Each licensee shall specify the corporate management, administrative, and technical support personnel who will augment the plant staff as specified in the table entitled "Minimum Staffing Requirements for Nuclear Power Plant Emergencies," (Table B-1) and in the following areas:

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Standard 10 CFR 50.47(b)(9), Emergency Assessment Capability Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Function Methods, systems, and equipment for assessment of radioactive releases are in use.

Element NUREG 0654 II.Section I

3. Each licensee shall establish methods and techniques to be used for determining: the source term of releases of radioactive material within plant systems. An example is the relationship between the containment radiation monitor(s) reading(s) and radioactive material available for release from containment.

the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors.

6. Each organization shall describe the capability and resources for field monitoring within the plume exposure Emergency Planning Zone which are an intrinsic part of the concept of operations for the facility.

Standard 10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

Function A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

Element NUREG 0654 II.J.1-8 (Excerpts only)

1. Each licensee shall establish the means and time required to warn or advise onsite individuals and individuals who may be in areas controlled by the operator, including:

Employees not having emergency assignments; Visitors; Contractor and construction personnel; and Other persons who may be in the public access areas on or passing through the site or within the owner controlled area.

2. Each licensee shall make provisions for evacuation routes and transportation for onsite individuals to some suitable offsite location, including alternatives for inclement weather, high traffic density and specific radiological conditions.
3. Each licensee shall provide for radiological monitoring of people evacuated from the site.

4 Each licensee shall provide for the evacuation of onsite non-essential personnel in the event of a Site or General Emergency and shall provide a decontamination capability at or near the monitoring point specified in J.3.

6. Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for:

Individual respiratory protection; Use of protective clothing; and Use of radioprotective drugs, (e.g., individual thyroid protection).

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Standard 10 CFR 50.47(b)(11), Emergency Radiological Exposure Control Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides.

Function The resources for controlling radiological exposures for emergency workers are established Element NUREG 0654 II.K

2. Each licensee shall provide an onsite radiation protection program to be implemented during emergencies, including methods to implement exposure guidelines. The plan shall identify individual(s), by position or title, who can authorize emergency workers to receive doses in excess of 10 CFR Part 20 limits. Procedures shall be worked out in advance for permitting onsite volunteers to receive radiation exposures in the course of carrying out lifesaving and other emergency activities. These procedures shall include expeditious decision making and a reasonable consideration of relative risks.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Responsibility for emergency response is assigned.

The process for timely augmentation of on-shift staff is established and maintained.

Methods, systems, and equipment for assessment of radioactive releases are in use.

A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

The resources for controlling radiological exposures for emergency workers are established The adoption of the standard augmenting ERO will continue to maintain or improve the capability and timeliness of the HNP augmenting ERO to respond to an event and effectively perform their assigned tasks. HNP continues to determine the magnitude of an accident, mitigate effects of an accident an maintains the capability to protect the onsite staff and responding organizations during an emergency.

The changes described do not affect the emergency planning functions listed in Part IV associated with 10 CFR 50.47(b) because the changes ensure adequate personnel, as well as adequate processes to support and mitigate an emergency event. The changes do not affect supporting requirements described in 10 CFR 50, Appendix E.IV.

The changes continue to ensure that adequate provisions shall be made and described for emergency facilities and equipment and the changes continue to ensure the organization for coping with radiological emergencies is described.

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The changes described provide additional assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure the protection of the onsite emergency staff
  • effectively use response equipment and emergency response procedures to evaluate conditions and protect the staff.

These changes support the HNP Emergency Plan, by ensuring that procedures used during response to a classified emergency are available. Effective use of these procedures helps ensure emergency response functions as described in the Emergency Plan are adequately maintained and demonstrated. The functions identified in this procedure were relocated to applicable fleet procedures to standardize ERO task and functions across the Duke Energy Fleet.

The changes described maintain the functions as described in the HNP Emergency Plan, as written and approved; and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 11/30/17 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 11/30/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Greg Simmons signed electronically in CAS 11/30/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:_____2165575_____________ CNS CR3 HNP MNS 5AD #:_____2165571_____________ ONS RNP GO Document and Revision PEP-241, REV SUP Technical Support Center (TSC) Emergency Ventilation System Operation Part I. Description of Proposed Change: Procedure is being superseded by new procedure AD-EP-HNP-0105, HNP Site-Specific TSC Support.

No commitments are identified in this procedure. , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.8 Emergency Facility and Equipment (applicable sections)

Standard Adequate emergency facilities and equipment to support the emergency response provided and maintained.

Evaluation Emergency facilities to support an emergency response have been established as follows:

(2) The TSC is located within the plant protected area in the fuel-handling building, approximately 400 feet (walking distance) from the CR. Traffic between the TSC and CR is entirely within buildings that are equipped with HEPA and charcoal filters and are built to seismic Category I, tornado, and missile safety-related criteria, with radiation protection equivalent to the CR. The TSC will have all the necessary equipment and supplies when fully functional to operate as the command center for the SEC and his staff.

The ERFs were evaluated as interim facilities in accordance with applicable portions of 10 CFR 50 and NUREG-0654 and found to be adequate. The applicant stated in a letter dated April 15, 1983, in response to Generic Letter 82-33, that the final facilities will be completed before fuel load, and then will be evaluated in accordance with Supplement 1 to NUREG-0737.

The plan states that equipment and systems for seismic monitoring, radiation monitoring, meteorological instrumentation, fire detection, gross failed fuel, loose parts monitoring, and security systems will be installed. The plan further states that additional information can be found in noted sections of the FSAR. A summary of the FSAR information should be included in the Emergency Plan so the emergency plan can stand as an independent document.

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PLP-201 Emergency Plan , Rev. 3 3.3 Technical Support Center (TSC) 3.3.1 Characteristics A. Located within the Plant Protected area at Elevation 324'-0" in the Fuel Handling Building, approximately 400 feet walking distance from the Main Control Room (CR) (primary route).

B. Protective clothing and portable breathing apparatus are kept in both the TSC and Control Room for personnel who must traverse between the two. Alternative paths are available that can be used based upon radiological conditions as determined by monitoring teams.

C. Only the Site Emergency Coordinator, Plant Operations Director, and Emergency Communicator have need to travel between the Technical Support Center and the Control Room. If necessary, all required briefing can be conducted by telephone rather than face to face.

D. Exterior walls, roof, and floor are built to Seismic Category I, tornado, wind, and missile safety-related criteria.

E. Provided with radiation protection equivalent to Control Room habitability requirements such that the dose to an individual in the TSC for the duration of a design basis accident is less than five Rem to the whole body or its equivalent to other parts of the body. Ventilation System includes HEPA and charcoal filter.

F. Environmentally controlled to provide room air temperature, humidity and cleanliness appropriate for personnel and equipment.

G. Backup power for habitability systems and battery pack emergency lighting are provided.

H. Equipment is nonsafety related and nonredundant.

I. Designed taking into account good human factors engineering principles.

PLP-201 Emergency Plan, Rev 67 3.3 Technical Support Center (TSC) 3.3.1 Characteristics A. Located within the Protected Area at Elevation 324'-0" in the Fuel Handling Building, Section "K," approximately 400 feet walking distance from the Main Control Room (MCR) (primary route).

B. Protective clothing and portable breathing apparatus are kept in both the TSC and Main Control Room for personnel who must traverse between the two. Alternative paths are available that can be used based upon radiological conditions as determined by monitoring teams.

C. Exterior walls, roof, and floor are built to Seismic Category I, tornado, wind, and missile safety-related criteria.

D. Provided with radiation protection equivalent to Main Control Room habitability requirements such that the dose to an individual in the TSC for the duration of a design basis accident is less than 5 Rem TEDE. The Emergency Ventilation System includes HEPA and carbon filtration.

E. Environmentally controlled to provide room air temperature, humidity and cleanliness appropriate for personnel and equipment.

F. Reliable power for habitability systems and battery pack emergency lighting are provided.

G. Equipment is nonsafety-related and nonredundant.

H. Designed taking into account good human factors engineering principles.

I. Alternate location is the 305 Shift Manager, Shift Technical Advisor, and the Auxiliary Operator office area. [7.0.U, Recommendation 5h]

RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.

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c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4),

these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.

d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this procedure revision were made to reflect the changes for the EOF relocation to Charlotte and the changes made for Standard ERO. PEP-241 Technical Support Center (TSC) Emergency Ventilation System Operation is being superseded by AD-EP-HNP-0105, HNP Site-Specific TSC Support. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2
  • PLP-201, Emergency Plan, Revision 67 Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR50.47(b) (8), Emergency Facilities and Equipment The regulation at 10 CFR 50.47(b)(8) states the following:

Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

Two emergency planning functions have been defined for this planning standard:

(1) Adequate facilities are maintained to support emergency response.

(2) Adequate equipment is maintained to support emergency response. (not applicable to these changes) 10 CFR 50, Appendix E, Section IV. E. Emergency Facilities and Equipment (applicable excerpts only)

Adequate provisions shall be made and described for emergency facilities and equipment, including 8.a. (i) A licensee onsite technical support center and an emergency operations facility from which effective direction can be given and effective control can be exercised during an emergency;

b. For a nuclear power reactor licensee's emergency operations facility required by paragraph 8.a of this section, either a facility located between 10 miles and 25 miles of the nuclear power reactor site(s), or a primary facility located less than 10 miles from the nuclear power reactor site(s) and a backup facility located between 10 miles and 25 miles of the nuclear

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power reactor site(s).

PEP-241 Technical Support Center (TSC) Emergency Ventilation System Operation is being superseded by AD-EP-HNP-0105, HNP Site-Specific TSC Support. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in 10 CFR50.47(b) (8), Emergency Facilities and Equipment and 10 CFR 50, Appendix E, Section IV. E. Emergency Facilities and Equipment.

Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR50.47(b) (8), Emergency Facilities and Equipment The regulation at 10 CFR 50.47(b)(8) states the following:

Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

Two emergency planning functions have been defined for this planning standard:

(1) Adequate facilities are maintained to support emergency response.

Function 10 CFR 50, Appendix E, Section IV. E. Emergency Facilities and Equipment (applicable excerpts only)

Adequate provisions shall be made and described for emergency facilities and equipment, including 8.a. (i) A licensee onsite technical support center and an emergency operations facility from which effective direction can be given and effective control can be exercised during an emergency;

b. For a nuclear power reactor licensee's emergency operations facility required by paragraph 8.a of this section, either a facility located between 10 miles and 25 miles of the nuclear power reactor site(s), or a primary facility located less than 10 miles from the nuclear power reactor site(s) and a backup facility located between 10 miles and 25 miles of the nuclear power reactor site(s).

Element NUREG-0654/FEMA-REP-1 Rev 1, II, H. Emergency Facilities and Equipment Evaluation Criteria (applicable excerpts only )

1. Each licensee shall establish a Technical Support Center and an onsite operations support center (assembly area) in accordance with NUREG-0696, Revision 1.
5. Each licensee shall identify and establish onsite monitoring systems that are to be used to initiate emergency measures in accordance with Appendix 1, as well as those to be used for conducting assessment.

The equipment shall include:

a. geophysical phenomena monitors, (e.g., meteorological, hydrologic, seismic)
b. radiological monitors, (e.g., process, area, emergency, effluent, wound and portable monitors and sampling equipment);
c. process monitors, (e.g., reactor coolant system pressure and temperature, containment pressure and temperature, liquid levels, flow rates, status or lineup of equipment components); and
d. fire and combustion products detectors.
6. Each licensee shall make provision to acquire data from or for emergency access to offsite monitoring and analysis equipment including:
a. geophysical phenomena monitors, (e.g., meteorological, hydrologic, seismic);
b. radiological monitors including rate-meters and sampling devices. Dosimetry shall be provided and shall meet, as a minimum, the NRC Radiological Assessment Branch Technical Position for the Environmental Radiological Monitoring Program; and
c. laboratory facilities, fixed or mobile.

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Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Two emergency planning functions have been defined for 10 CFR 50.47(b)(8):

Two emergency planning functions have been defined for this planning standard (one applicable):

(1) Adequate facilities are maintained to support emergency response.

PEP-241 Technical Support Center (TSC) Emergency Ventilation System Operation is being superseded by AD-EP-HNP-0105, HNP Site-Specific TSC Support. AD-EP-HNP-0105 continues to maintain the capability to operate the emergency ventilation system and maintain the function of the Technical Support Center (TSC).

Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 11/29/17 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 11/29/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Jamey Sharlow signed electronically in CAS 11/29/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:____2164176_____________ CNS CR3 HNP MNS 5AD #:____2164172___________ ONS RNP GO Document and Revision PEP-250, REV SUP Activation and Operation of the Joint Information Center Part I. Description of Proposed Change:

Procedure is being superseded by AD-EP-ALL-0108, ACTIVATION AND OPERATION OF THE NEAR SITE JOINT INFORMATION CENTER(S)

Commitments have been transferred as follows:

  • IER 11-39, Lack of Timely ERO and ERF Activation, Recommendations 3a, 3b, and 3c, have been transferred to the following steps in AD-EP-ALL-0108:

5.2.15.a 5.2.15.b 5.4.13

  • IER-L1-13-10, Nuclear Accident at Fukushima Daiichi Nuclear Power Station, has been transferred to the following steps in AD-EP-ALL-0108:

5.2.15 , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Bases Yes Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

Planning Standard 1 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.1 Assignment of Responsibility (Organization Control)

Standard On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of responsive capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.

Evaluation The plan identifies the specific individual and his successors who shall be in charge of the emergency response.

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PLP-201 Emergency Plan, Rev. 3 2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 General The plant emergency organization is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest number of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities.

Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time.

PLP-201 Emergency Plan, Rev 67 2.0 ORGANIZATION AND RESPONSIBILITIES 2.2 Emergency Organization (Excerpts only)

The plant Emergency Response Organization (ERO) is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest numbers of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities.

Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time.

Planning Standard 7 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.7 Public Information (applicable sections)

Standard Information is made available to the public on a periodic basis on how it will be notified and what initial actions should be taken in an emergency; the principal points of contact with the news media for dissemination of information during an emergency (including physical location or locations) are established in advance; and procedures for coordinated dissemination of information to the public are established.

Evaluation The applicant will conduct a public information program for persons living in the plume exposure Emergency Planning Zone. The program will be accomplished by (1) yearly dissemination of brochures containing educational information on emergency preparedness, nuclear power, and radiation, and how to contact CP&L more information; (2) establishment of an emergency preparedness speakers bureau to allow qualified plant personnel to address civic, religious, social, and occupational organizations in the plant vicinity; and (3) preparation of news material for TV, radio, and the press and the general public. The applicant is working with both state and local governments to ensure that all public education efforts will be consistent and complementary.

PLP-201 Emergency Plan, Rev. 3 3.6 Plant Media Center (PMC) 3.6.1 Characteristics

a. Located at the Civic Center and Memorial Auditorium in Raleigh, NC.

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3.6.2 Functions

a. Provides controlled point of contact and physical location near plant for use by news media
b. Activities directed by Site Public Information Coordinator
c. Provide immediate access to accurate emergency related information generated by all involved agencies by media representatives
d. Coordinates information releases to the press as described in the Corporate Emergency Plan 3.6.3 Emergency Equipment and Supplies
a. Provided with additional telephones for media use
b. Provide equipment for document reproduction, telecopying, communications, and television electrical connections PLP-201 Emergency Plan, Rev 67 Section 3.6 Joint Information Center A. Located at the Duke Energy Customer Service Center in Raleigh, North Carolina, approximately 21 miles from the plant.

B. Serves as the primary location for accumulating accurate and current information regarding the emergency conditions and writing non-technical news releases.

C. Provides work space and phones for public information personnel from the state, counties, NRC, FEMA, and industry-related organizations.

D. Provides responses to media inquiries through media communicators who staff telephones that the media can call for information about an emergency.

E. Implements provisions for rumor control by providing a number of telephones which members of the public, who hear rumors, can call for factual information.

Section 5.2.5 Public Education and Information - HNP (Applicable excerpts)

During an actual emergency, provisions will be established through the Joint Information Center to make available and distribute information to the news media. Provisions for a number of telephones which members of the public, who hear rumors, can call for factual information will also be implemented in the JIC when activated.

RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.
c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4),

these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.

d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by

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the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.

e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this Evaluation were made to reflect the changes for the EOF relocation to Charlotte and the changes made for Standard ERO. PEP-250 Activation and Operation of the Joint Information Center is being superseded. All functions performed by this procedure has been moved to a fleet procedure. The commitments identified in this procedure has been relocated to AD-EP-ALL-0108 Activation and Operation of the Near Site Joint Information Center(s). This fleet procedure provides the same capability to perform the tasks across the fleet. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2
  • PLP-201, Emergency Plan, Revision 67 Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(1), Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

b. Plant staff emergency assignments 10 CFR 50.47(b)(7)Emergency Public Information The regulation at 10 CFR 50.47(b)(7) states the following:

Information is made available to the public on a periodic basis on how they will be notified and what their initial actions should be in an emergency (e.g., listening to a local broadcast station and remaining indoors), the principal points of contact with the news media for dissemination of information during an emergency (including the physical location or locations) are established in advance, and procedures for coordinated dissemination of information to the public are established.

Two emergency planning functions have been defined for this planning standard:

(1) Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway emergency planning zone (EPZ).

(2) Coordinated dissemination of public information during emergencies is established. (applicable) 10 CFR 50, Appendix E, Section IV. D. Notification Procedures (applicable excerpts only)

1. Administrative and physical means for notifying local, State, and Federal officials and agencies and agreements reached with these officials and agencies for the prompt notification of the public and for public evacuation or other protective measures, should they become necessary, shall be described. This description shall include identification of

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the appropriate officials, by title and agency, of the State and local government agencies within the EPZs.

2. Provisions shall be described for yearly dissemination to the public within the plume exposure pathway EPZ of basic emergency planning information, such as the methods and times required for public notification and the protective actions planned if an accident occurs, general information as to the nature and effects of radiation, and a listing of local broadcast stations that will be used for dissemination of information during an emergency. Signs or other measures shall also be used to disseminate to any transient population within the plume exposure pathway EPZ appropriate information that would be helpful if an accident occurs.

Evaluation Duke Energy nuclear stations will continue staff facilities, personnel continue to have clearly defined positions and responsibilities, and they continue to have the ability to inform the public of the events during an emergency. The changes described maintains compliance with the applicable sections of 10CFR50.47(b) and 10CFR50 Appendix E.

Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR 50.47(b)(1) Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Function Two emergency planning functions have been defined for this planning standard:

1) Responsibility for emergency response is assigned.
2) The response organization has the staff to respond and to augment staff on a continuing basis (i.e., 24/7 support) in accordance with the emergency plan.

Element NUREG 0654 II. Section A.

Primary responsibilities for emergency response by the nuclear facility licensee, and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

NUREG 0654 II. Section J

7. Each licensee shall establish a mechanism for recommending protective actions to the appropriate State and local authorities.

These shall include Emergency Action Levels corresponding to projected dose to the population-at-risk, in accordance with Appendix 1 and with the recommendations set forth in Tables 2.1 and 2.2 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-520/1-75-001). As specified in Appendix 1, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone.

Standard 10 CFR 50.47(b)(7)Emergency Public Information

a. The regulation at 10 CFR 50.47(b)(7) states the following:

Information is made available to the public on a periodic basis on how they will be notified and what their initial actions should be in an emergency (e.g., listening to a local broadcast station and remaining indoors), the principal points of contact with the news media for dissemination of information during an emergency (including the physical location or locations) are established in advance, and procedures for coordinated dissemination of information to the public are established.

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Function

b. Two emergency planning functions have been defined for this planning standard:

(1) Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway emergency planning zone (EPZ).

(2) Coordinated dissemination of public information during emergencies is established. (applicable)

Elements NUREG-0654/FEMA-REP-1 Rev 1, II, G. Public Education and Evaluation Evaluation Criteria (applicable excerpts only) 3.a Each principal organization shall designate the points of contact and physical locations for use by news media during an emergency.

3.b Each licensee shall provide space which may be used for a limited number of the news media at the near-site Emergency Operations Facility.

4.a Each principal organization shall designate a spokesperson who should have access to all necessary information.

4.b Each organization shall establish arrangements for timely exchange of information among designated spokespersons.

4.c Each organization shall establish coordinated arrangements for dealing with rumors.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Functions The following functions were identified in the performance of this evaluation:

Responsibility for emergency response is assigned.

Coordinated dissemination of public information during emergencies is established.

The adoption of the standard ERO will continue to maintain or improve the capability and timeliness of the HNP ERO to respond to an event and effectively keep the public informed of events during an emergency. HNP continues to maintain the capability to disseminate information to the public during emergencies.

The changes described do not affect the emergency planning functions listed in Part IV associated with 10 CFR 50.47(b) because the changes ensure adequate personnel are available, understand the roles assigned to them, and can operate a Joint Information Center. The changes do not affect supporting requirements described in 10 CFR 50, Appendix E.IV. The changes continue to ensure that adequate provisions shall be made and described for informing the public during an emergency and the changes continue to ensure the organization for coping with radiological emergencies is described.

The changes described provide additional assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure the public is informed of events during an emergency.

These changes support the HNP Emergency Plan, by ensuring that procedures used during response to a classified emergency are available. Effective use of these procedures helps ensure emergency response functions as described in the Emergency Plan are adequately maintained and demonstrated. The functions identified in this procedure were relocated to applicable fleet procedures to standardize ERO task and functions across the Duke Energy Fleet.

The changes described maintain the functions as described in the HNP Emergency Plan, as written and approved; and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

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Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 11/28/17 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 11/29/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Greg Simmons signed electronically in CAS 11/29/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:____2165554___________ CNS CR3 HNP MNS 5AD #:_____2165552____________ ONS RNP GO Document and Revision PEP-260, REV SUP Activation and Operation of the Operations Support Center Part I. Description of Proposed Change:

Procedure is being superseded by AD-EP-ALL-0106 and AD-EP-HNP-0106.

Commitments are addressed as follows:

  • 6.1.1.a, b, c: IER-L2-11-39, Lack of Timely ERO and ERF Activation (OPEX 489031), Recommendations 3a, 3b, and 3c, are addressed in AD-EP-ALL-0106.
  • 6.1.2.a, b: IER L1-13-10, Recommendations 5f and 5h, are addressed in AD-EP-HNP-0106. , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form, is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

Planning Standard 1 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.1 Assignment of Responsibility (Organization Control)

Standard Primary responsibilities for emergency response by the nuclear facility licensee and by state and local organizations within the emergency planning zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Evaluation The plan identifies the specific individual and his successors who shall be in charge of the emergency response.

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PLP-201 Emergency Plan, Rev. 3 2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 General The plant emergency organization is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest number of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities.

Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time PLP-201 Emergency Plan, Rev 67 2.0 ORGANIZATION AND RESPONSIBILITIES 2.2 Emergency Organization (Excerpts only)

The plant Emergency Response Organization (ERO) is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest numbers of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities.

Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time Planning Standard 2 13.3.2.2 Onsite Emergency Organization Standard On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of responsive capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.

Evaluation The Shift Foreman for Unit 1 or the Shift Operating Supervisor for Units 1 and 2 will assume the position of Site Emergency Coordinator until relieved by the Plant General Manager, with authority to act on behalf of the company. When the EOF is activated, the ERM assumes the responsibility for overall emergency response, and the Site Emergency Coordinator concentrates on onsite response. The Site Emergency Coordinator/Emergency Response Manager will not delegate the responsibility to notify and recommend protective actions to offsite authorities. The Site Emergency Coordinator may not delegate the responsibility to determine the classification of the emergency. The duties and responsibilities of these two positions are clearly defined and the line of succession for each is specified in terms of normal staff positions.

Station staff personnel have been assigned emergency positions with responsibilities and duties commensurate with their normal activities.

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PLP-201 Emergency Plan, Rev 3 2.4.4.2 Damage Control Team Leader The Damage Control Team Leaders assemble initially in the OSC and are responsible to the Damage Control Team Coordinator for on-the scene supervision of the Damage Control Teams to which they are assigned. The Damage Control Team Leaders shall:

a. Assess the nature and extent of damage incurred.
b. Perform emergency repairs
c. Perform actions to reduce the effect of the emergency, or to slow down a radiological release, when repair is not possible.
d. Acquire procedures, drawings, schematics, tools, radiation work permits, and other documentation necessary for the team's specific mission.
e. Assure that all Damage Control Team members are properly outfitted with equipment necessary for their missions, 4e.g., dosimeters, hardhats, flash lights, etc.).

2.4.4.3 Damage Control Team(s)

The Damage Control Teams are dispatched by the Damage Control Team Coordinator, from their initial assembly point in the OSC, to the scene of an emergency repair or damage assessment requirement. The Damage Control Teams report to the on-scene Damage Control Team Leader and are composed of mechanical, instrument and control, and electrical maintenance personnel, operations personnel, radiation control personnel, and an individual with a hand held radio.

2.4.4.4 Operational Support Center Leader The Operational Support Center Leader, located in the OSC, is responsible to the Emergency Repair Director for performing functions as follows:

a. Perform personnel accountability for the OSC by maintaining personnel logs and informing appropriate TSC personnel of emergency team assignment.
b. Compose, equip, and dispatch personnel {except Damage Control Teams) in response to requests from the Radiological Control Director, Emergency Repair Director, or Plant Operations Director.
c. Dispatch additional personnel and/or equipment as requested by the Plant Monitoring Team Leader, Personnel Protection and Decontamination Team Leader, or Damage Control Team Coordinator.
d. Monitor communications between Plant Monitoring Teams, Personnel Protection and Decontamination Teams, and Damage Control Teams and the Technical Support Center.

2.4.6.8 Personnel Protection and Decontamination Teams Personnel Protection and Decontamination Teams (PP&DT) report to the PP&DT Leader and are composed of radiation control personnel. They assemble initially in the Operational Support Center and are subsequently dispatched wherever personnel radiation control and decontamination* functions are needed.

PLP-201 Emergency Plan, Rev 67 2.4.3 Operations Support Center A. Emergency Repair Director: The Emergency Repair Director, located in the Operations Support Center, reports to the Site Emergency Coordinator-TSC. The Emergency Repair Director is responsible for providing direction to the total on-site maintenance and equipment restoration effort from the Operations Support Center.

B. Damage Control Coordinator: The Damage Control Coordinator, located in the Operations Support Center, reports to the Emergency Repair Director. The Damage Control Coordinator is responsible for providing direction to the Damage Control Team Leaders, Maintenance Planners, and OSC Logkeeper.

C. Damage Control Team Leaders: The Damage Control Team Leaders are appointed by the Damage Control Coordinator. They are responsible to the Damage Control Coordinator for on-the-scene supervision of the Damage Control Teams to which they are assigned.

D. Damage Control Teams: The Damage Control Teams are dispatched by the Damage Control Coordinator, from their initial assembly point in the Operations Support Center, to the scene of an emergency repair or damage assessment requirement. The Damage Control Teams report to the on-scene Damage Control Team Leader and are composed of mechanical, instrument and control, and electrical maintenance personnel.

E. Maintenance Planners: Maintenance Planners, located in the Operations Support Center, report to the Damage Control Coordinator. The Maintenance Planners are responsible for developing plans for emergency repair, determining spare parts needed to make the repairs and estimating the amount of time required to perform the emergency repairs.

F. OSC Logkeeper: The OSC Logkeeper, located in the Operations Support Center, reports to the Damage Control Coordinator. The OSC Logkeeper is responsible for recording the major activities that occur in the Operations Support Center during an emergency.

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G. Radiological Control Coordinator: The Radiological Control Coordinator, located in the Operations Support Center, is responsible to the Radiological Control Director for providing direction to the Radiological Control Teams during an emergency.

H. Radiological Control Teams: Radiological Control Teams report to the Radiological Control Coordinator and are composed of health physics personnel. They assemble initially in the Operations Support Center and are subsequently dispatched wherever personnel radiation control and decontamination functions are needed.

I. Chemistry Coordinator: The Chemistry Coordinator, located in the OSC, is responsible to the Radiological Control Director for providing direction to the Chemistry Team during an emergency.

J. Chemistry Team: Chemistry Teams report to the Chemistry Coordinator and are composed of plant chemistry personnel. They assemble initially in the Operations Support Center and are subsequently dispatched to sampling stations and the laboratory.

Planning Standard 9 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.9 Accident Assessment Standard Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency are in use.

Evaluation The plan identifies the four emergency classes and discusses basic tests or criteria that must be considered in classifying the emergency (such as, radioactivity release, core damage, plant degradation).

The classification of the events is implemented through EALs, which are specific sets of plant conditions, instrument readings, and events coinciding with the initiating conditions associated with one of the emergency classes. The EALs are outlined in Figure 4.1-1, and will be discussed in detail in the plant emergency procedures, including specific instrument readings, plant system and effluent parameters, and equipment status indications corresponding to the initiating conditions of each emergency class.

The plan provides the onsite capability and resources to provide initial values and continuing assessment for the duration of an emergency such as the postaccident sampling system (PASS) and radiation monitoring systems. The details of these systems--

such as types, ranges, and location of monitors--and the PASS are discussed in appropriate sections of the FSAR.

Annex B of the plan describes the technical basis of the dose projection program, including calculation of source terms, dose conversion factors, atmospheric dispersion, and assumptions and limitations. The methodology and techniques for determining source terms and dose assessments will be detailed in plant emergency procedure 361.

Meteorological data from the onsite station is presented to the control room, the TSC, and the EOF via computer.

In case of off-scale or inoperable instrumentation, the cross reference in Annex B refers to PEP 361. There is no discussion of this contingency in the plan. The plan provides for environmental monitoring teams that will be activated in accordance with appropriate PEPS, equipped with company vehicles and sampling equipment, and capable of tracking the plume, obtaining and analyzing air samples, and sampling liquid effluents. The field monitoring equipment has the capability of measuring radioiodine in the vicinity of the plant site as low as 5x10-8 uCi/cc.

PLP-201 Emergency Plan, Rev. 3 4.4.4 Environmental Monitoring

a. Activation of Environmental Monitoring Teams will be in accordance with plant emergency procedures (PEP).
b. Environmental sampling and monitoring points are specified in Plant Emergency procedures.
c. At least two Environmental Monitoring Teams will initially be activated upon activation of the TSC. Additional teams from the Shearon Harris Energy & Environmental Center can be called upon for support as needed.
d. The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments and by obtaining and analyzing air samples.
e. The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents, such as the cooling tower blowdown.
f. Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency

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to ensure that a cumulative dose record is obtained.

PLP-201 Emergency Plan, Rev 67 4.4.4 Environmental Monitoring A. Environmental sampling and monitoring points are specified in environmental monitoring procedures.

B. Environmental Monitoring Teams will be activated in accordance with Table 2.2-1 and the appropriate implementing procedures. Additional teams can be called upon for support as needed.

C. The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments and by obtaining and analyzing air samples.

D. The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents, such as the cooling tower blowdown.

E. Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency to ensure that a cumulative dose record is obtained.

Planning Standard 10 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.10 Protective Response Standard A range of protective actions have been developed for the plume exposure pathway emergency planning zone for emergency workers and the public. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway emergency planning zone appropriate to the locale have been developed.

Evaluation The plan establishes the means and times to alert and notify onsite personnel of an emergency, and identifies the assembly areas adjacent to each of the gate houses. Personnel will be monitored for contamination at the assembly area. If it is necessary to evacuate further, evacuation routes and means of transportation are identified. Holding areas for additional decontamination will be identified if necessary. Supervisors will account for all persons evacuated from within the protected area at the assembly area and report missing persons to appropriate supervision within 30 minutes. Security search procedures will be implemented to locate missing persons. The plan provides individual respiratory protection, protective clothing, and physician-supervised radioprotective drugs for the emergency workers.

PLP-201 Emergency Plan, Rev. 3 4.6.1 On-Site Alerting, Warning, and Notification The Plant Public Address (PA) System will be used to alert and notify on-site personnel of an emergency condition with 15 minutes. This includes the Protected Area, any construction areas, the parking lots, the cooling tower area, intake structure, cement plant and construction lay down areas. Security personnel with portable loudspeakers may be used to augment the PA system and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify personnel of those actions which should be taken. The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this Plan.

4.6.3.1 Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. CP&L radiation and contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.4 of this plan. The radiation control facilities located in the Waste Processing Building (on the 261' and 286' level) include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area and radiation Control area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level}.

Additional personnel decontamination areas are located at radiation control areas at the north end of the Reactor Auxiliary Building (on the 261' level) and in the Turbine Building (on the 261' level). Radiation control and procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located near the first aid room in

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the Administration Building and at the SHE&E Center. Radiologically controlled areas can expanded by roping off areas and/or establishing access control points to maintain personnel exposure to As Low As Reasonably Achievable (ALARA) guidelines.

4.6.3.3 Use of Protective Equipment and Supplies During the course of ar. emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiologically Controlled Area. Measures that will be considered are:

  • Distribution of respirators;
  • Use of protective clothing; and
  • Use of thyroid blocking agents (Potassium Iodide).

The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures. Under the direction of a qualified Physician, administration of potassium iodide (KI), a radioprotective drug, to emergency response personnel may also be employed to mitigate the consequences of inhalation of radioiodines.

Procedures for the administration of radioprotective drugs to employees are described in the plant emergency procedures.

PLP-201 Emergency Plan, Rev 67 4.6.1 On-Site Alerting, Warning, and Notification The Plant Public-Address (PA) System will be used to alert and notify on-site personnel of an emergency condition within 15 minutes. Security personnel with portable loudspeakers may be used to augment the PA system and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify personnel of those actions which should be taken. The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this Plan.

4.6.3 Radiological Exposure Control A. Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. HNP contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.D of this plan. The radiation control facilities located in the Waste Processing Building include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level). Radiation control and radiation control procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located in the Turbine Building and at the Harris Energy & Environmental Center. Radiation Control Areas can be expanded by roping off areas and/or establishing access control points to maintain personnel exposure As Low As Reasonably Achievable (ALARA).

B. Exposure Records for Emergency Workers Emergency workers will receive self-reading pocket dosimeters (SRPDs) or equivalent and TLD badges. Dose records will be maintained by the Radiological Control Coordinator in accordance with PEP-330. TLDs are read at McGuire Island. They are capable of staffing 24-hour a day.

C. Use of Protective Equipment and Supplies During the course of an emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiation Control Area. Measures that will be considered are:

  • Use of process or engineering controls.
  • Distribution of respirators.
  • Use of protective clothing.
  • Use of thyroid blocking agents (Potassium Iodide).

The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures. Procedures for the administration of radioprotective drugs to employees are described in the plant emergency procedures.

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Planning Standard 11 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.11 Radiological Exposure Control Standard Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Workers and lifesaving Activity Protective Action Guides.

Evaluation The plan provides for a radiation protection program for controlling radiological exposures in the event of an emergency.

Emergency exposure guidelines, consistent with EPA Emergency Workers and Lifesaving Activity Protective Action Guides are specified for several categories of emergency workers. The plan specifies that the Plant General Manager or the Radiological Control Director may authorize emergency exposures in excess of 10 CFR 20 limits. In their absence, the Site Emergency Coordinator may grant such approval. The plan provides for 24-hour-a-day radiation safety controls to contain the spread of loose contamination and to monitor personnel exposure. Dose records will be maintained automatically utilizing the computerized Radiological Information Management System (RIMS).

Action levels for determining the need for decontamination are summarized in Table 4.6-l of the plan from the Plant Operations Manual Procedure ERC-101. The applicant will establish the means for radiological decontamination of emergency personnel wounds, supplies, instruments, and equipment, and for waste disposal in Plant Emergency Procedure 393.

PLP-201 Emergency Plan, Rev 3 4.6.3.1 Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. CP&L radiation and contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.4 of this plan. The radiation control facilities located in the Waste Processing Building (on the 261' and 286' level) include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area and radiation Control area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level}.

Additional personnel decontamination areas are located at radiation control areas at the north end of the Reactor Auxiliary Building (on the 261' level) and in the Turbine Building (on the 261' level). Radiation control and procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located near the first aid room in the Administration Building and at the SHE&E Center. Radiologically controlled areas can expanded by roping off areas and/or establishing access control points to maintain personnel exposure to As Low As Reasonably Achievable (ALARA) guidelines.

PLP-201 Emergency Plan, Rev 67 4.6.3 Radiological Exposure Control A. Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. HNP contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.D of this plan. The radiation control facilities located in the Waste Processing Building include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level). Radiation control and radiation control procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located in the Turbine Building and at the Harris Energy & Environmental Center. Radiation Control Areas can be expanded by roping off areas and/or

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establishing access control points to maintain personnel exposure As Low As Reasonably Achievable (ALARA).

RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.
c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4),

these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.

d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this procedure revision were made to reflect the changes for the EOF relocation to Charlotte and the changes made for Standard ERO. PEP-260 Activation and Operation of the Operations Support Facility is being superseded by AD-EP-ALL-0106, Operations Support Facility (OSC) Activation and AD-EP-HNP-0106, HNP Site Specific OSC Support.

Commitments identified in PEP-260 have been relocated to AD-EP-ALL-0106 and AD-EP-HNP-0106 as identified. HNP continues to maintain the capability to staff facilities, have specific responsibilities assigned to personnel, provide damage assessment and protect the emergency response personnel during an emergency, These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2

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Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(1), Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

b. Plant staff emergency assignments 10 CFR 50.47(b)(2), Onsite Emergency Organization On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

2. A description of the onsite emergency response organization (ERO) with a detailed discussion of:
a. Authorities, responsibilities, and duties of the individual(s) who will take charge during an emergency;
b. Plant staff emergency assignments;
c. Authorities, responsibilities, and duties of an onsite emergency coordinator who shall be in charge of the exchange of information with offsite authorities responsible for coordinating and implementing offsite emergency measures.

10 CFR 50.47(b)(9), Emergency Assessment Capability Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

10 CFR Part 50, Appendix E Section IV.E, Emergency Facilities and Equipment Adequate provisions shall be made and described for emergency facilities and equipment, including:

2. Equipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment; 10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public.

In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

10 CFR Part 50, Appendix E does not contain any supporting requirements.

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10 CFR 50.47(b)(11), Emergency Radiological Exposure Control Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides.

10 CFR Part 50, Appendix E Section IV.E. Emergency Facilities and Equipment Adequate provisions shall be made and described for emergency facilities and equipment, including:

1. Equipment at the site for personnel monitoring;
3. Facilities and supplies at the site for decontamination of onsite individuals; Evaluation HNP will continue to have the capability to activate and perform the functions of an OSC. The changes described maintains compliance with the applicable sections of 10CFR50.47(b) and 10CFR50 Appendix E.

Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR 50.47(b)(1) Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Function Two emergency planning functions have been defined for this planning standard:

(1) Responsibility for emergency response is assigned.

(2) The response organization has the staff to respond and to augment staff on a continuing basis (i.e., 24/7 support) in accordance with the emergency plan.

Element NUREG 0654 II. Section A.

Primary responsibilities for emergency response by the nuclear facility licensee, and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

NUREG 0654 II. Section J

7. Each licensee shall establish a mechanism for recommending protective actions to the appropriate State and local authorities.

These shall include Emergency Action Levels corresponding to projected dose to the population-at-risk, in accordance with Appendix 1 and with the recommendations set forth in Tables 2.1 and 2.2 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-520/1-75-001). As specified in Appendix 1, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone.

Standard 10 CFR 50.47(b)(2), Onsite Emergency Organization On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

Function The process for timely augmentation of onshift staff is established and maintained.

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Element NUREG 0654 II. Section B.

5. Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table B-1 entitled, "Minimum Staffing Requirements for Nuclear Power Plant Emergencies." The minimum on-shift staffing levels shall be as indicated in Table B-1. The licensee must be able to augment on-shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table B-1. The implementation schedule for licensed operators, auxiliary operators and the shift technical advisor on shift shall be as specified in the July 31, 1980 letter to all power reactor licensees.

Any deficiencies in the other staffing requirements of Table B-1 must be capable of augmentation within 30 minutes by September 1, 1981, and such deficiencies must be fully removed by July 1, 1982.

6. Each licensee shall specify the interfaces between and among the onsite functional areas of emergency activity, licensee headquarters support, local services support, and State and local government response organization. This shall be illustrated in a block diagram and shall include the onsite technical support center and the operational support (assembly) center and the licensee's near-site Emergency Operations Facility (EOF)
7. Each licensee shall specify the corporate management, administrative, and technical support personnel who will augment the plant staff as specified in the table entitled "Minimum Staffing Requirements for Nuclear Power Plant Emergencies," (Table B-1) and in the following areas Standard 10 CFR 50.47(b)(9), Emergency Assessment Capability Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Function Methods, systems, and equipment for assessment of radioactive releases are in use.

Element NUREG 0654 II.Section I

3. Each licensee shall establish methods and techniques to be used for determining: the source term of releases of radioactive material within plant systems. An example is the relationship between the containment radiation monitor(s) reading(s) and radioactive material available for release from containment.

the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors.

6. Each organization shall describe the capability and resources for field monitoring within the plume exposure Emergency Planning Zone which are an intrinsic part of the concept of operations for the facility.

Standard 10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public.

In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

Function A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

Element NUREG 0654 II.J.1-8 (Excerpts only)

1. Each licensee shall establish the means and time required to warn or advise onsite individuals and individuals who may be in areas controlled by the operator, including:

Employees not having emergency assignments; Visitors; Contractor and construction personnel; and Other persons who may be in the public access areas on or passing through the site or within the owner controlled area.

2. Each licensee shall make provisions for evacuation routes and transportation for onsite individuals to some suitable offsite location, including alternatives for inclement weather, high traffic density and specific radiological conditions.
3. Each licensee shall provide for radiological monitoring of people evacuated from the site.

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4 Each licensee shall provide for the evacuation of onsite non-essential personnel in the event of a Site or General Emergency and shall provide a decontamination capability at or near the monitoring point specified in J.3.

6. Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for:

Individual respiratory protection; Use of protective clothing; and Use of radioprotective drugs, (e.g., individual thyroid protection).

Standard 10 CFR 50.47(b)(11), Emergency Radiological Exposure Control Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides.

Function The resources for controlling radiological exposures for emergency workers are established Element NUREG 0654 II.K

2. Each licensee shall provide an onsite radiation protection program to be implemented during emergencies, including methods to implement exposure guidelines. The plan shall identify individual(s), by position or title, who can authorize emergency workers to receive doses in excess of 10 CFR Part 20 limits. Procedures shall be worked out in advance for permitting onsite volunteers to receive radiation exposures in the course of carrying out lifesaving and other emergency activities. These procedures shall include expeditious decision making and a reasonable consideration of relative risks.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Responsibility for emergency response is assigned.

The process for timely augmentation of onshift staff is established and maintained.

Methods, systems, and equipment for assessment of radioactive releases are in use.

A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

The resources for controlling radiological exposures for emergency workers are established The adoption of the standard augmenting ERO will continue to maintain or improve the capability and timeliness of the HNP augmenting ERO to respond to an event and effectively perform their assigned tasks. HNP continues to determine the magnitude of an accident, mitigate effects of an accident and maintains the capability to protect the onsite staff and responding organizations during an emergency.

The changes described do not affect the emergency planning functions listed in Part IV associated with 10 CFR 50.47(b) because the changes ensure adequate personnel, as well as adequate processes to support and mitigate a emergency event.

The changes do not affect supporting requirements described in 10 CFR 50, Appendix E.IV. The changes continue to ensure that adequate provisions shall be made and described for emergency facilities and equipment and the changes continue to ensure the organization for coping with radiological emergencies is described.

The changes described provide additional assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure the protection of the onsite emergency staff
  • effectively use response equipment and emergency response procedures to evaluate conditions and protect the staff.

These changes support the HNP Emergency Plan, by ensuring that procedures used during response to a classified emergency are available. Effective use of these procedures helps ensure emergency response functions as described in the Emergency

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Plan are adequately maintained and demonstrated. The functions identified in this procedure were relocated to applicable fleet procedures to standardize ERO task and functions across the Duke Energy Fleet.

The changes described maintain the functions as described in the HNP Emergency Plan, as written and approved; and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 11/29/17 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 11/29/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Jamey Sharlow signed electronically in CAS 11/29/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:_____2164166____________ CNS CR3 HNP MNS 5AD #:_____2164162______________ ONS RNP GO Document and Revision PEP-270, REV SUP Activation and Operation of the Emergency Operations Facility Part I. Description of Proposed Change:

  • 6.1.1, IER 11-39, Lack of Timely ERO and ERF Activation Recommendations 3a, 3b, and 3c; commitments have been transferred to the fleet procedure in Attachment 6, Steps 2.1.1.a and b; and Attachment 12, Step 2.1
  • 6.1.2, IER L1-13-10, Nuclear Accident at Fukushima Daiichi Nuclear Power Station, Recommendations 5h, 7, 11a, and 11b; commitments have been transferred to the fleet procedure in Steps 2.0.1, and 5.2.3.i; Attachment 5, Step 2.4.1 and Step 2.4.1.a(2); Attachment 6, Step 2.1.1.b; and Attachment 12, Step 2.1.6. , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

Procedure being superseded by AD-EP-ALL-0103, Emergency Operations Facility (EOF) Activation. Commitments were addressed as follows:

Planning Standard 1 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.2 Onsite Emergency Organization Standard On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of responsive capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.

Evaluation Station staff personnel have been assigned emergency positions with responsibilities and duties commensurate with their normal activities.

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PLP-201 Emergency Plan, Rev. 3 2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 General The plant emergency organization is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest number of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time.

PLP-201 Emergency Plan, Rev 67 2.0 ORGANIZATION AND RESPONSIBILITIES 2.2 Emergency Organization (Excerpts only)

The plant Emergency Response Organization (ERO) is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest numbers of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time.

Planning Standard 2 13.3.2.2 Onsite Emergency Organization Standard On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of responsive capabilities is available, and the interfaces among various onsite response activities and offsite support and response activities are specified.

Evaluation The Shift Foreman for Unit 1 or the Shift Operating Supervisor for Units 1 and 2 will assume the position of Site Emergency Coordinator until relieved by the Plant General Manager, with authority to act on behalf of the company.

When the EOF is activated, the ERM assumes the responsibility for overall emergency response, and the Site Emergency Coordinator concentrates on onsite response. The Site Emergency Coordinator/Emergency Response Manager will not delegate the responsibility to notify and recommend protective actions to offsite authorities. The Site Emergency Coordinator may not delegate the responsibility to determine the classification of the emergency.

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The duties and responsibilities of these two positions are clearly defined and the line of succession for each is specified in terms of normal staff positions.

Station staff personnel have been assigned emergency positions with responsibilities and duties commensurate with their normal activities.

PLP-201 Emergency Plan, Rev 3 2.4.10 Emergency Response Manager and Staff The Emergency Response Manager (ERM) is responsible for managing and directing all off-site related emergency operations involving the plant upon activation of the Emergency Operations Facility. He relieves the Site Emergency Coordinator of the requirements for all off-site related activities. He provides liaison between the Site Emergency Coordinator and off-site support personnel {Corporate Headquarters, Corporate Spokesman, Media Team leaders, State and Federal agencies), and controls off-site support as required to support the Site Emergency Coordinator. He manages an EOF staff organization consisting of the following positions as shown in Figure 2.4-1 and described in detail in the Corporate Emergency Plan:

Assistant to Emergency Response Manager. Upon activation, this position assists the Emergency Response Manager in preparing status reports and coordinating the activities of the EOF staff organization.

Radiological Control Manager. Upon activation, this position is responsible primarily for off-site dose assessment and environmental monitoring, for making recommendations to the ERM on necessary off-site protective actions, for communicating radiological information to the CEOC, and for coordinating and comparing dose-assessment and monitoring results with the State (Department of Human Resources at SERT).

Technical Analysis Manager. Upon activation, this position is responsible for collecting technical information on plant conditions, for providing a technical assessment of the emergency, providing appraisals of the status of the Plant, providing back-up technical support to the TSC, and for communicating this technical information on the plant condition to CEOC, to the State, and to Federal agencies.

Administrative and Logistics Manager. Upon activation, this position is responsible for providing administrative, logistic, communications and personnel support to the ERM and the Plant as required for emergency operations.

Site Public Information Coordinator. Described in Section 2.4.8, he reports to the Emergency Response Manager when the EOF is activated.

Emergency Communicator. Upon activation, this position and his staff make calls, using messages prepared by the EOF staff, to organ1zatfons and State and Local government agencies for the purposes of notifying them of emergency classes and conditions at the plant in accordance with Plant Emergency Procedures (PEPs).

3.5.2 Functions

a. Command center for Emergency Response Manager and his staff
b. Upon activation, performs off-site notification, environmental monitoring, and dose projection (Relieves TSC of these functions)
c. Emergency communications systems monitoring and control
d. Provides technical analysis and support
e. Receives and displays plant status and parameters data on ERFIS
f. Serves as the Recovery Center during recovery operations

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PLP-201 Emergency Plan, Rev 67 2.4.4 Emergency Operations Facility A. Emergency Response Manager: The Emergency Response Manager, located in the Emergency Operations Facility, is responsible for overall command and control of the HNP response to the emergency. The Emergency Response Manager is also responsible for providing guidance to the Technical Analysis Manager, Radiological Control Manager, Communications Manager, and the Admin and Logistics Manager.

Upon activation of the Emergency Operations Facility the Emergency Response Manager relieves the Site Emergency Coordinator-MCR of the following major responsibilities:

1) Approval of required notifications to the State/Counties.
2) Approval of planned radiation exposures for off-site HNP personnel in excess of 5 Rem TEDE or entry into radiation fields greater than 25 Rem/hr.
3) Approval of the administration of Potassium Iodide to off-site HNP emergency workers.
4) Approval of Protective Action Recommendations.
5) Direct interface with offsite authorities.
6) Coordination of Dose Projection and Environmental Monitoring activities.
7) A trained SAMG decision maker whose focus is on the offsite consequences of the strategy recommended by the TSC. The ERM has the ultimate approval authority for strategy implementation.

B. EOF-Senior Reactor Operator: The EOF-Senior Reactor Operator is located in the Emergency Operations Facility and reports to the Emergency Response Manager. The EOF-Senior Reactor Operator is responsible for providing technical information and assistance related to plant conditions and operations.

C. EOF ERFIS Operator: The EOF ERFIS Operator reports to the EOF Senior Reactor Operator and is located in the Emergency Operations Facility. The position is responsible for providing/displaying any information from ERFIS requested by Emergency Operations Facility personnel.

D. Emergency Preparedness Advisor: The Emergency Preparedness Advisor, located in the Emergency Operations Facility, reports to the Emergency Response Manager in the EOF and advises the Emergency Response Manager and other Emergency Response Organization personnel on implementation of the Emergency Plan and implementing procedures.

E. News Coordinator: The News Coordinator, located in the Emergency Operations Facility, reports to the Emergency Response Manager. The News Coordinator has the responsibility for preparing and coordinating the approval of news releases.

F. Administrative and Logistics Manager: The Administrative and Logistics Manager, located in the Emergency Operations Facility, reports to the Emergency Response Manager and is responsible for direction of activities of the Administrative Team Leader and Admin Building Assembly Area Leader.

G. EOF Telecomm/Computer Support: EOF Telecommunications/Computer Support personnel are located in the EOF and report to the Administrative and Logistics Manager. They are responsible for providing technical assistance required in the areas of telecommunications or computer support.

H. Admin Team Leader: The Admin Team Leader, located in the Emergency Operations Facility, reports to the Administrative and Logistics Manager and is responsible for directing the actions of the Admin Team.

I. Admin Team: The Admin Team, located in the Emergency Operations Facility, consists of a Setup Leader, Librarian and Admin Support personnel. They report to the Admin Team Leader and are responsible for providing any documents, prints or other clerical services as requested by personnel in the Emergency Operations Facility.

J. EOF Logkeeper: The EOF Logkeeper is located in the Emergency Operations Facility and reports to the Admin Team Leader. The EOF Logkeeper is responsible for recording the major activities that occur in the Emergency Operations Facility during an emergency.

K. Assembly Area Leader: The Assembly Area Leader is responsible to the Admin and Logistics Manager, or prior to activation of this position, the Site Emergency Coordinator, for coordinating the activities in the Admin Building Assembly Area.

L. Technical Analysis Manager: The Technical Analysis Manager reports to the Emergency Response Manager and is responsible for direction of activities of the Emergency Operations Facility Accident Assessment Team.

M. EOF Accident Assessment Team: The EOF Assessment Team reports to the Technical Analysis Manager and is located in the Emergency Operations Facility. The team is composed of a Civil Engineer, Electrical Engineer, I&C

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Engineer, and Mechanical Engineer. They are responsible for providing recommendations to the Technical Analysis Manager on problems as assigned.

N. Radiological Control Manager: The Radiological Control Manager, located in the Emergency Operations Facility, reports to the Emergency Response Manager. The Radiological Control Manager is responsible for providing direction to the Dose Projection Team Leader, Technical Advisor and the EOF Health Physics Technician. The Radiological Control Manager is also responsible for:

1) Providing direction to offsite health physics emergency response actions.
2) Ensuring that the Emergency Response Manager and other Managers in the EOF are kept informed of radiological/chemical conditions on and off site.

O. EOF HP Technician: The EOF HP Technician, normally located in the Emergency Operations Facility, reports to the Radiological Control Manager and is responsible for providing radiological support and monitoring activities within the EOF.

P. Technical Advisor: The Technical Advisor, located in the Emergency Operations Facility, reports to the Radiological Control Manager. The Technical Advisor assists the Radiological Control Manager and staffs the HPN Line when requested by the NRC.

Q. Dose Projection Team Leader: The Dose Projection Team Leader, located in the Emergency Operations Facility, reports to the Radiological Control Manager. The Dose Projection Team Leader provides guidance to the Environmental Field Coordinator and the Dose Projection Team.

R. Dose Projection Team: The Dose Projection Team reports to the Dose Projection Team Leader and is located in the Emergency Operations Facility. The Dose Projection Team is responsible for performing source term and offsite dose calculations.

S. Environmental Field Coordinator: The Environmental Field Coordinator, located in the Emergency Operations Facility, is responsible to the Dose Projection Team Leader. The Environmental Field Coordinator is responsible for providing direction to the Environmental Monitoring Teams.

T. Environmental Monitoring Teams: Environmental Monitoring Teams report to the Environmental Field Coordinator after activation of the Emergency Operations Facility, or, prior to activation of the Emergency Operations Facility, to the Site Emergency Coordinator -MCR. Teams assemble at HE&EC and are subsequently dispatched in vehicles to the surrounding area. They are responsible for offsite plume tracking, monitoring and other sampling activities.

U. Communications Manager: The Communications Manager, located in the Emergency Operations Facility, reports to the Emergency Response Manager. The Communications Manager is responsible for ensuring notification and communication to offsite authorities and providing direction to the Emergency Communicator-State/County and the Representatives to the State and County EOCs.

V. Emergency Communicator-State/Counties: The Emergency Communicator-State/Counties, located in the Emergency Operations Facility, reports to the Communications Manager. The Emergency Communicator-State/Counties is responsible for conducting timely notification and transfer of emergency information to the State and Counties.

W. Emergency Communicator-Corporate Comm/JIC: The Emergency Communicator-Corporate Comm/JIC, located in the Emergency Operations Facility, reports to the Communications Manager. The Emergency Communicator-Corporate Comm/JIC is responsible for providing information to support public information emergency response activities.

X. Representatives to the State/County EOCs: The Representatives to the State/County EOCs are located at the following:

N.C. State EOC Joint Force Headquarters (JFHQ) building, 1636 Gold Star Drive, Raleigh North Carolina and is the principle Emergency Operations Center.

Wake County EOC Wake County Courthouse, Raleigh, N.C.

Chatham County EOC Emergency Operations Center, Pittsboro, N.C.

Harnett County EOC Emergency Operations Center, Lillington, N.C.

Lee County EOC Lee County Courthouse, Sanford, N.C.

Chatham County Alternate EOC 3760 Alston Bridge Rd., Siler City, NC Harnett County Alternate EOC 126 Alexander Dr., Lillington, NC Lee County Alternate EOC, 225 E. Weatherspoon, Sanford, NC

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These representatives act as technical liaisons to facilitate communications and the coordination of information flow between the Site Emergency Coordinator or Emergency Response Manager and State/local authorities. They report to the Communications Manager in the Emergency Operations Facility.

Planning Standard 7 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.7 Public Information (applicable sections)

Standard Information is made available to the public on a periodic basis on how it will be notified and what initial actions should be taken in an emergency; the principal points of contact with the news media for dissemination of information during an emergency (including physical location or locations) are established in advance; and procedures for coordinated dissemination of information to the public are established.

Evaluation The applicant will conduct a public information program for persons living in the plume exposure Emergency Planning Zone. The program will be accomplished by (1) yearly dissemination of brochures containing educational information on emergency preparedness, nuclear power, and radiation, and how to contact CP&L more information; (2) establishment of an emergency preparedness speakers bureau to allow qualified plant personnel to address civic, religious, social, and occupational organizations in the plant vicinity; and (3) preparation of news material for TV, radio, and the press and the general public. The applicant is working with both state and local governments to ensure that all public education efforts will be consistent and complementary.

PLP-201 Emergency Plan, Rev. 3 3.6 Plant Media Center (PMC) 3.6.1 Characteristics

a. Located at the Civic Center and Memorial Auditorium in Raleigh, NC.

3.6.2 Functions

a. Provides controlled point of contact and physical location near plant for use by news media
b. Activities directed by Site Public Information Coordinator
c. Provide immediate access to accurate emergency related information generated by all involved agencies by media representatives
d. Coordinates information releases to the press as described in the Corporate Emergency Plan 3.6.3 Emergency Equipment and Supplies
a. Provided with additional telephones for media use
b. Provide equipment for document reproduction, telecopying, communications, and television electrical connections PLP-201 Emergency Plan, Rev 67 Section 3.6 Joint Information Center A. Located at the Duke Energy Customer Service Center in Raleigh, North Carolina, approximately 21 miles from the plant.

B. Serves as the primary location for accumulating accurate and current information regarding the emergency conditions and writing non-technical news releases.

C. Provides work space and phones for public information personnel from the state, counties, NRC, FEMA, and industry-related organizations.

D. Provides responses to media inquiries through media communicators who staff telephones that the media can

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call for information about an emergency.

E. Implements provisions for rumor control by providing a number of telephones which members of the public, who hear rumors, can call for factual information.

Section 5.2.5 Public Education and Information - HNP (Applicable excerpts)

During an actual emergency, provisions will be established through the Joint Information Center to make available and distribute information to the news media. Provisions for a number of telephones which members of the public, who hear rumors, can call for factual information will also be implemented in the JIC when activated.

Planning Standard 9 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.9 Accident Assessment Standard Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency are in use.

Evaluation The plan identifies the four emergency classes and discusses basic tests or criteria that must be considered in classifying the emergency (such as, radioactivity release, core damage, plant degradation).

The classification of the events is implemented through EALs, which are specific sets of plant conditions, instrument readings, and events coinciding with the initiating conditions associated with one of the emergency classes. The EALs are outlined in Figure 4.1-1, and will be discussed in detail in the plant emergency procedures, including specific instrument readings, plant system and effluent parameters, and equipment status indications corresponding to the initiating conditions of each emergency class.

The plan provides the onsite capability and resources to provide initial values and continuing assessment for the duration of an emergency such as the postaccident sampling system (PASS) and radiation monitoring systems.

The details of these systems--such as types, ranges, and location of monitors--and the PASS are discussed in appropriate sections of the FSAR.

Annex B of the plan describes the technical basis of the dose projection program, including calculation of source terms, dose conversion factors, atmospheric dispersion, and assumptions and limitations. The methodology and techniques for determining source terms and dose assessments will be detailed in plant emergency procedure 361.

Meteorological data from the onsite station is presented to the control room, the TSC, and the EOF via computer.

In case of off-scale or inoperable instrumentation, the cross reference in Annex B refers to PEP 361. There is no discussion of this contingency in the plan. The plan provides for environmental monitoring teams that will be activated in accordance with appropriate PEPS, equipped with company vehicles and sampling equipment, and capable of tracking the plume, obtaining and analyzing air samples, and sampling liquid effluents. The field monitoring equipment has the capability of measuring radioiodine in the vicinity of the plant site as low as 5x10-8 uCi/cc.

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PLP-201 Emergency Plan, Rev. 3 4.4.4 Environmental Monitoring

a. Activation of Environmental Monitoring Teams will be in accordance with plant emergency procedures (PEP).
b. Environmental sampling and monitoring points are specified in Plant Emergency procedures.
c. At least two Environmental Monitoring Teams will initially be activated upon activation of the TSC. Additional teams from the Shearon Harris Energy & Environmental Center can be called upon for support as needed.
d. The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments, and by obtaining and analyzing air samples.
e. The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents, such as the cooling tower blowdown.
f. Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency to ensure that a cumulative dose record is obtained.

PLP-201 Emergency Plan, Rev 67 4.4.4 Environmental Monitoring A. Environmental sampling and monitoring points are specified in environmental monitoring procedures.

B. Environmental Monitoring Teams will be activated in accordance with Table 2.2-1 and the appropriate implementing procedures. Additional teams can be called upon for support as needed.

C. The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments and by obtaining and analyzing air samples.

D. The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents, such as the cooling tower blowdown.

E. Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency to ensure that a cumulative dose record is obtained.

Planning Standard 10 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.10 Protective Response Standard A range of protective actions have been developed for the plume exposure pathway emergency planning zone for emergency workers and the public. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway emergency planning zone appropriate to the locale have been developed.

Evaluation The plan establishes the means and times to alert and notify onsite personnel of an emergency, and identifies the assembly areas adjacent to each of the gate houses. Personnel will be monitored for contamination at the assembly area. If it is necessary to evacuate further, evacuation routes and means of transportation are identified.

Holding areas for additional decontamination will be identified if necessary. Supervisors will account for all persons evacuated from within the protected area at the assembly area and report missing persons to appropriate supervision within 30 minutes. Security search procedures will be implemented to locate missing persons. The plan provides individual respiratory protection, protective clothing, and physician-supervised radioprotective drugs for the emergency workers.

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PLP-201 Emergency Plan, Rev. 3 4.6.1 On-Site Alerting, Warning, and Notification The Plant Public Address (PA) System will be used to alert and notify on-site personnel of an emergency condition with 15 minutes. This includes the Protected Area, any construction areas, the parking lots, the cooling tower area, intake structure, cement plant and construction lay down areas. Security personnel with portable loudspeakers may be used to augment the PA system and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify personnel of those actions which should be taken.

The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this Plan.

4.6.3.1 Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. CP&L radiation and contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.4 of this plan. The radiation control facilities located in the Waste Processing Building (on the 261' and 286' level) include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area and radiation Control area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (en the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level}. Additional personnel decontamination areas are located at radiation control areas at the north end of the Reactor Auxiliary Building (on the 261' level) and in the Turbine Building (on the 261' level). Radiation control and procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located near the first aid room in the Administration Building and at the SHE&E Center. Radiologically controlled areas can expanded by roping off areas and/or establishing access control points to maintain personnel exposure to As Low As Reasonably Achievable (ALARA) guidelines.

4.6.3.3 Use of Protective Equipment and Supplies During the course of ar. emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiologically Controlled Area. Measures that will be considered are:

  • Distribution of respirators;
  • Use of protective clothing; and
  • Use of thyroid blocking agents (Potassium Iodide).

The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures.

Under the direction of a qualified Physician, administration of potassium iodide (KI), a radioprotective drug, to emergency response personnel may also be employed to mitigate the consequences of inhalation of radioiodines.

Procedures for the administration of radioprotective drugs to employees are described in the plant emergency procedures.

PLP-201 Emergency Plan, Rev 67 4.6.1 On-Site Alerting, Warning, and Notification The Plant Public-Address (PA) System will be used to alert and notify on-site personnel of an emergency condition within 15 minutes. Security personnel with portable loudspeakers may be used to augment the PA system and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify

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personnel of those actions which should be taken. The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this Plan.

4.6.3 Radiological Exposure Control A. Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. HNP contamination control limits are shown in Table 4.6-1.

Emergency exposure guidance is given in Section 4.6.3.D of this plan. The radiation control facilities located in the Waste Processing Building include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level). Radiation control and radiation control procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located in the Turbine Building and at the Harris Energy & Environmental Center. Radiation Control Areas can be expanded by roping off areas and/or establishing access control points to maintain personnel exposure As Low As Reasonably Achievable (ALARA).

B. Exposure Records for Emergency Workers Emergency workers will receive self reading pocket dosimeters (SRPDs) or equivalent and TLD badges. Dose records will be maintained by the Radiological Control Coordinator in accordance with PEP-330. TLDs are read at McGuire Island. They are capable of staffing 24-hour a day.

C. Use of Protective Equipment and Supplies During the course of an emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiation Control Area. Measures that will be considered are:

  • Use of process or engineering controls.
  • Distribution of respirators.
  • Use of protective clothing.
  • Use of thyroid blocking agents (Potassium Iodide).

The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures.

Procedures for the administration of radioprotective drugs to employees are described in the plant emergency procedures.

RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that

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supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.

c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this procedure revision were made to reflect the changes for the EOF relocation to Charlotte and the changes made for Standard ERO. PEP-270 Activation and Operation of the Emergency Operations Facility is being superseded by AD-EP-ALL-0103, Emergency Operations Facility (EOF) Activation.

Commitments identified in PEP-270 have been relocated to AD-EP-ALL-0103. HNP continues to maintain the capability to staff facilities, have specific responsibilities assigned to personnel, provide updates to the public on events occurring during an emergency, and provide protective actions onsite and to the public as needed during an emergency. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2

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Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(1), Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

b. Plant staff emergency assignments 10 CFR 50.47(b)(2), Onsite Emergency Organization On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

2. A description of the onsite emergency response organization (ERO) with a detailed discussion of:
a. Authorities, responsibilities, and duties of the individual(s) who will take charge during an emergency;
b. Plant staff emergency assignments;
c. Authorities, responsibilities, and duties of an onsite emergency coordinator who shall be in charge of the exchange of information with offsite authorities responsible for coordinating and implementing offsite emergency measures.

10 CFR 50.47(b)(7)Emergency Public Information The regulation at 10 CFR 50.47(b)(7) states the following:

Information is made available to the public on a periodic basis on how they will be notified and what their initial actions should be in an emergency (e.g., listening to a local broadcast station and remaining indoors), the principal points of contact with the news media for dissemination of information during an emergency (including the physical location or locations) are established in advance, and procedures for coordinated dissemination of information to the public are established.

Two emergency planning functions have been defined for this planning standard:

(1) Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway emergency planning zone (EPZ).

(2) Coordinated dissemination of public information during emergencies is established. (applicable) 10 CFR 50, Appendix E, Section IV. D. Notification Procedures (applicable excerpts only)

1. Administrative and physical means for notifying local, State, and Federal officials and agencies and agreements reached with these officials and agencies for the prompt notification of the public and for public evacuation or other protective measures, should they become necessary, shall be described. This description shall include

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identification of the appropriate officials, by title and agency, of the State and local government agencies within the EPZs.

2. Provisions shall be described for yearly dissemination to the public within the plume exposure pathway EPZ of basic emergency planning information, such as the methods and times required for public notification and the protective actions planned if an accident occurs, general information as to the nature and effects of radiation, and a listing of local broadcast stations that will be used for dissemination of information during an emergency. Signs or other measures shall also be used to disseminate to any transient population within the plume exposure pathway EPZ appropriate information that would be helpful if an accident occurs.

10 CFR 50.47(b)(9), Emergency Assessment Capability Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

10 CFR Part 50, Appendix E Section IV.E, Emergency Facilities and Equipment Adequate provisions shall be made and described for emergency facilities and equipment, including:

2. Equipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment; 10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

10 CFR Part 50, Appendix E does not contain any supporting requirements.

Evaluation Duke Energy nuclear stations will continue to have the capability to activate and perform the functions of an EOF.

The changes described maintains compliance with the applicable sections of 10CFR50.47(b) and 10CFR50 Appendix E.

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Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR 50.47(b)(1) Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Function Two emergency planning functions have been defined for this planning standard:

(1) Responsibility for emergency response is assigned.

(2) The response organization has the staff to respond and to augment staff on a continuing basis (i.e., 24/7 support) in accordance with the emergency plan.

Element NUREG 0654 II. Section A.

Primary responsibilities for emergency response by the nuclear facility licensee, and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

NUREG 0654 II. Section J.

7. Each licensee shall establish a mechanism for recommending protective actions to the appropriate State and local authorities. These shall include Emergency Action Levels corresponding to projected dose to the population-at-risk, in accordance with Appendix 1 and with the recommendations set forth in Tables 2.1 and 2.2 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-520/1-75-001). As specified in Appendix 1, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone.

Standard 10 CFR 50.47(b)(2), Onsite Emergency Organization On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response capabilities is available and the interfaces among various onsite response activities and offsite support and response activities are specified.

Function The process for timely augmentation of onshift staff is established and maintained.

Element NUREG 0654 II. Section B.

5. Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table B-1 entitled, "Minimum Staffing Requirements for Nuclear Power Plant Emergencies." The minimum on-shift staffing levels shall be as indicated in Table B-1. The licensee must be able to

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augment on-shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table B-1. The implementation schedule for licensed operators, auxiliary operators and the shift technical advisor on shift shall be as specified in the July 31, 1980 letter to all power reactor licensees. Any deficiencies in the other staffing requirements of Table B-1 must be capable of augmentation within 30 minutes by September 1, 1981, and such deficiencies must be fully removed by July 1, 1982.

6. Each licensee shall specify the interfaces between and among the onsite functional areas of emergency activity, licensee headquarters support, local services support, and State and local government response organization. This shall be illustrated in a block diagram and shall include the onsite technical support center and the operational support (assembly) center and the licensee's near-site Emergency Operations Facility (EOF)
7. Each licensee shall specify the corporate management, administrative, and technical support personnel who will augment the plant staff as specified in the table entitled "Minimum Staffing Requirements for Nuclear Power Plant Emergencies," (Table B-1) and in the following areas:

Standard 10 CFR 50.47(b)(7)Emergency Public Information

a. The regulation at 10 CFR 50.47(b)(7) states the following:

Information is made available to the public on a periodic basis on how they will be notified and what their initial actions should be in an emergency (e.g., listening to a local broadcast station and remaining indoors), the principal points of contact with the news media for dissemination of information during an emergency (including the physical location or locations) are established in advance, and procedures for coordinated dissemination of information to the public are established.

Function

b. Two emergency planning functions have been defined for this planning standard:

(1) Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway emergency planning zone (EPZ).

(2) Coordinated dissemination of public information during emergencies is established. (applicable)

Element NUREG-0654/FEMA-REP-1 Rev 1, II, G. Public Education and Evaluation Evaluation Criteria (applicable excerpts only) 3.a Each principal organization shall designate the points of contact and physical locations for use by news media during an emergency.

3.b Each licensee shall provide space which may be used for a limited number of the news media at the near-site Emergency Operations Facility.

4.a Each principal organization shall designate a spokesperson who should have access to all necessary information.

4.b Each organization shall establish arrangements for timely exchange of information among designated spokespersons.

4.c Each organization shall establish coordinated arrangements for dealing with rumors.

Standard 10 CFR 50.47(b)(9), Emergency Assessment Capability Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

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Function Methods, systems, and equipment for assessment of radioactive releases are in use.

Element NUREG 0654 II.Section I

3. Each licensee shall establish methods and techniques to be used for determining: the source term of releases of radioactive material within plant systems. An example is the relationship between the containment radiation monitor(s) reading(s) and radioactive material available for release from containment.

the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors.

6. Each organization shall describe the capability and resources for field monitoring within the plume exposure Emergency Planning Zone which are an intrinsic part of the concept of operations for the facility.

Standard 10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

Function A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

Element NUREG 0654 II.J.1-8 (Excerpts only)

1. Each licensee shall establish the means and time required to warn or advise onsite individuals and individuals who may be in areas controlled by the operator, including:

Employees not having emergency assignments; Visitors; Contractor and construction personnel; and Other persons who may be in the public access areas on or passing through the site or within the owner controlled area.

2. Each licensee shall make provisions for evacuation routes and transportation for onsite individuals to some suitable offsite location, including alternatives for inclement weather, high traffic density and specific radiological conditions.
3. Each licensee shall provide for radiological monitoring of people evacuated from the site.

4 Each licensee shall provide for the evacuation of onsite non-essential personnel in the event of a Site or General Emergency and shall provide a decontamination capability at or near the monitoring point specified in J.3.

6. Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for:

Individual respiratory protection; Use of protective clothing; and Use of radioprotective drugs, (e.g., individual thyroid protection).

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Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Functions The following functions were identified in the performance of this evaluation:

Responsibility for emergency response is assigned.

The response organization has the staff to respond and to augment staff on a continuing basis (i.e., 24/7 support) in accordance with the emergency plan.

The process for timely augmentation of onshift staff is established and maintained.

Coordinated dissemination of public information during emergencies is established.

Methods, systems, and equipment for assessment of radioactive releases are in use.

A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

The adoption of the standard augmenting ERO will continue to maintain or improve the capability and timeliness of the HNP augmenting ERO to respond to an event and effectively perform their assigned tasks. HNP continues to maintain the capability to protect the onsite staff and responding organizations during an emergency. HNP continues to maintain the capability to release news of the event to the public to keep them informed and aware of conditions and events during an emergency.

The changes described do not affect the emergency planning functions listed in Part IV associated with 10 CFR 50.47(b) because the changes ensure adequate personnel, as well as adequate processes to support and mitigate a emergency event. The changes do not affect supporting requirements described in 10 CFR 50, Appendix E.IV.

The changes continue to ensure that adequate provisions shall be made and described for emergency facilities and equipment and the changes continue to ensure the organization for coping with radiological emergencies is described.

The changes described provide additional assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure the protection of the onsite emergency staff
  • effectively use response equipment and emergency response procedures to evaluate conditions and protect the staff.
  • effectively alert the public of conditions and events at the site during an emergency.

These changes support the HNP Emergency Plan, by ensuring that procedures used during response to a classified emergency are available. Effective use of these procedures helps ensure emergency response functions as described in the Emergency Plan are adequately maintained and demonstrated. The functions identified in this procedure were relocated to applicable fleet procedures to standardize ERO task and functions across the Duke Energy Fleet.

The changes described maintain the functions as described in the HNP Emergency Plan, as written and approved; and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

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Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 11/29/17 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 11/29/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Jamey Sharlow signed electronically in CAS 11/29/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:______2163299______________ CNS CR3 HNP MNS 5AD #:______2163294_____________ ONS RNP GO Document and Revision PEP-330 rev 13 - Superseded Radiological Consequences Part I. Description of Proposed Change:

Procedure is being superseded by the following site and fleet procedures in support of the Common ERO implementation:

Planning Standard 1 applies to all changes:

  • AD-EP-ALL-0205, Emergency Exposure Controls (Planning Standard 11)
  • AD-RP-ALL-2000, Preparation and Management of Radiation Work Permits (Planning Standard 11)
  • AD-EP-HNP-0106, HNP Site Specific OSC Support (Planning Standard 10, 11)
  • AD-EP-ALL-0204, Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (Planning Standard 10)
  • AD-EP-HNP-0203, HNP Site-Specific Field Monitoring (Planning Standard 9)
  • AD-RP-ALL-4000, Internal Dose Assessment (Planning Standard 11)

There were no commitments included in this procedure. , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

Planning Standard 1 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.1 Assignment of Responsibility (Organization Control)

Standard Primary responsibilities for emergency response by the nuclear facility licensee and by state and local organizations within the emergency planning zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

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Evaluation The plan identifies the specific individual and his successors who shall be in charge of the emergency response.

PLP-201 Emergency Plan, Rev. 3 2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 General The plant emergency organization is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest number of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time PLP-201 Emergency Plan, Rev 67 2.0 ORGANIZATION AND RESPONSIBILITIES 2.2 Emergency Organization (Excerpts only)

The plant Emergency Response Organization (ERO) is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest numbers of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time Planning Standard 9 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.9 Accident Assessment Standard Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency are in use.

Evaluation The plan identifies the four emergency classes and discusses basic tests or criteria that must be considered in classifying the emergency (such as, radioactivity release, core damage, plant degradation).

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The classification of the events is implemented through EALs, which are specific sets of plant conditions, instrument readings, and events coinciding with the initiating conditions associated with one of the emergency classes. The EALs are outlined in Figure 4.1-1, and will be discussed in detail in the plant emergency procedures, including specific instrument readings, plant system and effluent parameters, and equipment status indications corresponding to the initiating conditions of each emergency class.

The plan provides the onsite capability and resources to provide initial values and continuing assessment for the duration of an emergency such as the post-accident sampling system (PASS) and radiation monitoring systems.

The details of these systems--such as types, ranges, and location of monitors--and the PASS are discussed in appropriate sections of the FSAR.

Annex B of the plan describes the technical basis of the dose projection program, including calculation of source terms, dose conversion factors, atmospheric dispersion, and assumptions and limitations. The methodology and techniques for determining source terms and dose assessments will be detailed in plant emergency procedure 361.

Meteorological data from the onsite station is presented to the control room, the TSC, and the EOF via computer.

In case of off-scale or inoperable instrumentation, the cross reference in Annex B refers to PEP 361. There is no discussion of this contingency in the plan. The plan provides for environmental monitoring teams that will be activated in accordance with appropriate PEPS, equipped with company vehicles and sampling equipment, and capable of tracking the plume, obtaining and analyzing air samples, and sampling liquid effluents. The field monitoring equipment has the capability of measuring radioiodine in the vicinity of the plant site as low as 5x10-8 uCi/cc.

PLP-201 Emergency Plan, Rev. 3 4.4.4 Environmental Monitoring

a. Activation of Environmental Monitoring Teams will be in accordance with plant emergency procedures (PEP).
b. Environmental sampling and monitoring points are specified in Plant Emergency procedures.
c. At least two Environmental Monitoring Teams will initially be activated upon activation of the TSC. Additional teams from the Shearon Harris Energy & Environmental Center can be called upon for support as needed.
d. The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments, and by obtaining and analyzing air samples.
e. The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents, such as the cooling tower blowdown.
f. Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency to ensure that a cumulative dose record is obtained.

PLP-201 Emergency Plan, Rev 67 4.4.4 Environmental Monitoring A. Environmental sampling and monitoring points are specified in environmental monitoring procedures.

B. Environmental Monitoring Teams will be activated in accordance with Table 2.2-1 and the appropriate implementing procedures. Additional teams can be called upon for support as needed.

C. The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments and by obtaining and analyzing air samples.

D. The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents,

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such as the cooling tower blowdown.

E. Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency to ensure that a cumulative dose record is obtained.

Planning Standard 10 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.10 Protective Response Standard A range of protective actions have been developed for the plume exposure pathway emergency planning zone for emergency workers and the public. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway emergency planning zone appropriate to the locale have been developed.

Evaluation The plan establishes the means and times to alert and notify onsite personnel of an emergency, and identifies the assembly areas adjacent to each of the gate houses. Personnel will be monitored for contamination at the assembly area. If it is necessary to evacuate further, evacuation routes and means of transportation are identified.

Holding areas for additional decontamination will be identified if necessary. Supervisors will account for all persons evacuated from within the protected area at the assembly area and report missing persons to appropriate supervision within 30 minutes. Security search procedures will be implemented to locate missing persons. The plan provides individual respiratory protection, protective clothing, and physician-supervised radioprotective drugs for the emergency workers.

PLP-201 Emergency Plan, Rev. 3 4.6.1 On-Site Alerting, Warning, and Notification The Plant Public Address (PA) System will be used to alert and notify on-site personnel of an emergency condition with 15 minutes. This includes the Protected Area, any construction areas, the parking lots, the cooling tower area, intake structure, cement plant and construction lay down areas. Security personnel with portable loudspeakers may be used to augment the PA system and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify personnel of those actions which should be taken.

The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this Plan.

4.6.3.1 Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. CP&L radiation and contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.4 of this plan. The radiation control facilities located in the Waste Processing Building (on the 261' and 286' level) include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area and radiation Control area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (en the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level}. Additional personnel decontamination areas are located at radiation control areas at the north end of the Reactor Auxiliary Building

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(on the 261' level) and in the Turbine Building (on the 261' level). Radiation control and procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located near the first aid room in the Administration Building and at the SHE&E Center. Radiologically controlled areas can expanded by roping off areas and/or establishing access control points to maintain personnel exposure to As Low As Reasonably Achievable (ALARA) guidelines.

4.6.3.3 Use of Protective Equipment and Supplies During the course of ar. emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiologically Controlled Area. Measures that will be considered are:

  • Distribution of respirators;
  • Use of protective clothing; and
  • Use of thyroid blocking agents (Potassium Iodide).

The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures.

Under the direction of a qualified Physician, administration of potassium iodide (KI), a radioprotective drug, to emergency response personnel may also be employed to mitigate the consequences of inhalation of radioiodines.

Procedures for the administration of radioprotective drugs to employees are described in the plant emergency procedures.

PLP-201 Emergency Plan, Rev 67 4.6.1 On-Site Alerting, Warning, and Notification The Plant Public-Address (PA) System will be used to alert and notify on-site personnel of an emergency condition within 15 minutes. Security personnel with portable loudspeakers may be used to augment the PA system and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify personnel of those actions which should be taken. The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this Plan.

4.6.3 Radiological Exposure Control A. Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. HNP contamination control limits are shown in Table 4.6-1.

Emergency exposure guidance is given in Section 4.6.3.D of this plan. The radiation control facilities located in the Waste Processing Building include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level). Radiation control and radiation control procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located in the Turbine Building and at the Harris Energy & Environmental Center. Radiation Control Areas can be expanded by roping off areas and/or establishing access control points to maintain personnel exposure As Low As Reasonably Achievable (ALARA).

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B. Exposure Records for Emergency Workers Emergency workers will receive self reading pocket dosimeters (SRPDs) or equivalent and TLD badges. Dose records will be maintained by the Radiological Control Coordinator in accordance with PEP-330. TLDs are read at McGuire Island. They are capable of staffing 24-hour a day.

C. Use of Protective Equipment and Supplies During the course of an emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiation Control Area. Measures that will be considered are:

  • Use of process or engineering controls.
  • Distribution of respirators.
  • Use of protective clothing.
  • Use of thyroid blocking agents (Potassium Iodide).

The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures.

Procedures for the administration of radioprotective drugs to employees are described in the plant emergency procedures.

Planning Standard 11 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.11 Radiological Exposure Control Standard Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Workers and lifesaving Activity Protective Action Guides.

Evaluation The plan provides for a radiation protection program for controlling radiological exposures in the event of an emergency. Emergency exposure guidelines, consistent with EPA Emergency Workers and Lifesaving Activity Protective Action Guides are specified for several categories of emergency workers. The plan specifies that the Plant General Manager or the Radiological Control Director may authorize emergency exposures in excess of 10 CFR 20 limits. In their absence, the Site Emergency Coordinator may grant such approval. The plan provides for 24-hour-a-day radiation safety controls to contain the spread of loose contamination and to monitor personnel exposure. Dose records will be maintained automatically utilizing the computerized Radiological Information Management System (RIMS).

Action levels for determining the need for decontamination are summarized in Table 4.6-l of the plan from the Plant Operations Manual Procedure ERC-101. The applicant will establish the means for radiological decontamination of emergency personnel wounds, supplies, instruments, and equipment, and for waste disposal in Plant Emergency Procedure 393.

PLP-201 Emergency Plan, Rev 3 4.6.3.1 Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. CP&L radiation and contamination control limits are shown in

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Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.4 of this plan. The radiation control facilities located in the Waste Processing Building (on the 261' and 286' level) include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area and radiation Control area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (en the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level}. Additional personnel decontamination areas are located at radiation control areas at the north end of the Reactor Auxiliary Building (on the 261' level) and in the Turbine Building (on the 261' level). Radiation control and procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located near the first aid room in the Administration Building and at the SHE&E Center. Radiologically controlled areas can expanded by roping off areas and/or establishing access control points to maintain personnel exposure to As Low As Reasonably Achievable (ALARA) guidelines.

PLP-201 Emergency Plan, Rev 67 4.6.3 Radiological Exposure Control A. Radiological and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. HNP contamination control limits are shown in Table 4.6-1.

Emergency exposure guidance is given in Section 4.6.3.D of this plan. The radiation control facilities located in the Waste Processing Building include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236' and 261' levels) and at the north end of the Fuel Handling Building (on the 261' level). Radiation control and radiation control procedures are described in Section 12.5 of the FSAR.

Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located in the Turbine Building and at the Harris Energy & Environmental Center. Radiation Control Areas can be expanded by roping off areas and/or establishing access control points to maintain personnel exposure As Low As Reasonably Achievable (ALARA).

RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.

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c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this Evaluation were made to reflect the changes for the EOF relocation to Charlotte and the changes made for Standard ERO. PEP-330 Radiological Consequences is being superseded. All functions performed by this procedure are being moved to fleet procedures. These fleet procedures provide the same capability to perform the tasks across the fleet. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2

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Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(1), Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

b. Plant staff emergency assignments 10 CFR 50.47(b)(9), Emergency Assessment Capability Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

10 CFR Part 50, Appendix E Section IV.E, Emergency Facilities and Equipment Adequate provisions shall be made and described for emergency facilities and equipment, including:

2. Equipment for determining the magnitude of and for continuously assessing the impact of the release of radioactive materials to the environment; 10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

10 CFR Part 50, Appendix E does not contain any supporting requirements.

10 CFR 50.47(b)(11), Emergency Radiological Exposure Control Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides.

10 CFR Part 50, Appendix E Section IV.E. Emergency Facilities and Equipment Adequate provisions shall be made and described for emergency facilities and equipment, including:

1. Equipment at the site for personnel monitoring;
3. Facilities and supplies at the site for decontamination of onsite individuals;

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Evaluation Duke Energy nuclear stations will continue to have adequate methods for assessing the actual or potential offsite consequences of a radiological emergency condition and protect the emergency staff as the accident progresses.

The changes described maintains compliance with the applicable sections of 10 CFR 50.47(b) and 10 CFR50 Appendix E.

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Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR 50.47(b)(1) Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Function Two emergency planning functions have been defined for this planning standard:

(1) Responsibility for emergency response is assigned.

(2) The response organization has the staff to respond and to augment staff on a continuing basis (i.e., 24/7 support) in accordance with the emergency plan.

Element NUREG 0654 II. Section A.

Primary responsibilities for emergency response by the nuclear facility licensee, and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

NUREG 0654 II. Section J.

7. Each licensee shall establish a mechanism for recommending protective actions to the appropriate State and local authorities. These shall include Emergency Action Levels corresponding to projected dose to the population-at-risk, in accordance with Appendix 1 and with the recommendations set forth in Tables 2.1 and 2.2 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-520/1-75-001). As specified in Appendix 1, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone.

Standard 10 CFR 50.47(b)(9), Emergency Assessment Capability Adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Function Methods, systems, and equipment for assessment of radioactive releases are in use.

Elements NUREG 0654 II.Section I

3. Each licensee shall establish methods and techniques to be used for determining: the source term of releases of radioactive material within plant systems. An example is the relationship between the containment radiation monitor(s) reading(s) and radioactive material available for release from containment.

the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors.

6. Each organization shall describe the capability and resources for field monitoring within the plume exposure Emergency Planning Zone which are an intrinsic part of the concept of operations for the facility.

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Standard 10 CFR 50.47(b)(10), Emergency Protective Actions A range of protective actions has been developed for the plume exposure pathway EPZ for emergency workers and the public. In developing this range of actions, consideration has been given to evacuation, sheltering, and, as a supplement to these, the prophylactic use of potassium iodide (KI), as appropriate. Evacuation time estimates have been developed by applicants and licensees. Licensees shall update the evacuation time estimates on a periodic basis. Guidelines for the choice of protective actions during an emergency, consistent with Federal guidance, are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

Function A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

Element NUREG 0654 II.J.1-8 (Excerpts only)

1. Each licensee shall establish the means and time required to warn or advise onsite individuals and individuals who may be in areas controlled by the operator, including:

Employees not having emergency assignments; Visitors; Contractor and construction personnel; and Other persons who may be in the public access areas on or passing through the site or within the owner controlled area.

2. Each licensee shall make provisions for evacuation routes and transportation for onsite individuals to some suitable offsite location, including alternatives for inclement weather, high traffic density and specific radiological conditions.
3. Each licensee shall provide for radiological monitoring of people evacuated from the site.

4 Each licensee shall provide for the evacuation of onsite non-essential personnel in the event of a Site or General Emergency and shall provide a decontamination capability at or near the monitoring point specified in J.3.

6. Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for:

Individual respiratory protection; Use of protective clothing; and Use of radioprotective drugs, (e.g., individual thyroid protection).

Standard 10 CFR 50.47(b)(11), Emergency Radiological Exposure Control Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides.

Function The resources for controlling radiological exposures for emergency workers are established Element NUREG 0654 II.K

2. Each licensee shall provide an onsite radiation protection program to be implemented during emergencies, including methods to implement exposure guidelines. The plan shall identify individual(s), by position or title, who can authorize emergency workers to receive doses in excess of 10 CFR Part 20 limits. Procedures shall be worked out in advance for permitting onsite volunteers to receive radiation exposures in the course of carrying out

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lifesaving and other emergency activities. These procedures shall include expeditious decision making and a reasonable consideration of relative risks.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Functions The following functions were identified in the performance of this evaluation:

Responsibility for emergency response is assigned.

The response organization has the staff to respond and to augment staff on a continuing basis (i.e., 24/7 support) in accordance with the emergency plan.

Methods, systems, and equipment for assessment of radioactive releases are in use.

A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.

The resources for controlling radiological exposures for emergency workers are established The adoption of the standard augmenting ERO will continue to maintain or improve the capability and timeliness of the HNP augmenting ERO to respond to an event and effectively perform their assigned tasks. HNP continues to maintain the capability to protect the onsite staff and responding organizations during an emergency.

The changes described do not affect the emergency planning functions listed in Part IV associated with 10 CFR 50.47(b) because the changes ensure adequate personnel, as well as emergency facilities and equipment to support the emergency response are provided and maintained to protect the emergency worker. The changes do not affect supporting requirements described in 10 CFR 50, Appendix E.IV. The changes continue to ensure that adequate provisions shall be made and described for emergency facilities and equipment and the changes continue to ensure the organization for coping with radiological emergencies is described.

The changes described provide additional assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure the protection of the onsite emergency staff
  • effectively use response equipment and emergency response procedures to evaluate conditions and protect the staff.

These changes support the HNP Emergency Plan, by ensuring that procedures used during response to a classified emergency are available. Effective use of these procedures helps ensure emergency response functions as described in the Emergency Plan are adequately maintained and demonstrated. The functions identified in this procedure were relocated to applicable fleet procedures to standardize ERO task and functions across the Duke Energy Fleet.

The changes described maintain the functions as described in the HNP Emergency Plan, as written and approved; and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

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Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 11/29/17 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 11/29/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Jamey Sharlow signed electronically in CAS 11/29/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD

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Screening and Evaluation Number Applicable Sites BNP EREG #:_____2164144____________ CNS CR3 HNP MNS 5AD #:_____2164141______________ ONS RNP GO Document and Revision PEP-500, REV SUP Recovery Part I. Description of Proposed Change:

This procedure is being superseded by AD-EP-ALL-0110 Recovery The commitment to IER-L4-13-3 Recovery from a Beyond Basis Natural Event, Recommendation 2 is addressed in AD-EP-ALL-0110, Step 5.4.1.j. , 10 CFR 50.54(q) Initiating Condition (IC) and Emergency Action Level (EAL) and EAL Yes Bases Validation and Verification (V&V) Form , is attached (required for IC or EAL change) No Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

Planning Standard 1 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts)

Section 13.3.2.1 Assignment of Responsibility (Organization Control)

Standard Primary responsibilities for emergency response by the nuclear facility licensee and by state and local organizations within the emergency planning zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Evaluation The plan identifies the specific individual and his successors who shall be in charge of the emergency response.

PLP-201 Emergency Plan, Rev. 3 2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 General The plant emergency organization is composed of a broad spectrum of personnel with specialties in operations,

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maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest number of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time PLP-201 Emergency Plan, Rev 67 2.0 ORGANIZATION AND RESPONSIBILITIES 2.2 Emergency Organization (Excerpts only)

The plant Emergency Response Organization (ERO) is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest numbers of personnel with these specialties are available during day shift operations; however, specialists who are needed can be recalled to the site at any time.

The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Minimum staffing requirements for activation of each facility are indicated in Figures 2.2-1 and 2.4-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time.

Planning Standard 13 NUREG 1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant Units 1 and 2 (Applicable Excerpts) 13.3.2.13 Recovery and Reentry Planning and Postaccident Operations Standard General plans for recovery and reentry are developed.

Evaluation The applicant has developed general plans for reentry and recovery, and specifies the criteria to be used in deciding to de-escalate or terminate the emergency condition.

The plan describes the recovery organization including a block diagram, and lists the personnel and alternates by position/title who are designated for the key positions.

The plan states that notification of onsite -and offsite organizations of the activation of the recovery organization will be initiated by the Emergency Response Manager and will follow plant emergency notification procedures. The plan includes provisions for updating the total population exposure in cooperation with the North Carolina Radiation Protection Section (RPS), Department of ,Human Resources, who is the lead state agency in the collection and analysis of media monitoring. The RPS will be assisted by personnel from Shearon Harris and SHEEC.

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PLP-201 Emergency Plan, Rev 3 6.0 Recovery 6.1 General The overall goals of the recovery effort are to assess the in-plant consequences of the emergency and perform cleanup and repair operations. This effort includes marshaling of the Corporate resources and interfacing with outside agencies. All recovery actions will be preplanned in order to minimize radiation exposure or other hazards to recovery personnel.

The recovery organization may begin to develop plans for recovery of the facility while the emergency is still in progress. However, these efforts will not be permitted to interfere with or detract from the efforts to control the emergency situation. During the emergency phases of the incident, the recovery organization resources will be available to assist and provide support for the Site Emergency Coordinator.

6.2 Recovery Organization The recovery organization consists of the Recovery Manager, managers of support functions who are responsible to the Recovery Manager, and supporting personnel. This organization may be modified during the recovery process to better respond to the conditions at the plant. A block diagram of the recovery organization is presented in Figure 6.2-1. Table 6.2-1 indicates the personnel designated to assume responsibility of each of the activities shown in the block diagram.

The State will be the lead organization for off-site recovery operations. The State's recovery organization will be in accordance with the North Carolina Emergency Response Plan.

6.3 Assignment of Responsibilities 6.3.1 Recovery Manager The recovery organization, under the direction of the Recovery Manager, will have the following responsibilities:

a. Assess and determine the overall damage.
b. Develop a recovery plan.
c. Identify resources needed to complete the recovery.
d. Obtain any services and equipment necessary to complete the needed repair.
e. Conduct post-accident evaluations of the causes and consequences of the incident.
f. Obtain all necessary licenses, or amendments to licenses, required for repair of the Unit and disposal of radioactive waste products.
g. Coordinate with local and State agencies to keep them informed of onsite activities on a timely basis and provide support for any off-site protective actions required during the recovery operations.
h. Coordinate NRC activities at the site in an effort to avoid duplication and minimize impact on the plant staff.
i. Control personnel exposure during re-entry and recovery operations.

6.3.2 Plant General Manager The Plant General Manager is responsible for implementation of in-plant recovery activities with the objective of maintaining a safe shutdown conditions and controlling sources of radioactivity in the plant. The Plant General Manager will report to the Recovery Manager during recovery operations.

Responsibilities of the Plant General Manager include the following:

a. Direct operations of the plant site including approval and implementation of engineering modifications, special tests and experiments, and maintenance operations to recover from the incident.
b. Coordinate the plant staff's efforts to identify any damages to the facility.
c. Provide security forces as necessary for the plant site.
d. Coordinate on-site health physics activities, including on-site sampling program, dose assessment, dose management, and radiation protection programs.

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e. Provide information and recommendations to the Recovery Manager concerning future operations that could affect the plant or the environment.

6.3.3 Technical Analysis Manager The Technical Analysis Manager is responsible for analysis and development of plans and procedures to support the recovery operation and to maintain the affected Unit in a safe shutdown condition in a manner which minimizes the effect on the health and safety of the public.

Responsibilities of the Technical Analysis Manager include:

a. Provide support to the Recovery Manager in assessing the cause of the emergency.
b. Provide technical support to the Recovery Manager in systems analysis, core analysis, operating and maintenance procedural revisions, licensing information development and coordination, plant systems design data development, continued assessment of plant systems interaction, and continued determination of the safety status of the plant.
c. Provide technical interface as authorized by the Recovery Manager to utility groups, consultants, technical investigation groups, and regulatory agencies.
d. Assess the impact of the incident on continued operation of other CP&L nuclear plants, and submit results of this assessment to the Recovery Manager for review and subsequent submittal to CP&L Management.

6.3.4 Engineering Manager The Engineering Manager is responsible for engineering and design support to meet requirements of the recovery operation.

Responsibilities of the Engineering Manager include:

a. Provide engineering support to the Recovery Manager in assessing the cause of the emergency and the extent of equipment and systems damage.
b. Develop an engineering support plan compatible with the overall plant recovery plan. This plan will include allocation of engineering personnel resources.
c. Assist the Recovery Manager in establishing a list of plant equipment/systems modifications required for plant safe cold shutdown, plant cleanup, and plant restart.
d. Coordinate and supervise the engineering work performed by the Engineering Group including the Architect-Engineer, Nuclear Steam System Supplier, and other engineering consultants.
e. Coordinate the timely transmittal of engineering modification design documents (specifications and drawings) to the Construction and Plant Procurement Groups.

6.3.5 Construction Manager The Construction Manager coordinates the construction activities to meet the requirements of the recovery operation.

Responsibilities of the Construction Manager include:

a. Provide construction support to the Recovery Manager in assessing the cause(s) of the emergency and the extent of any structural damage.
b. Develop a construction plan, including the allocation of construction personnel, to support the timely completion of identified plant modifications required during the recovery process.
c. Coordinate and supervise the construction work performed by outside contractors.
d. Coordinate the timely transfer of installed equipment and/or systems (modifications) to Plant Operations Group in accordance with the established recovery procedures.

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6.3.6 Administrative and Logistics Manager The Administrative and Logistics Manager provides administrative, logistic, communications, and personnel support for the recovery operation.

Responsibilities of the Administrative and Logistics Manager include:

a. Provide assistance to the Recovery Manager in the planning, scheduling, and expediting of recovery operations.
b. Coordinate the use of communications personnel from other departments to install, maintain, and operate on-site communications facilities needed to carry out the recovery plan.
c. Provide purchasing personnel responsible for locating, ordering, and receiving equipment and materials needed to carry out the recovery plan.
d. Prepare an inventory of materials, supplies, and equipment that may be needed and locate potential suppliers.
e. Provide processing of expense accounts. distribution of checks from payroll, and administration of other personal financial aspects of the recovery organization.
f. Provide logistics arrangements for support personnel called in to assist in the recovery operations, including communications hardware, transportation, room and board.
g. Establish and maintain a cost control/accounting system for the recovery operation.
h. Determine additional contracts, facilities, and services required by the recovery organization and provide these facilities and services.
i. Serve as a liaison between the Recovery Manager end the Legal Department.
j. Provide appropriate Corporate and Contractor insurance personnel to process claims for financial losses resulting from emergency activities.
k. Establish and maintain a document control system for the recovery operation.
1. Provide administrative services for the recovery organization such as clerical, typing, and duplication.
m. Provide support for the screening, orientation, and badging of support personnel.
n. Process invoices from supporting utilities and contractors whose personnel were obtained through mutual aid agreements.

6.3.7 Radiological Control Manager The Radiological Control Manager is responsible for providing radiation protections and radioactive waste disposal plans consistent with the recovery operation.

Responsibilities of the Radiological Control Manager include:

a. Assist the Recovery Manager by providing as low as reasonably achievable (ALARA) review of engineering modifications and tasks proposed by the recovery organization, including necessary documentation of those reviews.
b. Coordinate with Engineering Manager in the design of special packaging required for the transport of radioactive waste resulting from the incident and recovery operation.
c. Assist in assessment of off-site radiological consequences of the incident. Coordinate and communicate with the State and the results of radiological assessments.
d. Develop methods for sampling, treatment, and/or disposal of radioactive wastes resulting from the emergency and recovery operation.
e. Provide consultation, support, review, and inspection of special waste treatment facilities.
f. Provide dose calculations to the Recovery Manager for total population exposure based on data from available sources and/or mathematical modeling.

6.4 Recovery Plan Activation Once the Site Emergency Coordinator and the Emergency Response Manager have determined that recovery

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efforts can begin, the Emergency Response Manager will activate the recovery organization and become the Recovery Manager.

Implementation of Recovery Operations would occur as follows:

1. Transition from Emergency to Recovery
2. Activation of Recovery Organization The decision to de-escalate or terminate the emergency condition and begin recovery operations may be based on the following considerations:
a. Stability of the reactor shutdown condition, i.e., successful progress toward a cold shutdown-condition.
b. Integrity of the Reactor Containment Bui1ding.
c. Operability of radioactive waste systems and decontamination facilities. *
d. The availability and operability of a heat sink.
e. The integrity of power supplies and electrical equipment.
f. The operability and integrity of instrumentation including radiation monitoring equipment.
g. Availability of trained personnel and support services.
h. Radiation levels in plant areas are stable o~ decreasing with time.
i. Releases of radioactive materials to the environment from the plant are under control or have ceased.
j. Any fire, flooding, or similar emergency conditions are controlled or have ceased.
k. Reduced or removed security threat.

Decisions to relax protective actions for the public will be made in accordance with the North Carolina Radiological Emergency Plan. The Recovery Manager will provide information to the appropriate State agencies to facilitate the decision.

Notification of on-site and off-site organizations that the Recovery Organization is to be activated will be initiated by the Emergency Response Manager and will follow plant emergency notification procedures. Notification will follow the plant emergency procedures summarized in Section 4.2 of the Plan, except that the notification message will state that the Recovery Plan has been initiated and will list the new positions of the Recovery Organization. The notification time limits will not be applied.

6.5 Recovery Planning Recovery from an emergency situation is guided by the following principles:

a. The protection of the public health and safety is the foremost consideration in formulating recovery plans.
b. Public officials are kept informed of recovery plans so that they can properly carry out their responsibilities to the public.
c. Periodic briefings of media representatives are held to inform the public of recovery plans and progress made.
d. Periodic status reports are given to company employees at other locations and to government and industry representatives.
e. The radiation doses to employees and other radiation workers are kept as low as reasonably achievable (ALARA).
f. Necessary adjustments in the size and makeup of the Recovery Manager's staff are made as deemed necessary by the Recovery Manager.

6.6 Reentry Planning The plans and procedures for area reentry will be developed at the time and will consider existing as well as potential conditions inside affected areas. Prior to reentry, the Recovery Manager and staff shall:

a. Review all available radiation survey data and determine plant areas potentially affected by radiation exposure and contamination.

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b. Review the radiation exposure records of personnel participating 1n the recovery operation and determine the need for additional personnel.
c. Review the adequacy of the radiation sampling and survey instrumentation to be used by the team (type, ranges, number, calibration, etc.).
d. Review protective clothing, dosimetry, and respiratory protection needs.
e. Ensure appropriate communications are available.
f. Ensure all team members are briefed concerning areas to be entered, anticipated radiation levels, access control procedures, and methods and procedures that will be employed during the entry.

The initial-entry into the affected area should encompass the following actions:

  • Conduct a comprehensive radiation survey of the plant facilities and define all radiological problem areas.
  • Isolate and post with appropriate warning signs all radiation and contamination areas.
  • Identify potential hazards associated with the recovery operation.

6.7 Total Population Exposure Estimates The Radiological Control Manager will periodically update the estimate of total population exposure. The estimate will be determined from data collected in cooperation with the State.

The North Carolina Radiation Protection Section (RPS), Department of Human Resources, will be the lead state agency in the collection and analysis of radiation monitoring reports and of environmental air, foliage, food, and water samples. The RPS will be assisted by qualified personnel from SHHPP and the Shearon Harris Energy and Environmental Center.

Total population exposure will be periodically determined through a variety of procedures including:

  • Examination of prepositioned TLDs.
  • Bioassay
  • Estimates based on release rates and meteorology.
  • Estimates based on environmental monitoring of food, water, and ambient dose rates.

6.8 Recovery Termination and Reporting Requirements Responsibility for providing a close out verbal summary and written summary to off-site authorities after the accident is the responsibility of the Plant General Manager. These summaries should be simple and in sufficient detail only to define that the accident situation is ended.

The Plant General Manager will provide a preliminary report to the Vice President-Nuclear Operations on all emergencies by the end of the next workday following the event. In addition to the preliminary report, the Plant General Manager will provide a close out report to the Vice President-Nuclear Operations within 30 days following the emergency.

Reports to the NRC are in accordance with 10CFR50.72, 10CFR20.403, and the SHNPP Technical Specifications, Section 6.9.

PLP-201 Emergency Plan, Rev 67 Section 6 Recovery 6.1 Recovery Planning Recovery is defined as those steps taken to return the plant to its pre-accident condition. The overall goals of the recovery effort are to assess the in-plant consequences of the emergency and perform cleanup and repair

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operations. This effort includes the utilization of Duke Energy Corporate resources and interfacing with outside agencies. All recovery actions will be pre-planned in order to minimize radiation exposure or other hazards to recovery personnel.

Recovery from an emergency situation is guided by the following principles:

A. The protection of the public health and safety is the foremost consideration in formulating recovery plans.

B. Public officials are kept informed of recovery plans so that they can properly carry out their responsibilities to the public.

C. Periodic briefings of media representatives are held to inform the public of recovery plans and progress made.

D. Periodic status reports are given to company employees at other locations and to government and industry representatives.

E. The radiation doses to employees and other radiation workers are kept As Low As Reasonably Achievable (ALARA).

F. Necessary adjustments in the size and makeup of the Recovery Manager's staff are made as deemed necessary by the Recovery Manager.

The recovery organization may begin to develop plans for recovery of the facility while the emergency is still in progress. However, these efforts will not be permitted to interfere with or detract from the efforts to control the emergency situation. During the emergency phases of the incident, the recovery organization resources will be available to assist and provide support for the Site Emergency Coordinator.

6.2 Recovery Plan Activation The Site Emergency Coordinator, with concurrence from the Emergency Response Manager, has the responsibility for determining when an emergency situation is stable and the plant is ready to enter the recovery phase. Prior to terminating an emergency and entering the recovery phase, the following conditions are considered:

A. Do conditions still meet an Emergency Action Level? If so, does it appear unlikely that conditions will deteriorate?

B. Radioactive releases are under control and are no longer in excess of Technical Specification limits.

C. The radioactive plume has dissipated and plume tracking is no longer required. The only environmental assessment activities in progress are those necessary to assess the extent of deposition resulting from passage of the plume.

D. In-plant radiation levels are stable or decreasing, and acceptable, given the plant conditions.

E. The potential for uncontrolled radioactive release is acceptably low.

F. The reactor is in a stable shutdown condition and long-term core cooling is available.

G. Containment pressure in within Technical Specification limits.

H. Any fire, flood, earthquake or similar emergency condition no longer exists.

I. All required notifications have been made.

J. Discussions have been held with Federal, State and local agencies and agreement has been reached to terminate the emergency.

K. At an Alert or higher classification, the Emergency Response Organization is in place and emergency facilities are activated.

It is not necessary that all conditions listed above be met; however, all items must be considered prior to entering the recovery phase. For example, it is possible after a severe accident that some conditions remain which exceed and Emergency Action Level, but entry into the recovery phase is appropriate.

Decisions to relax protective actions for the public will be made in accordance with the North Carolina Radiological Emergency Plan. The Recovery Manager will provide information to the appropriate state agencies to facilitate the decision.

Once the decision is made to enter the recovery phase, the extent of the staffing required for the HNP Recovery

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Organization is determined.

A. For events of a minor nature, (that is, for UNUSUAL EVENT classifications) the normal on shift organization is normally adequate to perform necessary recovery actions.

B. For events where damage to the plant has been significant, but no offsite releases have occurred and/or protective actions were not performed, (that is, for Alert classifications) the HNP Emergency Response Organization, or portions thereof, should be adequate to perform the recovery tasks prior to returning to the normal plant organization.

C. For events involving major damage to systems required to maintain safe shutdown of the plant and offsite radioactive releases have occurred, (that is, for Site Area Emergency or General Emergency classifications) the Recovery Organization is put in place.

When the decision is made to enter the recovery phase, all members of the HNP Emergency Response Organization are informed of the change. All appropriate personnel are instructed of the Recovery Organization and their responsibilities to the recovery effort. Notification of off-site organizations that the Recovery Organization is to be activated will be initiated by the Emergency Response Manager and will follow plant emergency notification procedures summarized in Section 4.2 of the Plan (except that the notification message will state that the Recovery Plan has been initiated, will list the new positions of the Recovery Organization, and the notification time limits will not be applicable).

6.3 Recovery Organization The specific members of the Recovery Organization are selected based on the sequence of events that preceded the recovery activities as well as the requirements of the recovery phase. The basic framework of the Recovery Organization is as follows:

Recovery Manager:

Onsite Recovery Director Offsite Recovery Director Company Spokesperson Other Duke Energy Support This organization may be modified during the recovery process to better respond to the conditions at the plant.

The state will be the lead organization for off-site recovery operations. The state's recovery organization will be in accordance with the North Carolina Emergency Response Plan.

6.4 Assignment of Responsibilities 6.4.1 Recovery Manager The Recovery Manager is charged with the responsibility for directing the activities of the HNP Recovery Organization. These responsibilities include:

A. Ensuring that sufficient personnel from Duke Energy and other organizations are available to support recovery.

B. Directing the development of a recovery plan and procedures.

C. Ensuring that adequate engineering activities to restore the plant are properly reviewed and approved.

D. Deactivating any of the HNP Emergency Response Organization which was retained to aid in recovery, in the appropriate manner.

E. Coordinating the integration of available Federal and State assistance into onsite recovery activities.

F. Coordinating the integration of Duke Energy support with Federal, State and local authorities into required offsite recovery activities.

G. Approving information released by the public information organization which pertains to the emergency or the recovery phase of the accident.

H. Determining when the recovery phase is terminated.

I. The Vice President-HNP or a designated alternate is the Recovery Manager.

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6.4.2 Onsite Recovery Director The Onsite Recovery Director reports to the Recovery Manager and is responsible for:

A. Coordinating the development and implementation of the recovery plan and procedures.

B. Directing all onsite activities in support of the recovery of HNP.

C. Designating other Duke Energy recovery positions required in support of onsite recovery activities.

The Onsite Recovery Director position will normally be filled by the General Manager-Harris Plant or designee.

6.4.3 Offsite Recovery Director The Offsite Recovery Director reports to the Recovery Manager and is responsible for:

A. Providing liaison with offsite agencies and coordinating HNP assistance for offsite recovery activities.

B. Coordinating HNP ingestion exposure pathway EPZ sampling activities.

C. Developing a radiological release report.

D. Designating other HNP recovery positions required in support of offsite recovery activities.

The Offsite Recovery Director position will normally be filled by the Director Nuclear Organizational Effectiveness or designee.

6.4.4 Company Spokesperson The Company Spokesperson reports to the Recovery Manager and is responsible for:

A. Functioning as the official spokesperson to the press for Duke Energy on all matters relating to the accident or recovery.

B. Coordinating non-Duke Energy public information groups (Federal, State, County, and so forth).

C. Coordinating media monitoring and rumor control.

D. Determining what public information portions of the HNP Emergency Response Organization will remain activated.

The Company Spokesperson position will normally be filled by the Communications Consultant-HNP or designee.

6.4.5 The Remainder of the HNP Recovery Organization The remainder of the HNP Recovery Organization is established and an initial recovery plan developed at the end of the emergency phase or just after entry into the recovery phase. Consideration is given to recovery activity needs and use of the normal HNP organizations. Individual recovery supervisor may be designated in any or all of the following areas:

A. Maintenance B. Engineering/Technical Support C. Radiation Protection D. Operations E. Chemistry F. Security G. Quality Assurance H. Training I. Special Offsite Areas (Community Representatives, Environmental Samples, Investigations, and so forth) 6.5 Reentry Planning The plans and procedures for area reentry will be developed at the time and will consider existing as well as potential conditions inside affected areas.

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Prior to reentry, the Recovery Manager and staff shall:

A. Review all available radiation survey data and determine plant areas potentially affected by radiation exposure and contamination.

B. Review the radiation exposure records of personnel participating in the recovery operation and determine the need for additional personnel.

C. Review the adequacy of the radiation sampling and survey instrumentation to be used by the team (type, ranges, number, calibration, and so forth).

D. Review protective clothing, dosimetry, and respiratory protection needs.

E. Ensure appropriate communications are available.

F. Ensure all team members are briefed concerning areas to be entered, anticipated radiation levels, access control procedures, and methods and procedures that will be employed during the entry. The initial entry into the affected area should encompass the following actions:

  • Conduct a comprehensive radiation survey of the plant facilities and define all radiological problem areas.
  • Isolate and post with appropriate warning signs all radiation and contamination areas.
  • Identify potential hazards associated with the recovery operation.

6.6 Total Population Exposure Estimates The Radiological Control Manager will periodically update the estimate of total population exposure. The estimate will be determined from data collected in cooperation with the State.

The North Carolina Radiation Protection Section (RPS), Department of Environment, Health and Natural Resources will be the lead state agency in the collection and analysis of radiation monitoring reports and of environmental air, foliage, food, and water samples. The RPS will be assisted by qualified personnel from HNP.

Total population exposure will be periodically determined through a variety of procedures including:

A. Examination of prepositioned TLDs.

B. Bioassay C. Estimates based on release rates and meteorology.

D. Estimates based on environmental monitoring of food, water, and ambient dose rates.

6.7 Recovery Termination and Reporting Requirements Responsibility for providing a closeout verbal summary and written summary to off-site authorities after the accident is the responsibility of the General Manager - Harris Plant. These summaries should be simple and in sufficient detail only to define that the accident situation is ended.

Reports to the NRC are in accordance with 10CFR50.72, 10CFR20, Subpart M, and the HNP Technical Specifications, Section 6.9.

RG 1.219 Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors, Rev 1. (July 2016) 3.5 Emergency Plan

a. Emergency plan means the document(s) that the licensee prepared and maintains that identifies and describes its methods for maintaining emergency preparedness and responding to emergencies. An emergency plan includes the plan that the NRC originally approved and all subsequent changes that the licensee made with and without prior NRC review and approval under 10 CFR 50.54(q). See 10 CFR 50.54(q)(1)(ii) for additional information.
b. This definition highlights that emergency plan includes the documents that describes the programmatic methods that the licensee uses to maintain emergency preparedness and to respond to emergencies. These methods, or program elements, are the implementation aspects of the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50 and generally correspond to the evaluation criteria of NUREG-0654 or approved alternatives that

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supply specific acceptable methods for complying with the planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50. Such programmatic documents are subject to the 10 CFR 50.54(q) change process. Non-programmatic documents, such as training rosters, equipment and maintenance test reports, lesson plans, and other documents that document the performance of the program elements, as opposed to those that establish the program elements, are not included.

c. Ordinarily, sub-tier documents such as emergency plan implementing procedures (EPIPs) are not considered to be part of an emergency plan for the purpose of evaluating proposed changes. If a licensee relocates a programmatic description from the emergency plan to a sub-tier document, that programmatic description continues to be subject to the 10 CFR 50.54(q) change process. For example, licensees have relocated the details of emergency classification schemes from the emergency plan to an EPIP or to large wall charts maintained in the control room. Because the EPIP or wall chart is now the means to demonstrate compliance with the planning standards in 10 CFR 50.47(b)(4), these sub-tier documents are subject to 10 CFR 50.54(q). Repeating, as opposed to relocating, program element descriptions in sub-tier documents do not necessarily make the sub-tier documents subject to the 10 CFR 50.54(q) change process. However, the descriptions in the various documents must remain consistent.
d. As a simple test, a licensee can consider what programmatic document(s), in addition to its emergency plan, it would supply during an inspection to demonstrate that its emergency plan meets the regulatory requirements, as informed by the evaluation criteria in NUREG-0654 or by approved alternatives. These documents would likely be subject to the 10 CFR 50.54(q) change process.
e. This definition also highlights the need to consider the NRC-approved plan and the subsequent changes in reviewing against 10 CFR 50.54(q) to ensure that a series of incremental changes (each determined not to reduce the effectiveness of the plan) do not reduce the effectiveness of the plan when compared to the NRC-approved plan.

The differences in implementing revisions and the current revisions of the Emergency Plans have been reviewed and they have been determined to meet the regulatory requirements required during the course of revisions. Each revision has been evaluated in the regulatory process has met the approval of the NRC during the inspection process.

The changes described in this Evaluation were made to reflect the changes for the EOF relocation to Charlotte and the changes made for Standard ERO. PEP-500 Recovery is being superseded. All functions performed by this procedure has been moved to a fleet procedure. One commitment identified in this procedure has been relocated to AD-EP-ALL-0110 Recovery. This fleet procedures provides the same capability to perform the tasks across the fleet. These changes do not reduce the effectiveness of the emergency plan or reduce the capability to meet the licensing bases as described in:

  • NUREG-1038, Safety Evaluation Report Related to the Operation of the Shearon Harris Nuclear Power Plant, Units 1 and 2

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Part Ill. Description of How the Proposed Change Complies with Regulation and Commitments.

If the emergency plan, modified as proposed, no longer complies with planning standards in 10 CFR 50.47(b) and the requirements in Appendix E to 10 CFR Part 50, then ensure the change is rejected, modified, or processed as an exemption request under 10 CFR 50.12, Specific Exemptions, rather than under 10 CFR 50.54(q):

10 CFR 50.47(b)(1), Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

10 CFR 50 Appendix E IV.A The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization and the means for notification of such individuals in the event of an emergency. Specifically, the following shall be included:

b. Plant staff emergency assignments 10 CFR 50.47(b)(13), Recovery and Reentry Planning General Plans for recovery and reentry are developed 10 CFR Part 50, Appendix E does not contain any supporting requirements Evaluation Duke Energy nuclear stations will continue to have adequate methods for assessing the emergency and to enter into the recovery phase when appropriate. The changes described maintains compliance with the applicable sections of 10CFR50.47(b) and 10CFR50 Appendix E.

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Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change (Address each function identified in Attachment 4, 10 CFR 50.54(q) Screening Evaluation Form, Part IV of associated Screen):

Standard 10 CFR 50.47(b)(1) Assignment of Responsibility\Organizational Control Primary responsibilities for emergency response by the nuclear facility licensee and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Function Two emergency planning functions have been defined for this planning standard:

(1) Responsibility for emergency response is assigned.

(2) The response organization has the staff to respond and to augment staff on a continuing basis (i.e., 24/7 support) in accordance with the emergency plan.

Element NUREG 0654 II. Section A.

Primary responsibilities for emergency response by the nuclear facility licensee, and by State and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

NUREG 0654 II. Section J.

7. Each licensee shall establish a mechanism for recommending protective actions to the appropriate State and local authorities. These shall include Emergency Action Levels corresponding to projected dose to the population-at-risk, in accordance with Appendix 1 and with the recommendations set forth in Tables 2.1 and 2.2 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-520/1-75-001). As specified in Appendix 1, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone.

Standard 10 CFR 50.47(b)(13), Recovery and Reentry Planning General Plans for recovery and reentry are developed Function Plans for recovery and reentry are developed.

Element NUREG 0654 II. Section M Each organization, as appropriate, shall develop general plans and procedures for reentry and recovery ad describe the means by which decisions to relax protective measures (e.g., allow reentry into an evacuated area) are reached. This process should consider both existing and potential conditions.

Each licensee plan shall contain the position/title, authority and responsibilities of individuals who will fill key positions in the facility recovery organization. This organization shall include technical personnel with

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responsibilities to develop, evaluate and direct recovery and reentry operations. The recovery organization recommended by the Atomic Industrial Forum's "Nuclear Power Plant Emergency Response Plan" dated October 11, 1979, is an acceptable framework.

Each licensee and State plan shall specify means for informing members of the response organizations that a recovery operation is to be initiated, and of any changes in the organizational structure that may occur.

Each plan shall establish a method for periodically estimating total population exposure.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Functions The following functions were identified in the performance of this evaluation:

Responsibility for emergency response is assigned.

Plans for recovery and reentry are developed.

The adoption of the standard ERO will continue to maintain or improve the capability and timeliness of the HNP ERO to respond evaluate an event and effectively enter the recovery phase when appropriate. HNP continues to maintain the capability to enter the recovery phase and exit the emergency when deemed appropriate during the event.

The changes described do not affect the emergency planning functions listed in Part IV associated with 10 CFR 50.47(b) because the changes ensure adequate personnel are available, understand the roles assigned to them, and can implement a recovery organization and plan. The changes do not affect supporting requirements described in 10 CFR 50, Appendix E.IV. The changes continue to ensure that adequate provisions shall be made and described for recovering from an emergency and the changes continue to ensure the organization for coping with radiological emergencies is described.

The changes described provide additional assurance that the normal plant operating organization and ERO has the ability and capability to:

  • respond to an emergency;
  • perform functions in a timely manner;
  • effectively identify and take measures to ensure the protection of the onsite emergency staff
  • enter the recovery phase of an event These changes support the HNP Emergency Plan, by ensuring that procedures used during response to a classified emergency are available. Effective use of these procedures helps ensure emergency response functions as described in the Emergency Plan are adequately maintained and demonstrated. The functions identified in this procedure were relocated to applicable fleet procedures to standardize ERO task and functions across the Duke Energy Fleet.

The changes described maintain the functions as described in the HNP Emergency Plan, as written and approved; and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.

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Part VI. Evaluation Conclusion.

Answer the following questions about the proposed change.

1 Does the proposed change comply with 10 CFR 50.47(b) and 10 CFR 50 Appendix E? Yes No 2 Does the proposed change maintain the effectiveness of the emergency plan (i.e., no Yes No reduction in effectiveness)?

3 Does the proposed change maintain the current Emergency Action Level (EAL) scheme? Yes No 4 Choose one of the following conclusions:

a The activity does continue to comply with the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E, and the activity does not constitute a reduction in effectiveness or change in the current Emergency Action Level (EAL) scheme. Therefore, the activity can be implemented without prior NRC approval.

b The activity does not continue to comply with the requirements of 10 CFR 50.47(b) or 10 CFR 50 Appendix E or the activity does constitute a reduction in effectiveness or EAL scheme change.

Therefore, the activity cannot be implemented without prior NRC approval.

Part VII. Disposition of Proposed Change Requiring Prior NRC Approval Will the proposed change determined to require prior NRC approval be either revised or Yes No rejected?

If No, then initiate a License Amendment Request in accordance 10 CFR 50.90 and AD-LS-ALL-0002, Regulatory Correspondence, and include the tracking number:__________________________________________________.

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Part VIII. Signatures: EP CFAM Final Approval is required for changes affecting risk significant planning standard 10 CFR 50.47(b)(4).

Preparer Name (Print): Preparer Signature: Date:

Jeffery White signed electronically in CAS 11/29/17 Reviewer Name (Print): Reviewer Signature: Date:

David Stih signed electronically in CAS 11/29/17 Approver (EP Manager) Name (Print): Approver Signature: Date:

Jamey Sharlow signed electronically in CAS 11/29/17 Approver (CFAM, as required) Name (Print): Approver Signature: Date:

n/a n/a If the proposed activity is a change to the E-Plan or implementing procedures, then create two EREG General Assignments.

If required by Section 5.5, Submitting Reports of Changes to the NRC, then create two EREG General Assignments.

to Licensing.

  • One for Licensing to submit the 10 CFR 50.54(q) information to the NRC within 30 days after the change is put in effect.

QA RECORD