ML16207A113

R.E. Ginna, Radiological Emergency Plan Annex Revisions

ML16207A113
Person / Time
Site:	Calvert Cliffs, Nine Mile Point, Ginna
Issue date:	07/14/2016
From:	David Gudger Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML16207A113 (364)

Text

ii? 200 Exelon Way Exelon Generation Kennett Square, PA 19348 www.exeloncorp.com July 14, 2016 1 O CFR 50, Appendix E 10 CFR 50.54(q)(5).

10 CFR 50.4 10 CFR 72.44(f) U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRG Docket Nos. 50-317 and 50-318 Calvert Cliffs Independent Spent Fuel Storage Installation Materials License No. SNM-2505 NRG Docket No. 72-8 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRG Docket Nos: 50-220, 50-410, and 72-1036 R.E. Ginna Nuclear Power Station Renewed Facility Operating License No. DPR-18 NRG Docket Nos. 50-244 and 72-67 Exelon Nuclear Radiological Emergency Plan Annex Revisions In accordance with 1 O CFR 50.4(b)(5), "Emergency Plan and related submissions," Exelon Generation Company, LLC (EGG) is submitting the Emergency Plan Annex revisions identified in the table below for Calvert Cliffs Nuclear Power Plants (Calvert Cliffs), Nine Mile Point Nuclear Station (NMP), and R.E. Ginna Nuclear Power Station (Ginna). I Procedure

• 1 Revision**

Title'**.

EP-AA-1011 1 Exelon Nuclear Radiological Emergency Plan Annex for Calvert Cliffs Station EP-AA-1012 3 Exelon Nuclear Radiological Emergency Plan Annex for Ginna Station EP-AA-1013 2 Exelon Nuclear Radiological Emergency Plan Annex for Nine Mile Point Station The changes to the Emergency Plan Annexes were evaluated under the requirements of 1 O CFR 50.54(q) and were determined not to result in a reduction in the effectiveness of the Emergency Plans for Calvert Cliffs, NMP, and Ginna. This notification is being submitted within 30 days of implementation of the changes as required by 1 O CFR 50, Appendix E. The changes continue to meet the applicable planning standards established in 1 O CFR _ ll h ( 0 50.47(b) and 10 CFR 50, Appendix E. )I/"

U.S. Nuclear Regulatory Commission Emergency Plan Annex Revisions July 14, 2016 Page 2 In addition, as required by 1 O CFR 50.54(q)(5), this submittal includes a summary analysis of the changes to the Emergency Plan Annexes (Attachment

1) for the cited plants. This submittal also satisfies the reporting requirements associated with 1 O CFR 72.44(f), which stipulates that within six months after any change is made to the Emergency Plan, the licensee shall submit a report containing a description of the changes to the Director, Division of Spent Fuel Storage and Transportation.

A copy of the revised procedure and supporting change summary analysis are included in the attachments to this letter. There are no regulatory commitments in this submittal.

If you have any questions or require additional information, please contact Richard Gropp at (610) 765-5557.

Respectfully,

--/. David T. Gudger Manager, Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachments:

1. 1 O CFR 50.54(q)(5)

Procedure Change Summary Analysis 2. EP-AA-1011, Revision 1, "Exelon Nuclear Radiological Emergency Plan Annex for Calvert Cliffs Station"

• 3. EP-AA-1012, Revision 3, "Exelon Nuclear Radiological Emergency Plan Annex for Ginna Station" 4. EP-AA-1013, Revision 2, "Exelon Nuclear Radiological Emergency Plan Annex for Nine Mile Point Station" cc: w/ Attachment 1 only Regional Administrator

-NRG Region I Director, NRG Division of Spent Fuel Storage and Transportation, ONMSS NRG Senior Resident Inspector

-Calvert Cliffs Nuclear Power Station NRG Senior Resident Inspector

-Nine Mile Point Nuclear Station NRG Senior Resident Inspector

-R.E. Ginna Nuclear Power Station NRG Project Manager, NRR -Calvert Cliffs Nuclear Power Station NRG Project Manager, NRR -Nine Mile Point Nuclear Station NRG Project Manager, NRR -R. E. Ginna Nuclear Power Station S. T. Gray, State of Maryland A. L. Peterson, NYSERDA ATTACHMENT 1 10 CFR 50.54(q)(5)

Procedure Change Summary Analysis Attachment 1 Page 1 of 8 1 O CFR 50.54(g)(5)

Procedure Change Summary Analysis Procedures/Titles Exelon Generation Company, LLC (EGC) is submitting the following Emergency Plan Annex revisions for Calvert Cliffs Nuclear Power Station (Calvert Cliffs), Nine Mile Point Nuclear Station (NMP) and the R.E. Ginna Nuclear Power Station (Ginna):

• EP-AA-1011, Revision 1, "Exelon Nuclear Radiological Emergency Plan Annex for Calvert Cliffs Station"

• EP-AA-1012, Revision 3, "Exelon Nuclear Radiological Emergency Plan Annex for Ginna Station"

• EP-AA-1013, Revision 2, "Exelon Nuclear Radiological Emergency Plan Annex for Nine Mile Point Station" Description of Procedures These documents are the Emergency Plan Station Annexes for the cited plants. Discussion of Changes 1. Training Frequency Revision (Calvert Cliffs, Ginna, and Nine Point) Description of Changes By letter dated July 29, 2015, Exelon submitted a License Amendment (LAR) pursuant to 1 O CFR 50.90 to define the annual training frequency for Exelon ERO personnel for the facilities noted below as "once per calendar year not to exceed 18 months between training sessions."

• Calvert Cliffs

• Nine Mile Point

• R.E. Ginna Subsequently, by letter dated March 17, 2016, the NRC approved the LAR (reference ML 15352A 164). Planning Standard 10 CFR 50.47(b)(15) specifies that Radiological Emergency Response Organization (ERO) training is provided to those who may be called on to assist in an emergency.

This is further expanded in regulatory guidance provided in NUREG-0654, Revision 1 , "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, "which specifies that organizations shall establish specialized initial and periodic retraining programs for those who may be called on to assist in an emergency.

• The proposed changes would revise the description of Emergency Response Organization (ERO) requalification training frequency defined in the station Emergency Plans listed above. The proposed frequency will be defined as "once per calendar year not to exceed 18

• Attachment 1 Page 2 of 8 months between training sessions." In this context, training session refers to the annual requalification training received by the ERO. Description of How the Change Still Complies with Regulations The revision to the ERO training frequency for the noted stations was approved by the NRC as documented in a letter and supporting Safety Evaluation Report (SER) dated March 17, 2016. The NRC approved the training frequency where annual training is defined as "is defined as once per calendar year not to exceed 18 months between training sessions. " Description of Why the Change is Not a Reduction in Effectiveness (RIE) This is a conforming change to an NRG-approved and supporting SER. Further evaluation under the 1 O CFR 50.54(q) process is not required based on the guidance specified in Regulatory Guide (RG) 1.219, "Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors," Section 5.1.a. 2. On-Shift Staffing Requirements (Calvert Cliffs) Description of Changes A change is being made to Figure 2-1, "Minimum On-Shift Staffing Requirements," to reflect the number of persons required to support the Fire Brigade. This is an enhancement to allow the Figure to provide a comprehensive view of the required on-shift staff. The actual number of persons on the Calvert Cliffs Fire Brigade has not changed as a result of this revision.

Note that the number of Fire Brigade members is evaluated under 1 O CFR 50, Appendix R, and not under 1 O CFR 50.54(q).

Description of How the Change Still Complies with Regulations The Calvert Cliffs Emergency Plan Annex Figure 2-1, "Minimum On-Site Staffing Requirements" table is being revised to reflect the actual Fire Brigade compliment required on shift. The actual Fire Brigade requirements for Calvert Cliffs are found in Updated Final Safety Analysis Report () Section 9.9.5, which states: 9.9.5 FIRE BRIGADE; COMPOSITION, RESPONSIBILITY, AND TRAINING Calvert Cliffs Nuclear Power Plant has a designated fire brigade of at least five members available on each shift. Members of the fire brigade do not include the minimum operations shift crew necessary for safe shutdown of both units. The fire brigade is trained and equipped to respond to fire-related emergencies at CCNPP. A mutual aid agreement has been established with off-site fire departments to provide assistance to the plant fire brigade on an as-needed basis. The on-shift fire brigade will be staffed with a fire brigade leader and at least two fire brigade members that have sufficient training and knowledge of nuclear safety systems to understand the effects of fire and fire suppression on nuclear safety performance criteria.

The sufficient training and knowledge is permitted to be provided by an Operations Technical Advisor dedicated to respond with the fire brigade.

Attachment 1 Page 3 of 8 A note (f) has been added to Figure 2-1 to explain the role of the Operations Advisor on the Fire Brigade and that an extra person may be required on shift if the Fire Brigade does not have sufficient nuclear safety system training and knowledge.

Description of Why the Change is Not a Reduction in Effectiveness (RI E) This is considered an editorial change to the table in that the actual Fire Brigade requirements are determined and evaluated under 1 O CFR 50, Appendix R and the site UFSAR. The number is placed in the Emergency Plan as an enhancement to allow reviewers to identify the total on-shift compliment on one (1) table. Changes to the Fire Brigade compliment will continue to be made in accordance with 1 O CFR 50, Appendix R and not 1 O CFR 50.54(q).

3. Manual Dose Assessment (Ginna) Description of Changes A change is being made to the Ginna Emergency Plan Annex to remove reference to the manual method to perform dose assessment.

The manual method was Ginna's original means of assessing projected doses resulting from accident conditions.

Subsequently, more sophisticated versions of Dose Assessment software were developed and added to the Emergency Plan; however, the description of the manual method was retained.

RG 1.219 allows changes to the Emergency Plan to re-establish the last NRG-approved licensing basis as long as the changes were based on an operating philosophy to exceed minimum requirements and not a done to compensate for special circumstances which existed at the, time of the change (e.g., performance issues or other deficiencies).

Description of How the Change Still Complies with Regulations Planning Standard 1 O CFR 50.47(b)(9) states that adequate methods, systems and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use. Furthermore, NUREG-0654,Section II.I, Accident Assessment Evaluation Criteria II.I ensures, with respect to Dose Assessment, that:

• Methods to be used for determining the source term of releases of radioactive material within plant systems are established as well as the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors.

• Each licensee shall establish the relationship between effluent monitor readings and onsite and offsite exposures and contamination for various meteorological conditions.

• Each licensee shall establish the methodology for determining the release rate/projected doses if the instrumentation used for assessment are offsca/e or inoperable.

• Each organization, where appropriate, shall provide methods, equipment and expertise to make rapid assessments of the actual or potential magnitude and locations of any radiological hazards through liquid or gaseous release pathways.

• Each organization shall establish means for relating the various measured parameters (e.g., contamination levels, water and air activity levels) to dose rates for key isotopes.

• Attachment 1 Page 4 of 8 Ginna's Emergency Plan Annex currently describes how the station meets these requirements.

Specifically, the Emergency Plan discusses multiple means to perform Dose Assessment including a procedure based manual method, a computer spreadsheet which mimics the manual methodology, and a sophisticated computer method which incorporates updated industry guidance.

Ginna utilizes the sophisticated URI computer-based program to perform dose assessments with their ERO, including on shift. The inclusion of the additional methods in the Emergency Plan exceeds the requirements of NUREG-0654.

Background A review of the historical licensing basis documentation was performed to establish the licensing basis and identify the reasons for including the three (3) dose assessment methods in the Emergency Plan. This review included a comparison of the initial Revision O licensing basis and subsequent revisions to the Emergency Plan with respect to dose assessment capabilities.

Ginna's initial Revision O to the site Emergency Plan contained the following description of the Dose Assessment capabilities.

A procedure for estimating off-site doses for areas around the plant is used at the TSC and EOF. Based upon these results, protective actions can be recommended As required by NUREG-0654, the original Emergency Plan described a single procedure based on a method for estimating offsite doses. The method was performed manually using tables and graph overlays.

As technology advanced, these manual methods were incorporated into a simple based spreadsheet.

The methodology was essentially the same; however, computers were used rather than paper tables and graphs. In 1989, Revision 8 of the Ginna Emergency Plan was implemented to recognize the computer-based spreadsheet in the Technical Support Center (TSC) and Emergency Operations Facility (EOF) which mimics the manual method, while maintaining the manual method in the Main Control Room (MCR). The following statement was added to the Emergency Plan to describe the computer-based program used: A computer program operating on a micro-computer is also available in the TSC and EOF. This system mimics the overlay method of calculating downwind dose rates and airborne contamination levels. As of 1981, the requirements of NUREG-0654 continued to be met with the additional redundancy offered by the computer spreadsheet program in the TSC and EOF. The addition of the computer was the result of the availability of improved technology and not by performance issues or identified deficiencies.

The addition created a more robust method of estimating offsite dose. The discussion of the manual procedure methods was maintained in the Emergency Plan and continued to be used in the MCR. As part of the 1989 revision, Ginna also added a more sophisticated computer-based program for dose assessment.

This program (i.e., MIDAS) utilized advanced methodologies to accomplish the dose assessments and meet the guidance requirements of NUREG-0654.

Attachment 1 Page 5 of 8 The more sophisticated programs provided more accurate and timely dose assessment estimates, surpassing the capabilities of the manual procedure methods. The following statement was added to the Ginna Emergency Plan: A more sophisticated computer program, which uses the methods for environmental dose calculations required by Federal regulations, is also available to assess doses during and after an emergency.

The revision was made as a result of a change in available technology and not driven by performance issues or identified deficiencies.

The addition was an enhancement that met the regulatory requirements and exceeded the requirements by including two (2) diverse methods for dose assessment.

The 1989 Ginna Emergency Plan recognized two (2) methods which supported dose assessment (a procedure-driven method which could be used with or without the aid of a computer spreadsheet and the more sophisticated MIDAS computer model). In 2005, the MIDAS computer model was replaced by NRC's computer-based program (i.e., RASCAL) (EOF8) at the TSC and EOF. The RASCAL model offered improvements over MIDAS in that it was self-contained and did not require a dial-up remote access to run. There no changes needed to the description in the Emergency Plan for this ctiange. In 2014, Ginna replaced the computer-based program (RASCAL) with Exelon's Unified Rascal Interface

.(URI) for performance of dose assessment.

URI was also placed in the MCR for use with on-shift assessments.

This change was evaluated pursuant to 1 O CFR 50.54(q).

Assessment The change to remove the reference to the manual procedure method and the associated computer supporting spreadsheet method from the Emergency Plan is considered acceptable.

These methods have been superseded initially by MIDAS, then based EOF8 and now by the current URI dose assessment program. URI incorporates updated methodologies for dose assessment and is considered more comprehensive, timely, and accurate than the original tables and graphs used in the manual method. URI continues to satisfy all the NUREG-0654 guidance requirements, is an acceptable method for performing dose assessment, and used successfully by many licensees in the industry.

Note that when the MIDAS system was incorporated at the station, Ginna could have elected to remove the manual procedure methods from the Emergency Plan and completely credit the sophisticated computer-based model without a reduction in effectiveness.

The station elected to retain the manual methods, as well as the descriptions contained in the station Emergency Plan at the time. RG 1.219 provides the governing guidance pertaining to which changes can be made without obtaining prior NRC approval.

The process involves evaluating the NRG-approved licensing basis and determining whether a proposed change would reduce the effectiveness (i.e., capabilities and timeliness) of performing an emergency planning function.

In this revision to the Emergency Plan, Ginna proposes to remove a discussion regarding the original manual dose assessment contained in the Emergency Plan licensing basis. For this change, the licensing basis was revised to add additional computer-based dose assessment Attachment 1 Page 6 of 8 methods, while retaining the original manual methods which have since become obsolete.

This exceeded the regulatory requirements and guidance established in NUREG-0654.

RG 1.219 allows a revision of the Emergency Plan to remove these original methods without considering the revision as a reduction in effectiveness if it can be shown that the original level of commitment can be maintained.

An example in RG 1.219, Section 1.6 specifies that a licensee should consider why regulatory requirements were exceeded when making a change to re-establish a previous licensing basis. RG 1.219 provides the following discussion with respect to reasons for exceeding regulatory requirements in the Emergency Plan: Was it a matter of exceeding the regulatory minimum as an operating philosophy, or was it done to compensate for special circumstances that existed when the decision was made? A decrease .... in the first case might not reduce effectiveness; a decrease ... in the second case would reduce effectiveness if the special circumstances still existed. For Ginna's change, there were no special circumstances that required the station to maintain both dose assessment methods to be described in the Emergency Plan. There were no performance issues or identified deficiencies which required multiple methods for dose assessment to be maintained.

There were no commitments to the NRC to require multiple methods for dose assessment to be maintained at the station. The additional methods were added due to technological advancements and changes in available methodology.

Ginna elected to maintain the description of the manual methods as an enhancement to the program. Due to the rudimentary methodology of the manual method and associated computer-based spreadsheet, the burden of maintaining a spreadsheet method, as well as the burden of maintaining ERO proficiency with manual methods, Ginna is removing the manual method and associated computer-based spreadsheet method from the Emergency Plan. The current URI methodology meets the regulatory requirements and guidance established of NUREG-0654 stated above. The URI program is accepted and used at the other Exelon stations, as well as other licensees in the industry.

The URI program is considered more accurate and timely than the manual methods previously used at the station. The program is' used both as a network-based program, and will also be implemented as a stand-alone self-contained program to satisfy Cyber Security requirements by 2017. This redundancy with the implementation of URI ensures a robust method will be available at the Emergency Response Facilities (ERFs) for dose assessment.

The availability of backup power to the ERFs and the Uninterruptible Power Supplies (UPSs) will further ensure that the dose assessment function will be maintained using a more sophisticated dose assessment method than could be provided by the manual methods. The MCR and TSC have two (2) redundant Personal Computers (PCs) with standalone versions of URI installed, while the EOF has three (3) redundant PCs. The UPS is available for at least four (4) hours at all of the ERFs, as well as dedicated backup generators at the TSC and EOF. Therefore, the URI method will provide for a more accurate, reliable, and timelier means of performing the dose assessment function.

Also, as noted, above this change was evaluated pursuant to 1 O CFR 50.54(q).

Attachment 1 Page 7 of 8 Specific Emergency Plan Changes Step 5.3.3 was revised to delete reference to X/Q "tables" and just reference the X/Q values. With the deletion of the manual method for dose assessment, the tables no longer exist. Step 5.3.3 was revised to delete a statement that: "The airborne concentration is multiplied by the X/Q value and divided by the wind speed to obtain an estimated release rate from the plant." The sentence provides specific details of how release rates are determined with respect to X!Q and windspeed.

This is accomplished through the URI program and such calculations are no longer performed.

In its place, the statement: "Field Team survey results can be used to back calculate doses at the site boundary and offsite, 11 to establish that release rates can still be obtained through the use of Field Team surveys through URI. This maintains the level of commitment to the NUREG-0654 guidance and does not reduce the effectiveness of the Emergency Plan. Step 5.3.3 was revised to delete the sentence:

for manually estimating offsite doses for areas around the plant is available in the Control Room, TSC and EOF. Based upon these results, protective actions can be recommended.

11 This procedure for manually estimating offsite dose is no longer necessary with the implementation of the more sophisticate URI dose assessment software.

While the Emergency Plan maintained the description of both methods for a period of time, it has been established above that this decision exceeded regulatory requirements and was not done as a result of performance issues or identified deficiencies.

As such, the level of commitment in the last NRG-approved licensing basis has not been reduced with the deletion of the manual method. Step 5.3.3 was revised to delete reference to the overlay method, which was associated with the manual methods. The sentence was revised to maintain the requirement to calculate downwind dose rates and airborne concentrations as stipulated by the guidance in NUREG-0654.

Some editorial changes were implemented as part of this revision to maintain sentence structure.

For example, the phrase 11 A more sophisticated

... 11 was replaced with the phrase "The sophisticated

... " in Step 5.3.3. In addition a revision was made to Step 5.3.1 O to delete reference to the manual calculation methods of dose assessment, leaving reference to the computerized calculation methods. This is acceptable for reasons stated above. The deletion of the manual methods of performing dose assessment (procedure and spreadsheet) from the Ginna Emergency Plan essentially re-establishes the original licensing basis. URI not only satisfies the original commitment for dose assessment found in the last NRC approved Emergency Plan, but it also satisfies current regulatory regulations and guidance for the performance of dose assessment.

Tummary, Ginna originally relied on a manual proceduralized method to perform dose assessment as described in Revision O of their Emergency Plan. Following advances in technology, Ginna implemented a computer-based dose assessment method which replaced the manual method. Following the adoption of the computer software to perform dose assessment, the manual method was no longer required to support any aspects of dose assessment.

The Emergency Plan retained reference to this manual method even though it was no longer required; this change to the Emergency Plan is removing reference to an outdated manual method of dose assessment.

Attachment 1 Page 8 of 8 Description of Why the Change is Not a Reduction in Effectiveness (RIE) This revision does not constitute a Reduction in Effectiveness as discussed above. There are no Regulatory Commitments impacted by this revision to the Emergency Plan. The current Computer method which remains in the Emergency Plan is an industry proven and NRC accepted method which has been installed at Ginna's ERFs with redundancy and continues to satisfy the Regulatory requirements referenced in the Emergency Plan. 4. Position Titles (Nine Mile Point EP-AA-1013, Revision 2) Description of Changes A revision was made regarding editorial changes to Figures 2.3 TSC Staffing and Figure 2.5 EOF Staffing.

Specifically changes were made to revise position titles. No changes to responsibilities were made as a result of this change. Description of How the Change Still Complies with Regulations Editorial changes to Figures 2.3 TSC Staffing and Figure 2.5 EOF Staffing were made to revise position titles. No technical changes were made and no changes to responsibilities were made as a result of this change. These changes do not impact the compliance with EP regulatory requirements.

• Description of Why the Change is* Not a Reduction in Effectiveness (RIE) Per RG 1.219, these types of changes do not result in a Reduction in Effectiveness of the Emergency Plan. Regulatory requirements and emergency planning commitments were not impacted.

ATTACHMENT 2 EP-AA-1011, Revision 1, "Exelon Nuclear Radiological Emergency Plan Annex for Calvert Cliffs Station" Emergency Plan Annex Revision Exelon Generation EXELON NUCLEAR EP-AA-1011 Revision 1 RADIOLOGICAL EMERGENCY PLAN ANNEX FOR CAL VERT CLIFFS STATION Calvert Cliffs Annex Exelon Nuclear REVISION HISTORY Revision 0: 04/15 Revision 1 : 06/16 -. June 2016 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY RESPONSE PLAN TABLE OF CONTENTS Exelon Nuclear PAGE Section 1: Introduction

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1-1 1.1 Site Description

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1-1 1.2 Purpose ............................................................................................

1-2 1.3 Concept. ...............................................................

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1-2 1.4 Emergency Response Documents

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1-3

• Figure 1-1, Emergency Planning Zones ......................................................

1-5 Figure 1-2, 10-Mile Emergency Planning Zone Boundary ............................

1-6 Section 2: Organizational Control of Emergencies

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2-1 2.1 Operating Organization

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• .......................

• .. 2-1 2.2 Standing Review Committees

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2-1 2.3 Emergency Organization

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2-1 2.4 Recovery Organization

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2-3 2.5 Contracted Services .............................................................................

2-5 2.6 Local Services ......................... , ............................................................

2-6 2.7 Participating Governmental Agencies ..................... .............................

2-6 Figure 2-1, Minimum On-Site Staffing Requirements

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2-13 Figure 2-2, Emergency Response Organization

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2-15 Figure 2-3, Recovery Organization

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2-20 Figu*re 2-4, Center Interfaces:

Unusual Event and Alert .............................

2-21 Figure 2-5, Center Interfaces:

Site Area and General Emergency

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2-22 Section 3: Classification of Emergencies

3.1 Classification

System ........................................................................

3-1 3.2 Unusual Event ...................................

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

3-1 3.3 Alert .................................................................................................

3-2 3.4 Site Area Emergency

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3-2 3.5 General Emergency

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3-3 Section 4: Emergency Measures ................................................... ..........................

4-1 4.1 Recognition and Classification

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4-1 4.2 Notification

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4-2 4.3 Augmentation

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4-2 4.4 Accident Assessment

...................................................................... , 4-3 4.5 Repair and Mitigative Action .............................................................

4-4 4.6 Protective Actions ............................................................................

4-4 4. 7 Exposure Control ..... : .......................................................................

4-4 4.8 Contamination Control. .....................................................................

4-5 4.9 Personnel Emergencies

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4-5 June 2016 ii EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Figure 4-1, Off-Normal Condition Response Sequence ................................

4-6 Figure 4-2, Off-Site Agency Notification

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4-7 Section 5: Facilities and Equipment

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5-1 5.1 Facilities

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5-1 5.2 Communications

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5-5 5.3 Monitoring Instrumentation

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5-6 5.4 Emergency Kits ................................................................................

5-8 5.5 Respiratory Protection

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5-9 5.6 Protective Clothing ...........................................................................

5-9 5.7 Radioprotective Drugs ......................................................................

5-9 Figure 5-1, Facility Functional Objectives

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5-10 Figure 5-2, Emergency Operations Facility ..................................................

5-12 Figure 5-3, Emergency Operations Facility and Joint Information Center Location .........................................................................

5-13 Figure 5-4, TSC Location Relative to Control Room ....................................

5-14 Figure 5-5, Characteristics of Technical Support Center vs. Control Room and Operational Support Center ........................

5-15 Figure 5-6, Public Information Flow .............................................................

5-16 Section 6: 6.1 6.2. 6.3 6.4 6.5 6.6 Maintaining Preparedness

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6-1 Training .......................... , .....................................................................

6-1 Exercises and Drills ..........................................................................

6-2 Program Responsibility

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6-2 Equipment Inventory and Maintenance

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6-2 Program Review and Update ................................................................

6-3 Records ...........................................................................

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6-4 Section 7: Definitions and Acronyms .......................................................................

7-1 7.1 Abbreviations

& Acronyms ................................................................... 7.2 Definitions

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7-2 Section 8: References

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8-1 APPENDICES

1. NUREG-0654 Evaluation Criteria Cross Reference

2. Letters of Agreement

3. Emergency Plan Implementing Procedures

4. Emergency Response Organization Responsibilities

5. Liquefied Natural Gas Contingency

6. Calvert Cliffs Communications Equipment June 2016 iii EP-AA-1011 (Revision

1)

Calvert Cliffs Annex CALVERT CLIFFS NUCLEAR POWER PLANT EMERGENCY PLAN Section 1: Introduction Exelon Nuclear As required in the conditions*

set forth by the Nuclear Regulatory Commission (NRC) for the operating licenses for the Exelon Nuclear Stations, the management of Exelon recognizes its responsibility and authority to operate and maintain the nuclear power stations in such a manner as to provide for the safety of the general public. The Exelon _ Emergency Preparedness Program consists of the Exelon Nuclear Standardized Radiological Emergency Plan, Station Annexes, emergency plan implementing procedures, and associated program administrative documents.

The Exelon Nuclear Standardized Radiological Emergency Plan outlines the basis for response actions that would be implemented in an emergency.

Planning efforts common to all Exelon Nuclear stations are encompassed within the Emergency Plan. This document serves as the Radiological Emergency Plan Annex for Calvert Cliffs Station and contains information and guidance that is unique to the station. This includes facility geography and location for a full understanding and representation of the station's emergency response capabilities.

The Station Annex is subject to the same review and audit requirements as the Exelon Nuclear Standardized Radiological Emergency Plan per EP-AA-120, "Emergency Plan Administration".

1 .1 Site Description Calvert Cliffs Nuclear Power Plant is. a fixed nuclear facility located in Lusby, Maryland.

It is owned and operated by Exelon Generation.

The site consists of two units. Each unit includes a two loop pressurized water reactor. The reactors are designed for a gross electrical output of approximately 91 O MWE. Cooling water is supplied by the Chesapeake Bay. The site contains an Independent Spent Fuel Storage Installation (ISFSI). The ISFSI is a life-of-plant storage facility for spent nuclear fuel assemblies discharged from Calvert Cliffs Units 1 and 2. 1.2 Purpose The Emergency Preparedness program for the Calvert Cliffs Nuclear Power Plant consists of the Exelon Nuclear Standardized Radiological Emergency Plan, Calvert Cliffs Station Annex, off-site radiological emergency plans, and procedures for protection of plant personnel and the general public. This program helps provide dose savings for a spectrum of accidents.

Some of these. accidents could produce off-site dose in excess of the Environmental Protection

• Agency's Protective Action Guides. The Calvert Cliffs Emergency Plan and June 2016 cc 1-1 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear Maryland State Radiological Emergency Plan ensure the following are achieved:

• Effective coordination of activities among response organizations.

• Early warning and instructions for the population-at-risk.

• Continuous assessment of on-site and off-site actual or potential consequences.

• Effective emergency measures implementation.

• Continuous emergency preparedness maintenance.

1.3 Concept

1.3.1

• Calvert Cliffs Nuclear Power Plant Emergency Plan has been developed to protect the general public and site personnel from possible consequences of emergency conditions.

Combined with its implementation procedures and radiological emergency plans of the State and local agencies, the Emergency Plan allows for:

• Early emergency condition recognition and classification.

• Prompt notification of agencies via reliable communication channels and personnel to augment the normal operating personnel.

• Prompt pre-planned protective actions for protecting the population-at-risk.

1 .3.2 Calvert Cliffs Nuclear Power Plant is staffed with personnel trained to respond to emergencies, Additionally, written agreements are maintained with federal agencies, private contractors, and State and local agencies that are required by law to provide assistance to ensure resources can be readily available in as short a time as possible to cope with emergencies and to protect the population-at-risk.

The agencies and reso1,Jrces provided are described in:

• Exelon Nuclear Standardized Radiological Emergency Plan

• Calvert Cliffs Nuclear Power Plant Radiological Emergency Plan Annex

• Maryland Core Emergency Operations Plan -Fixed Nuclear Facilities (FNF) Appendix (Formerly Annex Q) to Radiological Incident Annex

• Calvert County, Dorchester County, and St. Mary's County Radiological Emergency Plans and Standard Operating Procedures

• Virginia, Radiological Emergency Response Plan

• Delaware, Radiological Emergency Plan.

• District of Columbia, District Response Plan. Maryland Core Emergency Operations Plan, describes State and local agency roles and interfaces for carrying out protective and parallel actions in a radius plume zone and 50-mile-radius ingestion zone from Calvert Cliffs Nuclear Power Figure 1-1, Emergency Planning Zone, and Figure .1-2, 10-Mile June 2016 *CC 1-2 EP-AA-1011 (Revision

1)

. / Calvert Cliffs Annex Exelon Nuclear Emergency Planning Zone Boundary, shows the geographical area within the plume and ingestion zones . 1.3.3. Documents used in developing the Emergency Plan and implementation procedures are listed in Section 8, Calvert Cliffs Nuclear Power Plant Emergency Plan References.

1.4 Emergency

Response Documents

1.4.1 Emergency

Plan (Standard Plan ,Station Annex and Addendums)

The Emergency Plan ensures that emergency situations, including . those involving radiation or radioactive material, are handled properly and efficiently.

The Emergency Plan covers a spectrum of emergencies from minor localized emergencies to major emergencies involving off-site emergency response.

The Emergency Plan provides for advance planning required to develop implementation methods. The Emergency Plan describes:*

1. An emergency classification system used at the plant and emergency measures to be taken that are compatible with those used by Federal, State and county emergency response agencies and organizations.

2. Organizational control . of emergencies by on-site, off-site, and augmentation organizations, including identification of normal and emergency operating organizations.

3. Identification of Federal,*

State, and County authorities and agencies and other outside organizations that are available for assistance, including plans and agreements pertaining to participating off-site organizations and agencies.

• 4. Requirements for ensuring a high degree of emergency preparedness and operational readiness such as through training, drills, reviews, and au.dits. 5. Information pertaining to on-site and off-site emergency facilities and equipment such as the Emergency Operations Facility, Technical Support Center, Operational Support Center, and Joint Information Center. 6. Figures and tables that display information and data such as organizations, maps, and population distributions.

1.4.2 Emergency

Plan Implementation Procedures Emergency Plan Implementation Procedures are used in conjunction plant operating, chemistry, radiological control, security, and other technical procedures, as appropriate, to respond to emergency conditions and mitigate accident consequences.

These documents are made available to those individuals, facilities, and June 2016 cc 1-3 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear organizations where immediate use of such instructions would be required during an emergency.

These documents provide: 1. Specific instructions for emergency organizations including responsibilities, facilities, equipment, emergency classification, and seeking emergency assistance used to implement the Emergency Plan and support implementation of the State Radiological Emergency Response Plan. 2. Specific authorities and responsibilities for emergency response personnel responsible for assessing emergency conditions and providing steps to be taken to mitigate the consequences of an accident.

3. Specific instructions to ensure-prompt actions, notifications, and communications.

4. A record of completed actions. 5. A mechanism for maintaining emergency preparedness.

Emergency Plan Implementation Procedures are developed to respond to a variety of . accident scenarios.

These include minor events up to core melt situations with unplanned radioactive material release to the environment.

While the emergency level(s) listed in the procedures is sufficient to cause their implementation, it is not necessary to implement all Emergency Plan Implementation Procedures under these conditions.

Specific procedures may not be used if the actual emergency does not call for their use. For example: a security threat may not result in plant damage and an unplanned release; therefore, radiological monitoring procedures may not be used. The following types* of documents include the Emergency Plan Implementation Procedures:

• Fleet EP Procedures and T&HMs (Training and Reference Materials)

• Station/Region EP.procedures and T&RMs

• Position Specific Checklists and Forms June 2016 cc 1-4 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex = I I I I 1 ? I 1 1 '-* :r ) ... June 2016 Figure 1-1 EMERGENCY PLANNING ZONE cc 1-5 f .._ ""'0 r I ,/ Exelon Nuclear ' * \. E P-AA-1011 (Revision 1 )

Calvert Cliffs Annex ,, --.... /. 111 *' l -w June 20 1 6 Exelon Nuclear Figure 1-2 10-MILE EMERGENCY PLANNING ZONE BOUNDARY

• l!M , f ii cc 1-6 AR E Zoto.EE E D ZOHEC ....... '--,_ _ ...... o---41'-o..

-_.._... !.... _........., ,..._....,_c-, .........

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• t UI I u , *-EP-AA-1011 (Rev i s i on 1)

Calvert Cliffs Annex Exelon Nuclear Section 2: Organizational Control of Emergencies This section describes the Exelon Emergency Response Organization (ERO) at Calvert Cliffs, its key positions and associated responsibilities.

It outlines the staffing requirements which provide initial emergency response actions and provisions for timely augmentation of on-shift personnel when required.

It also describes interfaces among emergency response personnel and specifies the offsite support available to respond to the nuclear generating stations.

2.1 Operating

Organization The first line of control of any emergency at Calvert Cliffs Nuclear Power Plant lies with the normal shift personnel on duty at such time as an emergency situation should occur. Assistance is available within one hour from other plant staff and operating personnel.

Additional assistance is available from Exelon Generation, Federal, and State agencies and contractor personnel.

Corporate Headquarters supports the ERO in the following functional areas: Corporate Communications is able to field rumor control issues while providing feedback to the Joint Information Center representatives.

Additionally, Headquarters aligned personnel assigned to CCNPP are considered available for assignment to the ERO if their duties do not include extended travel and they have the approval of their corporate sponsor. Emergency positions are staffed so relations to responsibilities and duties of the normal staff complement are essentially unchanged.

Operafing Organization personnel resources provide *the means for* continuous (24-hour) plant operations, including manning of communications links. 2.2 Standing Review Committees Two committees are established in the Updated Final Safety Analysis Report, Section 12.5, Review and Audit of Operations, to ensure adequate review of matters pertaining to nuclear plant safety and integrity.

The Plant Operations Review Committee functions iri an advisory*

capacity to the Plant General Manager-Calvert Cliffs Nuclear Power Plant. The Nuclear Safety Review Board is an independent review organization functioning in an advisory capacity to the Chief Nuclear Officer. Membership and specific responsibilities of the Plant Operations Review Commjttee and Nuclear Safety Review Board are detailed in Fleet procedures.

2.3 Emergency

Organization Emergency Preparedness Unit maintains a list of personnel assigned as primary and alternates to emergency positions.

Emergency titles apply to interim, alternate, and primary candidates alike. The first person assuming an emergency position retains title, authority, and responsibilities until relieved.

Figure 2-1, Minimum On-Site Staffing Requirements, lists the minimum on-site staffing.

The following attachments show Emergency Organization relationships:

June 2016 cc 2-1 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear

• Figure 2-2, Emergency Response Organization

• Figure 2-3, Recovery Organizations

• Figure 2-4, Center Interface:

Unusual Event

• Figure 2-5, Center Interface:

Alert, Site Area and General Emergency Description of ERO positions are contained in Appendix 4. For Calvert Cliffs, the ERO position descriptions within the Annex supersede descriptions contained in the Standard Plan. 2.3.1 Shift Manager The Shift Manager has authority and responsibility for reactor plant manipulations including implementation of normal, abnormal, and emergency procedures.

The Shift Manager will perform the duties of the Shift Emergency Director.

Emergency Director non-delegable duties are transferred in time to another qualified individual.

After transferring the non-delegable duties, the Shift Emergency Director reports to the Operations Manager in the TSC. Direct reports to the Shift Manager are the:

• Shift Operations Personnel Perform plant operations functions from the* Control Room and in the plant.

• Shift Technical Advisor: The Shift Technical Advisor assists the Shift Manager by making recommendations pertaining to plant safety, operations, accident assessment, and procedures.

• First Aid Responders:

Nuclear Plant Operations, under the supervision of the Shift Manager, provides first aid medical services to injured persons.

• Fire Brigade Responders:

Nuclear Plant Operations, under the supervision of the Shift Manager, provides firefighting services to the site. 2.3.2 Emergency Director (Shift I Corporate)

The Shift Emergency Director has the authority and responsibility to manage and direct the emergency response and serves as the main contact at the site. In addition to directing staff and operations personnel, he or she can cal! on additional Company and outside agencies assistance as needed. Additional staff will be called upon to support overall operations of the Emergency Operations Facility and may include additional personnel to support administrative, accountability, media control, etc. Emergency Director responsibilities, include but are not limited to, emergency classification; immediate and unilateral initiation

• of emergency actions, including making June 2016 CC2-2 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear . notifications and providing protective action recommendations to authorities responsible for implementing off-site emergency measures; and requesting Federal assistance.

The Emergency Director has primary responsibility for interface with agenCies having responsibilities to ensure the protection of the population-at-risk within the Calvert Cliffs Nuclear Power Plant emergency planning zones. The decision to notify and make off-site protective action recommendations to off-site authorities may not be delegated.

The Emergency Director is also responsible for on-site protective actions and reentry operations.

The Shift Manager (staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) assumes the Shift Emergency Director duties at the onset of an emergency and retains it until certain duties are relieved by augmenting personnel.

When physically present and updated on plant conditions, another qualified Shift Emergency Director from the operations department may relieve the Shift Manager until responsibilities are transferred to an individual assigned to the Corporate Emergency Director position as their primary responsibility.

In accordance with the Calvert Cliffs Emergency Plan, the TSC Station Emergency Director does not take Command and Control responsibilities.

Transfer of authority and responsibility is by voice acknowledgment of relieving party. 2.4 Recoverv Organization Once plant conditions have been stabilized and the Recovery Phase has been initiated, the Corporate Emergency Director may form a Recovery Organization for long-term operations.

These types of alterations will be discussed with the NRC prior to implementation.

• For events of a minor nature, (i.e. for Unusual Event classifications) the normal on shift organization is normally adequate to perform necessary recovery actions.

• For events where damage to the plant has been significant, but no off-site releases have occurred and/or protective actions were not performed, (i.e. for Alert classifications) the station Emergency Response Organization, or portions thereof, should be adequate to perform the recovery tasks prior to returning to the normal station organization.

• For events involving major damage to systems required to maintain safe shutdown of the plant and off-site radioactive releases have occurred, (i.e. for Site Area Emergency or General Emergency classifications) the station recovery organization is put in place. The specific members of the station 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 station recovery organization is as follows: *June 2016 cc 2-3 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear 2.4.1 The Recoverv Manager: The Corporate Emergency Director is initially designated as the Recovery Manager. The Recovery Manager is charged with the responsibility for directing the activities of the station recovery organization.

These responsibilities include:

• Ensuring that sufficient personnel, equipment, or other resources from Exelon Generation and other organizations are available to support recovery.

• Directing the development of a recovery plan and procedures.

• Deactivating any of the plant Emergency Response Organization which was retained to aid in recovery, in the appropriate manner. Depending upon the type of accident and the on., site and off.,site affects of the accident, portions of the ERO may remain in place after initiation of the recovery phase.

• Coordinating the integration of available federal and state assistance into . on.,site recovery activities.

• the integration of Exelon Generation support with federal, state and county authorities into required off-site recovery activities.

• Approving information released by the public information organization which pertains to the emergency or the recovery phase of the accident.

• Determining when the recovery phase is terminated.

2.4.2 The Station Emergency Director:

The Station Manager or a designated alternate will become the Recovery Station Emergency Director.

The Station Emergency Director reports to the Recovery Manager and is responsible for:

• Coordinating the development and implementation of the recovery plan and procedures.

• Ensuring that ,adequate engineering activities to restore the plant, are properly reviewed and approved.

• Directing all on-site activities in support of the station recovery effort.

• Designating.

other Exelon Generation recovery positions required in support of on-site recovery activities.

2.4.3 The EOF Director:

A senior Emergency Preparedness or Regulatory Affairs individual, or a designated alternate, is the Recovery EOF Director.

The EOF Director reports to the Recovery Manager and is responsible for:

• Providing liaison with off-site agencies and coordinating Exelon Generation assistance for off-site recovery activities.

• Coordinating Exelon Generation ingestion exposure pathway EPZ sampling activities and the development of an off-site accident analysis report.

• Developing a radiological release report.

• Designating other Exelon Generation recovery positions required in support of off-site recovery activities.

June 2016 CC2-4 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear 2.4.4 The JIC Manager: Continues to direct JIC activities to provide information to the public through the media as needed during the recovery phase. The JIC Manager is responsible for: *

• Coordinating non-Exelon Generation public information groups (federal, state, county, etc.).

• Coordinating media monitoring and rumor control.

• Determining what public information portions of the ERO will remain activated.

2.4.5 The Company Spokesperson:

A senior Exelon Generation management individual is designated as the Company Spokesperson.

The Company Spokesperson reports to the Recovery Manager and is responsible for:

• Functioning as the official spokesperson to the press for Exelon Generation on all matters relating to the accident or recovery.

The remainder of the 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 station organizations.

Individual recovery supervisors may be designated in any or all of the following areas:

• Training

• Radiation Protection

• Chemistry

• Technical/Engineering Support

• Nuclear Oversight

• Operations

• Security

• Maintenance

• Special Off-site Areas (Community Representatives, Environmental Samples, Investigations, , etc 2.5 Contracted Services 2.5.1 Contractors Contractors and private organizations .may be requested to provide assistance to and augmentation of the emergency organization.

Assisting groups may include the NSSS supplier, plant Architect-Engineer or any industry support company. These support services are outlined in memorandums of agreement in Appendix 2 and include support for Fire and Rescue, Ambulance Services, Medical Services to include Physicians, Nuclear Incident Training, Nuclear Emergency Consulting and Technical Assistance, Earthquake confirmation; Disaster planning memorandums between local utilities.

Specific contractors are dependent on emergency situation needs and are described in associated Emergency Plan Implementing Procedures.

June 2016 cc 2-5 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear 2.6 Local Services Appendix 2, Letters of Agreement, contains written agreements identifying services provided by local agencies for handling emergencies, (e.g., medical, hospital, local law enforcement, and fire fighting organizations).

Agreement letters identify authorities, responsibilities, and limits on the actions of the *respective agency. 2.6.1 Local Law Enforcement A Letter of Agreement is established for Local Law Enforcement to support Calvert Cliffs Power Plant to respond to a Radiological Event, including a Hostile Action Based Event, in conjunction with the National Incident Management System (NIMS) upon notification by the station in accordance with the established communications protocol.

2.6,2 Medical Facilities The Calvert Memorial Hospital and MedStar St. Mary's Hospital agree in the event of a Radiological Event, including a hostile action based event, to ensure the capability for the evaluation of radiation exposure and uptake, including assurance that persons providing these services are adequately prepared to handle contaminated individuals and capable of providing medical support for any contaminated injured individual.

2.6.3 Fire Fighting Services (. -'* A Letter of Agreement is established for the Local Fire Department to respond to a Radiological Event, including a Hostile Action Based Event, in conjunction with the Mutual Aid Box Alarm System (MABAS). 2.6.4 EMS. Support A letter of Agreement is established for the local ambulatory services to provide Emergency Medical Services in response to a Radiological . Event, including a Hostile Action Based Event. This includes transportation of patients from the Calvert Cliffs Power Plant, including those who may have been exposed to radiation or may have injuries complicated by radioactive contamination, to Calvert Memorial Hospital or to MedStar St. Mary's Hospital upon request through established protocols.

2.7 Participating

Governmental Agencies Functions performed by Federal, State, and county agencies are summarized in the following subsections.

Appendix 2, Letters of Agreement, contains written agreements identifying services provided by Federal, State, and county agencies.

Detailed information is contained in: June 2016

• Maryland Core Emergency Operations Plan -Fixed Nuclear Facilities (FNF) Appendix (Formerly Annex Q), Radiological Emergency Plan CC2-7 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear

• Calvert County, Dorchester County, and St. Mary's County Radiological Emergency Plans and Standard Operating Procedures.

• Virginia Radiological Emergency Response Plan

• Delaware Radiological Emergency Plan

• District of Columbia, District Response Plan 2. 7 .1 State of Maryland The Maryland Core Emergency Operations Plan is the official State plan for responding to radiological emergencies.

State officials and agencies identified in the Plan having overall command, coordination, key, and support responsibilities include: 1 . The Governor 2. Maryland Emergency Agency (MEMA) 3. Department of Health and Mental Hygiene 4. Maryland Department of Agriculture

5. Maryland Department of Environment

6. Department of Natural Resources

7. Maryland State Police 8. Department of Human Resources

9. Department of Transportation

10. Maryland State Department of Education

11. Department of Housing and Community Development

12. Maryland Military Department/National Guard 13. Maryland Institute for Emergency Medical Services System 14. Office of the Comptroller of the Treasury 15. Office of the State Fire Marshal 2.7.2 Functions and Responsibilities of Key Agencies and Officials June 2016 1 . The Secretary

-Maryland Department of the Environment has the authority of the Governor and maintains responsibility for overall command of an emergency response.

Major areas of action under his/her command include: a. Accident assessment

b. Notification and communication

c. Command and coordination

d. Protective actions 1) Evacuation

2) Ingestion of Potassium Iodide or thyroid protection cc 2-8 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear June 2016 3) Take shelter 4) Access control 5) Food, water, and milk control e. Parallel actions 1) Emergency medical services 2) Radiation exposure .control 3) Law enforcement and crime prevention

4) Mass Care 5) Re-entry 6) Return 7) Relocation t Public Information

2. The MEMA coordinates State, private, and Federal agency response to and from CCNPP to aid County emergency operations.

The MEMA directs County requests for assistance to appropriate State and Federal agencies.

3. The State Department bf Environment makes available resources and personnel to perform the following:

' --' ' a. Provide technical information to the Secretary-Department of the Environme-nt.

• b. Dispatch field monitoring teams to emergency area(s). c. Set up headquarters for direction of activities by the State Radiological Health Administrator at the Accident Assessment Center in the near site Emergency Operations Facility.

d. Determine when assistance is required from the Federal Department of Energy and request such assistance.

e. Determine when protective actions for the public are required and inform State and local authorities.

f. Provide guidance in establishing public restricted areas. g. Provide contamination control guides. h. Request outside radiological monitoring-assistance when needed. L Provide guidance for external human and animal decontamination.

j. Provide guidance for facilities, equipment, and area decontamination.

• k. Provide guidance to the State Departments of Agriculture and Health and Mental Hygiene for controlling the use of milk and agricultural products.

cc 2-9-EP-AA-1011 (Revision

1)

,_,,--' Calvert Cliffs Annex Exelon Nuclear I. Determine and notify appropriate authorities when people may return to evacuated areas. m. Provide direction of Ingestion Pathway Coordinating Committee activities.

4. The State Department of Health and Mental Hygiene makes available resources and personnel to perform the following:

a. Dispatch agricultural sampling teams to effected areas. b. Provide guidance to the State Department of Agriculture for controlling the use of milk and agricultural products.

c. Provide laboratory analysis of field samples. d. Support Ingestion Pathway Coordination Committee activities.

5. The Maryland State Police render assistance as follows: a. b. c. d. e. f. g. Establish off-site command post in vicinity of the plant site. Evacuate and exclude individuals from designated public and private areas. Control traffic into and out of designated areas. Transport Maryland Department of Environment Monitoring T earns on request. Assist in medical evacuation via helicopter.

Aid in emergency communications.

Coordinate with County Sheriffs to assist in communications, evacuations, and traffic control. 6. The Maryland Department of Natural Resources Police Force and the Fisheries Service render assistance as follows: a. Evacuate and prevent entry to designated water areas. b. Aid in emergency communications.

c. Assist in radiological monitoring.

d. Assist in waterborne population evacuation as required.

7. The Maryland Emergency Management Agency Public Information Officer is responsible for co9rdination of State and local information releases.

The Public Information Officer coordinates with Calvert Cliffs Nuclear Power Plant's Joint Information Center Director to prevent conflicting statements between State/local and Calvert Cliffs Nuclear Power Plant's spokespersons.

2.7.3 Planning

Zone Support 1. Plume Exposure Emergency Planning Zone Calvert County, Dorchester County, and St. Mary's County Radiological June 2016 cc 2-10 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear Emergency Plans and Standard Operating Procedures summarize the plan used by county agencies within the Plume Exposure Emergency Planning Zone. Command of county agencies is under the direction of the Board of County Commissioners, or County Council for each county. Coordination and responsibility for 'implementing protective actions is the responsibility of the Director of each county's Emergency Management Agency. 2. Ingestion Emergency Planning Zone June 2016 a. Maryland The ingestion EPZ for CCNPP includes all or portions of thirteen Maryland counties.

• Anne Arundel County

• Calvert County

• Caroline County

• Charles County

• Dorchester County

• Kent County

• Prince George's County

• Queen Anne's County

• Somerset County

• St. Mary's.County

• . Talbot County

• Wicomico County

• Worcester County Functions and responsibilities of agencies responsible for emergency response are described in the Maryland Emergency Operations Plan, Annex Q, and Radiological Emergency Plan. b. Commonwealth of Virginia The ingestion EPZ for CCNPP includes all or portions of the following Virginia political subdivisions:

Counties . Accomack (Tangier Island) Arlington

• Caroline Essex Fairfax King George King and Queen Lancaster Middlesex Northumberland Prince William Richmond Stafford Westmoreland Cities Alexandria Falls Church Functions and activities of these agencies are described in the Virginia cc 2-11 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear Radiological Emergency Response Plan. c. State of Delaware Functions and activities of 'agencies responsible for emergency response in the Delaware portion of the ingestion EPZ are described in the Delaware Radiological Emergency Pl.ah and Implementing Procedures.

d. District of Columbia Functions and activities of agencies responsible for emergency response in the Washington, D.C., portion of the ingestion EPZ are described in the District of Columbia, District Response Plan. 2.7.4 Support From Federal Agencies Calvert Cliffs Nuclear Power Plant is located about 70 miles south of Baltimore and 50 miles southeast of Washington, D.C. The site_ is less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> driving time from either city or their respective airports (Baltimore-Washington International; Ronald Reagan National). . A helicopter landing can be accommodated at Calvert Cliffs Nuclear Power Plant and the Emergency Operations Facility.

Emergency facilities have been designed to meet the space and communications needs of a small scale Federal response.

Federal Radiological Emergency Response Plan implementation may require the use of Andrews Air Force Base and/or Federal, State or local facilities to accommodate the large volume of associated personnel.

June 2016 cc 2-12 EP-AA-1011 (Revision

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Calvert Cliffs Annex MAJOR FUNCTIONAL AREA Plant operations and assessment of operational aspects Emergency direction and control (c) Notification/

communication Support of operational accident assessment Radiological accident assessment Plant System Engineering, repair and corrective actions Protective actions (in/plant) operational aspects Firefighting June 2016. Figure 2-1 MINIMUM ON-SITE STAFFING REQUIREMENTS Page 1 of 2 POSITION, TITLE, MAJOR TASKS OR EXPERTISE Senior Reactor Operator Reactor Operators Auxiliary Operators Shift Technical Advisor Ops Technical Assistant Shift Manager Corporate Emeraencv Director Notify licensee, Federal, Shift Communicator State, and local personnel and State/Local Communicator , maintain communications ENS Communicator Site emergency coordination Station Emergency Director a. Off-site dose assessment EOF Radiation Protection Manager (RPM) b. Off-site surveys OMT Team Members c. On-site surveys RP Tech d. In-plant surveys RP Tech e. Chemistry/radio"chemistry Chemistry Technicians Technical support Core I Thermal Hydraulic Engineer Electrical Engineer Mechanical Engineer Repair and corrective actions OSC Director Mechanical maintenance Rad Waste Operator Electrical maintenance Instrument and Control (l&C) Technician Assistant OSC Director Radiation protection:

a. Access control RP Tech b. HP coverage for repair, TSC Rad. Protection corrective actions, search Manager and rescue first-aid and RP Lead firefighting

c. Personnel monitoring

d. Dosimetry Fire Brigade personnel cc 2-13 Exelon Nuclear WITHIN (a) APPROX. ON SHIFT 60 MINUTES 2 --4 5 1 PerUFSAR 1 1 1 1 1 --1 --1 --4 --2 1 2 1 1 --2 __ , 1 --1 1 --3 1(b) ----2 --2 1 1 4 1 1 8-fft Local Support (d) EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear MAJOR FIGURE 2-1 MINIMUM ON-SITE STAFFING REQUIREMENTS Page 2 of 2 POSITION, TITLE, MAJOR TASKS OR EXPERTISE ON SHIFT FUNCTIONAL AREA Rescue operations First Aid Team personnel 2(e) and first aid Site access control and Security, communications, Security personnel per Security personnel accountability personnel accountability Plan Notes: (a) Additions required for Alert, Site Area Emergency and General Emergency. (b) Provided by shift personnel assigned other functions. (c) Overall direction of facility response to be assumed by the person assigned to the Emergency Director position as primary responsibility when all centers are fully manned. Direction of minute-to-minute facility operations remains with the Station Emergency Director in the Technical Support Center. (d) Additions within approximately 30 minutes. (e) Rescue operations and first aid is a collateral duty of the designated Fire Brigade (Fire & Safety Watch and Fire & Safety Responder) (f) Per the Calvert Cliffs UFSAR, the fire brigade leader and at least two fire brigade members must have sufficient training and knowledge of nuc!Bar safety systems te understand the effects of fire and fire suppression on nuclear safety performance criteria.

lf the Fire Brigade does not meet this requirement, the sufficient training and knowledge is permitted to be provided by an additional Operations Technfca!

dedicated to respond with the fire brigade. WITHIN (a) APPROX. 60 MINUTES Local Support (d) --June 2016 cc 2-14 (Revision

1)

Calvert Cliffs Annex June 2016 I EOF Director Off-site ERO Interface with Off-site Response Organizations (Federal, State and Local) to coordinate Protective Actions for the public FIGURE 2-2 Emergency Response Organjzation Emergency Director Station Emergency Director On-site ERO On-site (OCA) Protective Response and Mitigative Actions cc 2-15 Exelon Nuclear I JIC Manager Public Information ERO Provides information to the Public through the News Media, addresses phone inquiries , conducts Rumor Control operations.

EP-AA-1011 (Revision

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Calvert Cli ff s Annex Exelon Nuclear FIGURE 2-2 Emergency Response Oraanjzation Statio n Eme r gency Di rect o r TSC Direct o r -TSC ---RM S Co m m. Ad min Staff .. .. -.. I I I I Techn i ca l Ma i n t enance Manager I TSC Rad P rotection Secu r ity Manager O p erations Manager Manager Coor d i na t o r I .j --* ---I -. I I I (CAS) (Control Room) (O SC) (O SC) -Electrical Engineer -L

• L

• Security S hi ft Shift Manager OSC D irector RP L ea d Su p e rvi s o r -------Mechanical ENS Comm"";"to 1 Sec ur it y F o re -Engineer --e Core Thermal I -Hydraulic

-TSC Ops Engineer (2) I Co m municator I I ...... TS C/O SC Computer I Sp e cialist -CR Op s Communic ato r Jun e 20 16 c c 2-16 E P-AA-1011 (Rev i s i on 1)

Calvert Cliffs Annex I I Electrical l&C Group Lead Group Lead Electrical l&C --Techs Techs June 2016 FIGURE 2-2 Emeraency Response Organization

.... OSCAdmin Staff I osc Directo r -... Exelon Nuclear -I Assistant OSC OSC Team OSC Ops Director Tracker Communicator I I I I I Mechanical I RP OSC Chem Ops I Group Lead i Group Lead Group L ead Group Lead j ---Mechanical RP Chem Operators

---

Techs Techs Techs ----cc 2-17 EP-AA-1011(Rev i sion1)

Calvert Cliffs Annex I EOF Technical Advisor -EOF Ops Communicator June 2016 -FIGURE 2-2 Emeraency Response Orqanizatjon EOF Director State/Local Communicator i I EOF Logistics Manager EOF/JIC Computer Specialist I EOC Communicator

-State Liaison ,___ EOF Admin Staff -County Liaison(s) cc 2-18 HPN Communicator I Dose Assessor Exelon Nuclear EOF Rad Protection Manager -I Environmental Coordinator

---

Off site -Mon. Team Members -EP-AA-1011 (Revision

1) -

Calvert Cliffs Annex June 2016 FIGURE 2-2 Emergency Response Organjzation JIC Manager ; Company i .... Spokesperson j I MM/RC Coordinator

-Inquiry Phone JIC -Admin Staff Team Media Media Liaison ---Monitoring Team JIC Security cc 2-19 Exelon Nuclear ! JIC Logisitics I Manager I _J ---News Writer -------JIC Technical Advisor -EP-AA-1011 (Revision

1)

Calvert Cliffs Annex I Station ED On-site Recovery Interfaces between normal on-site organizations and the Recovery Organization.

FIGURE 2-3 Recoyerv Orqanjzatjon Recovery Manager EOF Director Off-site Recovery Assist Off-site Agencies with recovery activities.

Oversees off-site radiological assessment activities.

\.. \.. Exelon Nuclear I JIC Manager Company Spokesperson Public Information Coordinates release of Recovery Phase information to the public through media. Support positio n s w i ll be assigned to each area manager as needed based on the even t. June 2016 cc 2-20 EP-AA-1011 (Revis i on 1)

. Calvert Cliffs Annex Exelon Nuclear * ** June 2016 FIGURE 2-4 Center Interfaces:

Unusual Event Control Room Shift Emergency Director Calvert County Technical Support Center* -Emergency Operations Center** . Station Emergency Director -----------

---

Emergency Management . Director St. Mary's County Emergency Operations Center Emergency Management Director Dorchester County Center I Facility Emergency Operations Center Emergency Management Organizational Title at end of Director communications link. May be accesses directly or through communicators.

Accident Assessment Center MDEManager Emergency Operations Maryland Emergency Management Agency (MEMA) Emergency Management Director If TSC is staffed at Unusual Event to support Control Room Interface with local agencies (e.g., police, fire, rescue, hospital) is through Calvert County Emergency Operations Center. cc 2-21 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear June 2016 FIGURE 2-5 Center Interfaces:

Alert. Site Area and General Emergencies EOF -Corp Emergency Director Joint Information Center EOF Director JICManager Calvert County Emergency Operations Center Emergency Management Director i Control Room Local Offices Shift Emergency Director and Agencies

• St. Mary's County Technical Support Center -Emergency Operations Center Station Emergency Director Emergency Management Director ; i Operations Support Center Local Offices OSC Director and Agencies Dorchester County NRC Emergency Operations Center -NRR Emergency Management Director ; NRC

• Federal Offices and Agencies Region Local Offices and Agencies Maryland Emergency Accident Assessment Center Management Agency (MEMA) orEOF Emergency Management MDEManager Director Emergency Operations State Offices ,_______ Center I Facility . and Agencies Organizational Title at end of DC, Delaware communications link. and Virginia -May be accesses directly or through communicators.

cc 2-22 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Section 3: Classification of Emergencies

3.1 Classification

System

• Emergency classifications are: 1. Unusual Event 2. Alert 3. Site Area Emergency

4. General Emergency Each classification requires immediate action to classify the accident, notify site agen'cies and support groups, and mobilize emergency organizations as required to cope with the emergency.

Accidents are classified and reclassified (more and less severe) as situations warrant. Unusual Event and Alert classifications provide early notification of minor events and ensure timely response for more severe emergencies.

Assembly of Calvert Cliffs Emergency Response Organization is initiated for an Alert classification.

Full mobilization of emergency personnel and organizations is initiated for Site Area and General Emergency . . Each emergency classification is characterized*

by Emergency Action Levels consisting of specific plant parameters or conditions.

The Emergency Action Level scheme is consistent with R.G. 1.101, Emergency Planning and Preparedness for Nuclear Power Reactors, Revision 4, July, 2003, as modified by CCNPP, Inc., submittals to the NRC. Satisfying Emergency Action Level criteria other than a General Emergency does not necessitate immediate protective action, Implementation; it ensures time is available to confirm in-plant readings by implementing assessment measures on-site and off-site.

Classification philosophy is to declare the highest class emergency for Emergency.

Action Levels met or exceeded.

For example, a Site Area Emergency would be declared immediately, if the Emergency Action Level is met or exceeded, lower classes will not be declared first. 3.2 Unusual Event 3.2.1 Description Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection.

No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs. 3.2.2 Emergency Action Levels Initiating conditions established as Emergency Action Levels for determining an Unusual Event classification are listed in EP-AA-1011, Addendum 3. An Unusual Event is declared any time that respective Emergency Action Levels are met or *exceeded.

All minor events are analyzed in light of their potential for degrading the level of plant safety. June 2016 cc 3-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 3.3 Alert 3.3.1 Description Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site* equipment because of hostile action. Any releases are expected to be limited to _ small fractions of the EPA Protective Action Guideline exposure levels. Alert classification ensures personnel are available to: A. Respond to worsening situations.

B. Perform confirmatory radiation monitoring.

c. Provide off-site authorities with information.

3.3.2 Emergency

Action Levels Initiating conditions established as Emergency Action Levels for determining an Alert emergency classification are listed in EP-AA-1011, Addendum 3. An Alert is declared any time that respective Emergency Action Levels are met or exceeded.

3.4 Site Area Emergency

3.4.1 Description

Events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or hostile action that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.

Site Area Emergency classification ensures: 1. Response centers are manned .. 2. Survey teams are dispatched.

3. Personnel required for near site evacuation are at their duty stations.

4. The public is updated through off-site authorities.

_3.4.2 Emergency Action Levels f nitiating conditions established as Emergency Action Levels for determining Site Area Emergency classification are listed in EP-AA-1011, Addendum 3. A Site Area Emergency is declared any time that respective Emergency Action Levels are met or exceeded.

-June 2016 cc 3-2 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 3.5 General Emergency A. Description Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or hostile action that results in an actual loss of physical control of the facility.

Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels off-site for more than the immediate site area. General Emergency classification ensures: 1. Initiation of predetermined warning and protective actions for the public. 2. Continuous plant information and off-site measurement assessment.

3. Initiation of additional measures as indicated by . actual or potential releases.

4. Consultation with off-site authorities.

5. Public updates through off-site authorities.

B. Emergency Action Levels June 2016 Initiating conditions established as Emergency Action Levels for determining General Emergency are listed in EP-AA-1011, Addendum 3. A General Emergency is declared any time that a respective Emergency Action Level is met or exceeded.

cc 3-3 (Revision

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Calvert Cliffs Annex Exelon Nuclear Section 4: Emergency Measures 4.1 Recognition and Classification Calvert Cliffs Nuclear Power Plant staff recognizes and responds to off-normal plant conditions.

Abnormal and Emergency Operating Procedures allow personnel to mitigate emergency consequences and correct off-normal conditions quickly. These procedures reference the Emergency Plan Implementation Procedures.

Emergency Plan Implementation Procedures contain procedures and guidance for accident assessment and emergency classification.

These procedures implement the Emergency Plan. Figure 4-1 , Off-Normal Condition Response Sequence, shows the basic response sequence followed during off-normal conditions.*

4.2 Notification

4.2.1 On-Site Personnel Emergency Plan Implementation Procedures provide for 24-hour on-site personnel warning, alerting, activating, and advising for emergency situations.

This includes:

1. Employees without emergency assignments.

2. Visitors and persons in on-site public access areas. 3. Contract and construction personnel.

4.2.2 Off-Site Agencies Emergency Plan Implementation Procedures provide for 24-hour alerting, notifying, and mobilizing Exelon off-site response organizations and for 24-hour alerting and notifying non-Exelon off-site response organizations as provided in Figure 4-2, site Agency Notification.

These procedures include means for message verification

.. 4.2.3 Messages 1. Initial emergency messages sent from the plant are detailed in the Emergency Plan Implementation Procedures.

Messages contain:*

a) Emergency class and nature of incident.

b) Whether a release is taking place. c) Potentially affected population and areas. d) Whether protective measures are necessary.

2. Emergency Plan Implementation Procedures provide for facility follow-up messages to off-site authorities.

These procedures contain: June 2016 a) Incident location, caller name, and communications identification.

b) Nature of incident, date/time, and classification.

c) Actual or projected release type (airborne, waterborne, surface spill} and estimated duration/impact times. cc 4-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear d) Radioactive material release quantity estimate and release points/heights.

e) Released material chemical and physical form including relative quantities and concentrations of noble gases, iodines, and particulates.

f) Meteorological conditions (wind speed, direction-to and from), stability indicator, precipitation.

g) Actual or projected site boundary dose rate; site boundary projected integrated dose. h) Projected dose rates and integrated dose at projected peak and at 2, 5, and 10 miles including sector(s) affected.

i) In-plant, on-site, off-site surface radioactive contamination estimate.

j) Facility response actions in progress.

k) Recommended emergency actions, protective measures, and recommendations set forth in Environmental Protection Agency's Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-400-R-92-001

), Tables 2-1 and 2-2. I) Support. requests.

m) Incident prognosis (worsening/termjnating).

3. Initial and follow-up messages provide supporting information for messages developed by State and local agencies for the public. Initial and follow-up messages are consistent with the classification scheme addressed in the Emergency Plan Implementation Procedures.

4. Off-site authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone receive initial (prompt notification) and follow-up messages directly.

Provision exists to make Initial Notifications within 15 minutes of emergency declaration.

4.2.4 Prompt

Public Notification Prompt public notification using sirens or backup methods such as mass communications or route alerting that facilitates public awareness to turn on their televisions or radios and listen for information or instructions broadcast by state or local government authorities on the Emergency Alert System.

• A physical means has been established and demonstrated to exist for providing prompt public notification within the plume exposure pathway Emergency Planning Zone. The Public Alert and Notification System Design Report is described in detail in the upgraded Public Alert and Notification System for Calvert Cliffs Nuclear Power Plant and subsequent correspondence with the Federal Emergency Management Agency. 4.3 Augmentation

4.3.1 Staffing

Figure 2-1, Minimum On-Site Staffing Requirements outlines ERO positions required to meet minimum staffing and full augmentation of the on-shift June 2016 CC4-2 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear complement at an Alert or higher declaration.

Minimum staffing is to occur within approximately 60 minutes of an Alert or higher classification with the exception of the Joint Information Center (JIC) which will achieve minimum staffing within approximately 120 minutes of event declaration.

4.3.2 Activation

It is the goal to activate the ERO facilities within 15 minutes of achieving minimum staffing.

The facility can be declared activated when the following conditions are . 1. Minimum staffing has been achieved.

2. Personnel are ready to perform their function.

3. Personnel have been briefed on the situation.

4.4 Accident

Assessment Accident assessment consists of a variety of actions taken to determine the nature, effects, and severity of an accident and includes evaluation of reactor operator status reports, damage assessment reports, meteorological observations, seismic observations, fire reports, radiological dose projections, plant radiological monitoring, off-site (environmental) radiological monitoring, etc. Emergency Plan Implementation Procedures provide methods and techniques for: A. Determining radioactive material release source term. Example: Relationship between Containment radiation monitor reading and radioactive material available for release from Containment.

B. Determining radioactive material release based on plant system parameters and_ effluent monitors (graphic recorders and the plant computer provide records to back calculate total amounts of plant released radioactivity).

c. Establishing the relationship between effluent monitor readings and site/off-site exposure and contamination for various meteorological conditions.

D. Determining release rate/projected dose if assessment instrumentation is off-scale or inoperable.

E. Rapid assessment and chemical sampling and analysis of magnitude and location of radiological hazards (actual or potential) through liquid or gaseous release pathways.

_ F. Relating measured parameters

'(e.g., Containment levels, water and air activity levels) to dose rates for key isotopes (i.e., NUREG-0654, Table 3, Page 18) and gross radioactivity measurements.

Provisions are made for estimating integrated dose from projected and actual dose rates and for comparing these estimates with protective action guides. G. Periodically estimating total population exposure.

H. Relaxing protective measures to allow reentry into an evacuated area and for return of areas to normal use. This condition includes provision for June 2016 CC4-3 EP-AA-1011 (Revision

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\ Calvert Cliffs Annex Exelon Nuclear informing the response organizations that a recovery operation is being initiated and of any changes in the organization structure that may occur. 4.5 Repair and Mitigative Action Those emergency measures taken to lessen or terminate an emergency situation at or near the source of the problem includes measures taken to prevent an uncontrolled release of radioactive material, or to reduce the magnitude of a release. Mitigative action includes equipment repair or shutdown, installation of emergency structures, fire fighting, and damage control. 4.6 Protective Actions 4.6.1 Accountability Emergency Plan Implementation Procedures provide the capability to account for all individuals in the Protected Area during a Site Area Emergency or General Emergency, to ascertain the names of missing individuals within 30 minutes of and Alert (for Security Event) Site Area Emergency or General Emergency declaration, and to account for all Protected Area individuals continuously thereafter.

To accomplish accountability, site assembly is executed at Alert level emergency in anticipation of emergency escalation.

The accountability process begins when assembly is complete.

4.6.2 Evacuation

1. .Evacuation routes for on-site individuals allow access to Maryland Route 2/4 via the plant access road and Camp Canoy Road (through Camp Canoy facility).

Transportation is by personal vehicle. Two roads allow alternative evacuation routes for inclement weather, high traffic density, and specific radiological conditions.

2. Emergency Plan Implementation Procedures provide for on-site, non-essential personnel evacuation during an Alert (for Security Event), Site Area Emergency or General Emergency.

• 4.6.3 Off-Site Recommendations

1. Guidelines for the choice of protective actions during an emergency, consistent with Federal Guidance, are provided in the Emergency Plan Implementation Proced1,1res.

The effectiveness of evacuation and protection afforded in residential units and other shelters is assumed to be that which is described in Federal Guidance.

4.7 Exposure

Control 4.7.1 Emergency Plan Implementation Procedures and Radiation Protection Procedures provide an on-site radiation protection program including exposure guidelines implementation methods for use during emergencies.

Provisions are made for distribution of dosimeters (both direct reading and permanent record devices);

ensuring dosimeters are read at appropriate frequencies; maintaining dose records for emergency workers. June 2016 CC4-4 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 4.7.2 The Emergency Plan Implementation Procedures permit on-site workers to receive radiation exposures while carrying out lifesaving or other emergency activities.

They facilitate expeditious decision making and a reasonable consideration of relative risks. 1. Exposure guidelines are consistent with Environmental Protection Agency's Guidance on Dose Limits for Workers Performing Emergency Services (EPA-400-R-92-001)

2. Guidelines are established for: a) Providing first aid and medical treatment service. b) Undertaking corrective actions. c) Performing assessment actions. d) Performing personnel decontamination.

e) Injured person removal and ambulance service. 4.8 Contamination Control 4.8.1 Radiation Protection Procedures provide on-site contamination/

decontamination control measures for: 1. Area access control. 2. Equipment, supplies, and instruments.

3. Personnel (including wounds). These procedures specify levels at which decontamination needs tO' be performed and provides for decontaminants suitable for expected contamination types including radio/iodine skin contamination.

Emergency food and water supplies will be brought to the site as needed. Food and water brought to the site will be protected against contamination.

4.8.2 Radiation

Protection Procedures provide for radiological monitoring of people evacuated from the site. 4.9 Personnel Emergencies Emergency Plan Implementation Procedures describe actions taken in response to emergencies (with and without contamination considerations).

Other procedures such as Fire, Medical, Safety, etc. may also be used to respond to personnel emergencies when the emergency plan is not implemented.

June 2016 CC4-5 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear FIGURE 4-1 OFF-NORMAL CONDITION RESPONSE SEQUENCE EVENT OCCURS Plant parameters out of normal range or a potentially damaging event is recognized " Operator observes event/instruments alarms Plant Operations-Related

-' Population-at-risk 11 Actions ' i,,-/ Prntection

• • jlE'.7

' i ,:1*. <w:*c:,-">1 y

• Evaluate event lmmec:lfate Actions 1) Determine release potentiaL initiated according to 2) Declare radiological event ifwammted.

AOPs"'/EOPs"*

3) Calculate projected doses. 4) Compare comfltions to Technical Speclfications :5) Compare conditions to EA.Ls""* Follow-up actions Classify Event According to EAls'"'" taken according to AOPs/EOPs Unusual Alert Site Area General Event Emergency Emergency , Plant placed in safe -Initiate Emergency Response Plan lmp!ementing Procedures.

cond!ftion

-Reclassify as warranted.

-Compare comllitions to Protective Action Guides. *ADP -Al:mocrnal Opera ling Procedure

• ""EOP -Emergency Operaling Procedure

""EAL -Emergency Actic;n Le*:el June 2016 cc 4-6 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear FIGURE 4-2 OFF-SITE AGENCY NOTIFICATION Emergency Occurs 1 Facilities Maintenance NRC &Ops -Emergency via Nuclear Security Director r Emergency Notification System I I I I Calvert County I Communications I H Communications r--. Emergency Center Center Operations Center , , Maryland St. Mary's County Emergency

• ---, H Communications Emergency Management I Center Operations I Agency I Center I I I I I I .. I I Maryland I Dorchester County I Department I Communications Emergency of the f----+ Center ---+ Operations Environment Center 24 Hour Operations Center Line Normal Work Hours June 2016 cc 4-7 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Section 5: Facilities and Equipment

5.1 Facilities

Specific locations on-site and off-site have been designated as emergency control and support centers. These centers are equipped to control, assess, and correct emergency conditions and allow timely communication between centers. The centers' functional objectives are presented in Figure 5-1, Facilities Functional Objectives.

5.1.1 Control

Room Plant operations are directed from the Control Room. Nuclear plant instrumentation, Area and Process Radiation Monitoring System instrumentation, controls and instrumentation for reactor and turbine generator operation are provided here. A description of the Control Room is contained in the Updated Final Safety Analysis Report (Ref. 55) Section 7.6.2. Emergency equipment available to the Control Room is listed in Emergency Plan Implementation Procedures.

5.1.2 Emergency

Operations Facility (EOF) 1. The Emergency Operations Facility floor plan is shown in Figure 5-2, Emergency Operations Facility, and its location in Calvert County is shown in Figure 5-3, Emergency Operations Facility and Joint Information Center Location.

2. The EOF is the location where the Corporate Emergency Director will direct a staff in evaluating and coordinating the overall company activities involved with an emergency.

June 2016 The EOF has facilities and capabilities for:

• Management of overall emergency response

• Coordination of radiological and environmental assessment (including receipt and analysis of field monitoring data and sample media coordination)

• Determination of recommended public protective actions, and Notification of off-site agencies (when emergency declaration is performed at the EOF) *

• Coordination of event, plant and response informatiqn provided to public information staff for dissemination to the media and public

• Staffing and activation of the facility within time frames and at emergency classification levels defined in the emergency plan

• Coordination of emergency response activities with Federal, State, and local agencies

• Provisions are ma.de for acquisition, displaying, and evaluation of radiological, meteorological , and plant system data cc 5-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex . Exelon Nuclear

• Analyzing plant technical information and providing technical briefing on event conditions and prognosis to licensee staff and off-site agencies The EOF is used for continued evaluation and coordination of activities related to an emergency having actual or potential environmental consequences.

The EOF is activated during an Alert, Site Area Emergency or General Emergency.

Space is provided so that NRC, Federal, State, and local response agencies can coordinate their activities from this location.

3. The Emergency Operations Facility is located about twelve miles from the site, in Calvert Industrial Park, Skipjack Road at Hallowing Point Road. It is a well engineered structure for design life of Calvert Cliffs Nuclear Power Plant. Detailed emergency equipment listing for the Emergency Operations Facility is contained in Emergency Plan Implementation Procedures.

5.1.3 Technical

Support Center 1. The location of the Technical Support Center at Calvert Cliffs Nuclear Power Plant is shown in Figure 5-4, TSC Location Relative to Control Room. 2. The Technical Support Center is a work area for designated technical, engineering, and management personnel who provide technical support to plant operations personn*e1 during emergency conditions.

Technical Support Center resources are used to provide guidance and technical assistance to the Control Room. Technical Support Center facilitates reactor operator relief from peripheral duties and communications not directly related to reactor system operations.

Figure 5-5, Characteristics of Technical Support Center vs. Emergency Operations Facility, shows characteristics of Technical Support Center relative to plant operations.

The Technical Support Center will be fully operational within approximately one hour after declaration.

3. The Technical Support Center is located on the 55 foot elevation with an Annex on the 58 foot elevation.

It is contiguous with and has direct (door) access from the Control Room (can also be accessed from the Turbine Hall). Habitability duplicates Control Room for postulated accident conditions.

Space available is considered adequate for personnel_

and equipment assigned (NRC Inspection Report dated 5/26/1982 EP Appraisal Combined Inspection Report Nos. 50-317/81-19 and 50-318/81-18).

Radiological protection of personnel is afforded by radiation monitoring personnel.

4. The Plant Process Computers provide data gathering, trending, storage, and display to permit accurate accident assessment with minimum interference of Control Room operation:

June 2016

• Safety Parameter Display System provides continuous indication of plant parameters from which quick assessments of plant safety status can be made.

• Plant Process Computer provides real time and historical displays and reports to assist in analysis of unit shutdown.

cc 5-2 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear These systems have backup battery power supply to maintain continuity of Technical Support Center functions and immediately resume data acquisition, storage, and display if primary source loss occurs. Parameters monitored in the Technical Support Center include NUREG 0737 Supplement 1 variables as modified by Calvert Cliffs Nuclear Power Plant's submittals to NRC. 5. The Technical Support Center contains .or has access to complete and date plant records and procedures including:

a. Drawings/Schematics

b. Technical Specifications

c. Operating Instructions/Abnormal Operating Procedures/Emergency Operating Procedures

d. Final Safety Analysis Report e. Emergency Plan Implementation Procedures

6. Detailed emergency equipment listing is contained in Emergency Plan Implementation Procedures.

5.1 .4 Operations Support Center The Operations Support Center is located within the protected area (co-located with the Outage Control Center (OCC)) separate from Control Room and

• Technical Support Center. It provides space for the assembly of support personnel during an emergency.

F'rom this location in-plant support (e.g., operations and maintenance), required to bring the plant to a safe, stable condition is coordinated.

In this way, access to the Control Room is restricted to personnel specifically requested by the Control Room. No specific habitability criteria are established.

Detailed Operations Support Center emergency equipment listing is contained in Emergency Plan Implementation Procedures.

Implementation Procedures include provisions for performing Operations Support Center functions by essential support people from a second (alternate) location.

5.1.5 Joint

Information Center 1. The Joint Information Center location is shown in Figure 5-3, Emergency Operations Facility and Joint Information Center Location.

2. The Joint Information Center is a central location for Calvert Cliffs Nuclear Power Plant personnel to meet with NRC, State and County representatives for releasing emergency announcements to news media. 3. The Joint Information Center is located about twelve miles from the site, in Calvert Industrial Park, Skipjack Road at Hallowing Point Road. It is a well engineered structure for design life of Calvert Cliffs Nuclear Power Plant. 4. The Joint Information Center will be activated for a Site Area Emergency and General Emergency.

In the first few hours of an emergency (while the Joint Information Center is being activated)

Corporate Communications will provide an information clearing house from their current location.

Should a crisis assume prolonged proportions after the center has been activated, Corporate June 2016 cc 5-3

• EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Communications can provide additional personnel.

The Joint Information Center, once activated, provides media representatives and public information officers immediate access to accurate emergency related information.

The Joint Information Center contains equipment for document reproduction, telecopying, web access, communications, and television electrical connections.

The Joint Information Center is a central clearing house for regular information exchange such that all parties have the most current and accurate information to . communicate to the public. Figure 5-6, Public Information Flow identifies the flow of public information after Joint Information Center activation.

• 5.1 .6 Laboratories 1 .. On-site The Chemistry Laboratory (Auxiliary Building) is available for emergency response during a design basis accident.

This availability includes design basis accidents that are coincident with a loss of off-site power. The laboratory can receive power from the plant's emergency diesel generators.

General capabilities include:

• Radionuclide identification in various sample media.

• Analysis and measurement of radionuclides in samples taken within the plant and samples taken in the plant site and off-site environment.

2. Off-site The. Technical and Support Services Division, Exelon Generation Group maintains a fixed counting laboratory in the Fort Smallwood Road Shops Complex:

• Dosimetry of Legal Record processing.

• Radiological Environmental monitoring equipment and sample media.

• Radiological Environmental sampling, and analysis of soil, water, air, vegetation, etc.

• Radiological Environmental Consulting.

5.1. 7 Decontamination Facilities:

• 69 foot Auxiliary Building, Rad-Con area.

• Farm Demonstration Building (on-site).

Serves relocated on-site personnel.

• Calvert. Memorial Hospital, Prince Frederick These facilities contain provisions for radiological decontamination of personnel, their wounds, supplies, instruments and equipment.

These facilities have extra clothing and decontaminants suitable for the type of contamination expected, including radioiodine skin contamination.

Detailed inventory lists and instructions for these facilities are part of Emergency Plan Implementation Procedures.

Waste disposal, subsequent to decontamination activities, is according to Radiation Protection procedures.

June 2016 cc 5-4 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 5.1 .8 Medical 1. On-Site A first aid room located in the Auxiliary Building (69 foot level) facilitates medical treatment and initial assessment of radiation exposure and uptake. Emergency Plan Implementation Procedures coupled with Operations Instructions provide detailed listing of emergency equipment kept there. 2. Off-Site Arrangements have been made for local and back-up hospitals and medical services having the capability for evaluation of radiation exposure and uptake and treatment of injuries involving radiation exposure and contamination as well as hostile based event injuries.

This arrangement includes assurance that persons providing these services are adequately prepared to handle contaminated individuals.

Arrangements with other hospitals having similar capabilities are contained in the Maryland Core Emergency Operations Plan -Fixed Nuclear Facilities (FNF) Appendix (Formerly Annex Q), Radiological Incident Annex. Equipment kept at the local off-site facility is listed in the Emergency Plan Implementation Procedures.

3. Transport Agreements are maintained for transporting victims of radiological accidents to medical support facilities including transport of contaminated injured individuals or those injured as a result of a Hostile Action Based event. 5.1.9 Alternative Emergency Response Facilities The Alternative Facility maintains the capability for staging the TSC/OSC emergency response organization personnel in the event of a hostile action. This alternative facility has the capability for communications with the emergency operations facility, control room, and plant security and the capability for engineering assessment activities, including damage control team planning and preparation.

Consistent with NRC EPFAQ No. 2013-005, the EOF will satisfy the offsite notification responsibilities for the Alternative Facility.

The Alternative Facility is located at the College of Southern Md, Prince Frederick.

5.2 Communications

Emergency Plan Implementation Procedures describe the primary and backup means of communications between Calvert Cliffs Nuclear Power Plant, local, State and Federal response organizations.

Systems are compatible with one another and include:

• A minimum of a telephone link and alternate (State/local).

• Provision for communications with contiguous State/local governments within the Emergency Planning Zones.

• Provision for communications as needed with Federal emergency response organizations.

• Provision for communications between Plant, Emergency Operations Facility, June 2016 cc 5-5 EP-AA-1011

1)

Calvert Cliffs Annex Exelon Nuclear alternate and alternative facilities, State and local emergency operations centers and radiological monitoring teams.

• Provision for alerting or activating emergency personnel in each response organization.

• Provision for Calvert Cliffs Nuclear Power Plant communication with NRC headquarters and NRC Regional Office Emergency Operations Center and the Emergency Operations Facility and radiological monitoring team assembly area.

• Coordinated communication link for fixed* and mobile medical support facilities.

See Appendix 6 for a description of the Calvert Cliffs Communication equipment.

5.3 Monitoring

Instrumentation

5.3.1 Geophysical

Phenomena Monitors

1. On-site a. Meteorological/Hydrologic

1) Primary Systems: Meteorological tower is equipped with:

• 1 Om & 60m -wind speed/direction sensors.

• 1 Om to 60m -Temperature Gradient System with Aspirated Radiation Shields and RTD sensors (1 Om & 60m ambient temperature).

• Ground level Precipitation Gauge. 2) Backup System: The Emergency Plan Implementation Procedures . provide instructions for accessing back-up meteorological data in the event the primary meteorological data becomes unavailable.

This equipment is used to initiate emergency measures according to Emergency Plan Implementation Procedures, Emergency Action Levels. Primary systems produce current local meteorological data that provides the means to estimate radioactive material dispersion due to accidental, atmospheric releases by the plant and is consistent with recommendations addressed in Regulatory .Guide 1.23, as supplemented by Supplement 1 to NUREG-0737.

The backup system utilizes near site meteorological data that provides information when the primary system is out of service. b. Seismic The Updated Final Safety Analysis Report (Reference

55) Section 7.5.7 identifies seismic monitoring systems used to initiate emergency classification according to Emergency Plan Implementation Procedures.

2. Off-Site June 2016 a. Agreements are maintained with off-site agencies to acquire geophysical phenomena monitor data for emergency access when necessary.

These agencies are identified in the Emergency Response Facility Directory.

cc 5-6 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear b. Regional meteorological information is available via contracted services with a weather monitoring center that provides appropriate National Weather Service warnings directly to control room personnel.

Regional weather information is also available at Exelon's Electric Systems Operations Building, Rutherford Business Center. Capabilities include weather radar monitor and National Weather Service information via the satellite based data system (National Weather Wire System) from the Washington Weather Forecast Office in Sterling, Virginia.

5.3.2 Meteorological

Model A Class A, atmospheric transport and diffusion assessment model (Ref. 21, App. 2) is maintained on independent, redundant, computers in the Control Room, Technical Support Center, and Emergency Operations Facility (includes a separate computer for state use). Provisions exist for remote access of site meteorological parameters for Federal, State, and locq.I authorities.

The variable trajectory, puff advection, atmospheric dispersion model is used to determine the magnitude of the impact of an accidental release* of radioactivity and provides continuous real time (as the release is occurring) assessment of predicted effluent transport and diffusion.

The model uses input from meteorological data systems and source term estimates to provide estimates of exposure rates, and dose to 10 miles. It also internally

• calculates deposition rates and total deposition and uses them, in conjunction with the meteorological and source term data mentioned above, to calculate dose due to ground contamination out to 50 miles. The model accmmts for source decay, plume depletion mechanisms, building wake, plume rise and mixing height. For the 10-mile EPZ, the model uses finite cloud techniques to estimate plume exposure dose rates, four-day external dose rates from deposition, thyroid dose rates and dose rates due to inhalation.

Avoided dose is calculated as the sum of external exposure to the plume, internal exposure due to inhalation in the plume and external exposure to ground deposition according to EPA-400 guidance.

A complete description is referenced in the Emergency Plan Implementation Procedures and in the URI System Require*ments Specification Site Annex. 5.3.3 Radiological Monitors The Updated Final Safety Analysis Report (Reference

55) Chapter 11, identifies radiological monitors (e.g., process, area, effluent, wound and portable monitors and sampling equipment) available for initiating emergency measures according to Section 3, Classification of Emergencies.

Specific instruments are incorporated in Emergency Plan Implementation Procedures . . 5.3.4 Process Monitors The Updated Final Safety Analysis Report (Reference

55) Chapter 7, identifies process monitors (e.g., reactor coolant system pressure and temperature, containment pressure and temperature, liquid levels, flow rates, status or line-up of equipment components) available for initiating emergency measures according to Section 3, Classification of Emergencies.

Specific instruments are incorporated in Emergency Plan Implementation Procedures. . June 2016 cc 5-7 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 5.3.5 Fire/Combustion Monitors The. Updated Final Safety Analysis Report (Reference

55) Section 9.9, identifies fire and combustion products detectors available for initiating emergency measures according to Section 3, Classification of Emergencies.

5.3.6 Field

Monitoring Emergency Plan Implementation Procedures describe field monitoring capabilities and resources within plume exposure Emergency Planning Zone which are intrinsic to Calvert Cliffs Nuclear Power Plant's concept of operation.

These capabilities include transportation and monitoring equipment (dose rate meters and sampling devices).

Sampling devices are capable of detecting and measuring radioiodine concentrations in air as low as 1 E-7 uCi/cc under field conditions.

Interference from noble gas presence and background radiation do not decrease the stated minimum detectable activity.

Maps identify preselected sampling and monitoring points using sector and zone designators such as those in Reference 21, Table J-1. 5.3.7 Environmental Monitoring The Updated Final Safety Analysis Report (Reference

55) Section 11.2.3.4 and Off-site Dose Calculation Manual, describe the off-site radiological monitoring program for the area surrounding Calvert Cliffs Nuclear Power Plant. Appropriate equipment is provided to facilitate this program. The monitoring equipment meets, as a minimum, the NRC Radiological Assessment Branch Technical Position for the Environmental Radiological Monitoring Program. 5.3.8 Post Accident Sampling The Updated Final Safety Analysis Report (Reference

55) Section 9.6.2.2 describes capabilities and resources available to provide initial values and

• continuing assessment through the course of an accident for post accident sampling.

Capability to sample and analyze the containment atmosphere and Reactor Coolant System meets or exceeds NUREG 0737, Item 11.B.3 requirements as modified by Calvert Cliffs Nuclear Power Plant's submittals to NRC. Calvert Cliffs Nuclear Power Plant procedures detail system operations

.. 5.3.9 In-plant Iodine Instrumentation Radiation Protection Procedures and Emergency Plan Implementation Procedures describe in-plant iodine instrumentation which provides on-site capabilities for determining initial iodine values and continuing assessment through the course of an accident.

5.4

• Emergency Kits Emergency Plan Implementation Procedures identify emergency kits/lockers and their contents (protective equipment, communications equipment, radiological monitoring equipment and emergency supplies).

June 2016 cc 5-8 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 5.5 Respiratory Radiation Protection Procedures provide for individual respiratory protection for individuals remaining or arriving on-site during emergencies.

Site specific ERO Respirator qualification requirements contained in the ERO Training and Qualification procedure take precedence over requirements contained in the Exelon Standardized Radiological Emergency Plan for Calvert Cliffs Station. 5.6 protective Clothing Supplies of apparel include coveralls, rubber gloves, shoe covers and boots, and hoods. Inventories are maintained for normal plant use by Radiation Protection personnel.

Emergency clothing supplies are kept at specific areas and emergency centers. This clothing is issued to personnel required to enter areas of known or suspected radioactive contamination.

For emergency conditions, normal street clothing is considered as protective apparel. It can be supplemented, as necessary, to protect skin surfaces.

5. 7 Radioprotective Drugs Emergency Plan Implementation Procedures provide for use of radioprotective drugs (e.g., individual thyroid protection) for individuals remaining or arriving site during emergencies.

June 2016 cc 5-9 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear FIGURE 5-1 FACILITY FUNCTIONAL OBJECTIVES . *;FACILITYNAME

.: .. *.: << ' Emergency Operations Facility (EOF) Technical Support Center (TSC) Operations Support Center (OSC) Joint Information Center (JIC) June 2016 1) 2) 3) 4) 5) 6) 7) 8) 1) 2) 3) 4) 1) 2) 1) 2) .*: . , :;; Management of overall emergency response Coordination of radiological and environmental assessment (including receipt and analysis of field monitoring data and sample media coordination)

Determination of recommended public protective actions, and Notification of off-site agencies (when emergency declaration is performed at the EOF) Coordination of event, plant and response information provided to public information staff for dissemination to the media and public Staffing and activation of the facility within time frames and at emergency classification levels defined in the emergency plan Coordination of emergency response activities with Federal, State, and local agencies Provisions are made for acquisition, displaying, and evaluation of radiological, meteorological , and plant system data Analyzing plant technical information and providing technical briefing on event conditions and prognosis to licensee staff and off-site agencies Provide plant management and analytical support to Operations personnel during emergency conditions.

Relieve reactor operators of peripheral duties and communications not directly related to reactor system manipulations.

Provide and coordinate engineering support for emergency response.

Prevent congestion in the Control Room. Provide and coordinate logistic support (i.e., maintenance, etc.) to bring the plant to a safe, stable condition.

Restrict Control Room access to personnel specifically requested by Shift Manager or TSC Operations Manager. Provide media representatives with immediate access to accurate emergency related information, generated by all involved agencies.

Provide equipment for document reproduction, telecopying, communications, and television electrical connections.

cc 5-10 EP-AA-1011 (Revision

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Calvert Cliffs Annex Alternative Facilities June 2016 Exelon Nuclear 8.1 Staging area for the TSC/OSC emergency response organization personnel in the event of a hostile action. 8.2 Communication capability with EOF, Control Room and Plant Security.

8.3 Capability

to perform engineering assessment activities including damage control team planning and preparation.

CC 5-11 EP-AA-1011 (Revision

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C=:j w I i;j I LJ June 2016 UPPER STATUS PLENUM ROOM l 1 rTJ STATE I NRC/ LOCAL FEMA I I I I WAVE I TELEPHO_N_i;;t I "'", MENS WOMENS OM J:CTRl:CRA R_O_O_M __ _,_ __ R_O_O_M MOE ROOM NRC ROOM STATUS ROOM r===r ---, Storage CONFERENCE I (J) ROOM I !!:: AUDIO/ VIDEO ROOM I i;j cc 5-12 DOSE ASSESSMENT STAIRS , I MECHANICAL I I _I SECURITY -----( ENTRY LUNCH ROOM SUPPLY ROOM EP-AA-1011 (Revision

1)

Calvert Cliffs Annex June 2016 * * ' ' HA!iOWJNG FIGURE 5-3 EMERGENCY OPERATIONS FACILITY AND JOINT INFORMATION CENTER LOCATION 0 Sires Rd. Exelon Nuclear cc 5-13 EP-AA-1011 (Revision i)

Calvert Cliffs Annex UNIT 1 PL.I.NT COIT'UTER ROOH r June 2016 JI Exelon Nuclear FIGURE 5-4 TSC LOCATION RELATIVE TO CONROL ROOM T\.RBINC HALL lAcCess to TsC fr-oni EL '15'> T.ECHNICAL SIJePORT CENTER SHI;::T SUPERVISOR OFFJCE TECHNICAL SU'PORT CENTER ANNEX I UNlT 2 II PLANT _ll COMPUTER ROOH MAIN CONTROL ROOM UNITS I ANO :;? cc 5-14 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear FIGURE 5-5 CHARACTERISTICS OF TECHNICAL SUPPORT CENTER VS. CONTROL ROOM AND OPERATIONS SUPPORT CENTER (i.e. Control Room and Operations Support Center) CONTROL ROOM & OPERATIONS SUPPORT CENTER

• Activities performed by trained, licensed operators in the Control Room supported by OSC maintenance and operations staff.

• Actions based on: * * * * *

• Specific procedures to assure success of safety functions (criticality control, core coverage, heat removal, containment)

• Reaction to plant symptoms (flux, flows, pressures, temperatures)

Success-oriented (goal is to bring plant to a safe stable condition)

Limited number of options prescribed Strong incentives for adherence to procedures Actions should be unambiguously beneficial Time for decision making on order of minutes

• TECHNICAL SUPPORT CENTER Activities performed by high level engineering and management personnel.

Supported by the OSC staff.

• Actions based on: * * * * *

• Accident management strategies derived from likely paths to core melt and containment failure.

• Anticipation of potential problems or phenomenon Defensive strategy (do what is necessary to save the core and containment)

Broad range of options in response to unfolding events Requires authority to overrule established procedures Actions may have negative side effects Time for decision making on order of hours to days June 2016 cc 5-15 EP-AA-1011 (Revision

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Calvert Cliffs Annex

• CONTROL ROOM OFF-SITE AGENCIES Exelon Nuclear FIGURE 5-6 PUBLIC INFORMATION FLOW TECHNICAL SUPPORT CENTER EMERGENCY

• OPERA TIO NS FACILITY if ........................................ , JOINT *******************.*.***.**..*

'.) INFORMATION CENTER ..................

EMPLOYEES PUBLIC CALLS MEDIA INQUIRY GOVERNMENTAL OFFICIALS STOCKHOLDERS

___ Normal Information Flow (JIG Activated)

___ Back-up Information Flow (Prior to JIG Activation or JIG communications directly with station) June 2016 cc 5-16 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear Section 6: Maintaining Nuclear Emergency Preparedness

6.1 Training

An integrated training program provides for and ensures initial, annual, and continuing training of appropriate individuals and groups involved in emergencies.

6.1.1 General

Orientation General Employee Training describes the program that provides training to all persons having access to Calvert Cliffs Nuclear Power Plant and includes Emergency Plan indoctrination.

6.1.2 Emergency

Personnel Plant procedures establish a training program for instructing personnel who implement radiological emergency plans. Specialized initial training, annual, and continuing training programs (including scope, nature and frequency) is provided for: 1. Directors or coordinators of response organizations.

2. Personnel responsible for accident assessment.

3. Radiological monitoring teams and radiological analysis personnel.

4. Security and fire fighting personnel.

5. On-site repair and damage control/correctional action teams. 6. First aid and rescue personnel.

This training includes courses equivalent to or exceeding Red Cross Multi-Media.

7. Local support services personnel including Emergency Management/Emergency Services personnel.

Site specific training is provided to those off-site organizations who may be called upon to provide assistance.

8. Medical support personnel.

9. Recovery Organization personnel.

1 o. Personnel responsible for transmission of emergency information instructions.

Annual requalification training as applied to those personnel assigned Exelon ERO positions is defined as once per calendar year .not to exceed 18 months behveen training sessions.

The training program for members of the emergency organizations includes practical drills in which individuals demonstrate ability to perform assigned emergency functions.

The training frequency for the practical drills is at least once every 2 years. 6.1.3 Public 1. Calvert Cliffs Nuclear Power Plant coordinates annual updating and dissemination of information to the public regarding how they will be notified and what their actions should be in an emergency.

The information includes but is not necessarily limited to: a. Educational information on radiation.

b. Contact for additional information.

June 2016 cc 6-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear c. Protective measures, e.g., evacuation routes and reception centers, sheltering, respiratory protection, radioprotective drugs. d. Special needs of the handicapped.

Means for accomplishing this dissemination include publication distribution, and signs or notices to refer the transient population to radio stations or other source of local emergency information.

This program provides the permanent and transient adult population within the plume exposure Emergency Planning Zone an adequate opportunity to become aware of the information annually.

Publications and information provide written material that is likely to be available in a residence during an emergency.

2. Calvert Cliffs Nuclear Power Plant disseminates information annually to acquaint news media with emergency plans, information concerning radiation, and points of contact for release of public information in an emergency.

6.1.4 Emergency

Preparedness Organization The Emergency Preparedness Organization maintains a training program for Emergency Preparedness Organization members

• responsible for the planning effort. Training includes attendance at emergency planning seminars, information workshops and training classes, and literary reviews. 6.2 Exercises and Drills Plant procedures provide for periodic exercises to evaluate major portions of emergency response capabilities; drills to develop and maintain skills; tests to verify communications operability; and correction of deficiencies identified as a result of any of the preceding.

During drills, on-the-spot correction of performance errors is made with a demonstration of proper performance offered by the controlleL Correction of errors made in exercises is through Self-Assessment and Corrective .Actions programs described in plant procedures.

6.3 Program

Responsibility The* Emergency Preparedness Manager has authority and responsibility for Calvert Cliffs Nuclear Power Plant radiological emergency response planning.

This responsibility includes emergency plan development and updating and coordination of plans with other response organizations.

6.4 Equipment

Inventory and Maintenance Emergency equipment and instrumentation are inspected, inventoried and/or operationally checked once each calendar quarter, after each use and/or whenever tampering is suspected.

Equipment calibration is according to plant procedures that endorse manufacturers' calibration recommendations.

Sufficient reserves are available to replace items removed from kits for calibration and repair. June 2016 cc 6-2 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 6.5 Program Review and Update 6.5.1 Calvert Cliffs Emergency Plan and plant procedures and agreements contained there:-in are updated as needed. Updates include changes identified by drills and exercises.

6.5.2 Calvert

Cliffs Emergency Plan changes and revisions shall be reviewed by the Plant .Operations and Review Committee.

The Plant Operations and Review Committee shall submit recommended changes to the Nuclear Safety Review Board according to plant procedures.

6.5.3 Calvert

Cliffs Emergency Plan and Emergency Plan Implementation

• Procedures and approved changes are forwarded to appropriate organizations and individuals having responsibility for their implementation.

Revised pages are marked to show changes, except where changes are extensive.

An Emergency Plan distribution list is maintained according to standard plant practices for document control. The Calvert Cliffs Emergency Plan is submitted to the Nuclear Regulatory*

Commission (NRC) Document Control Desk through standard plant practices for transmitting approved documentation to the NRC. 6.5.4 The Calvert Cliffs Emergency Plan is certified by the Emergency Preparedness Manager to be current on an annual basis. Emergency Plan Implementation Procedures are certified by the Emergency Preparedness Manager to be current on a biennial basis. 6.5.5 Documents that are associated with the Calvert Cliffs Emergency Plan that contain telephone numbers are updated quarterly.

• 6.5.6 Emergency Preparedness will ensure that all emergency preparedness program elements . are reviewed by persons who have no direct responsibility . for the implementation of the emergency preparedness program either: 1. At intervals not to exceed 12 months or, 2. As necessary, based on an assessment against performance indicators, and as soon as reasonably practicable after a change occurs in personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but not longer than 12 months after the change. In any case, all elements of the emergency preparedness program are to be reviewed at least once every 24 months. This review includes an evaluation for adequacy of interfaces with the State and local governments and of drills, exercises, capabilities, and procedures.

The Emergency Preparedness Manager will evaluate and correct review findings.

The results of the review, along with the recommendations for improvement, must be documented and reported to corporate and plant management.

Parts of the review involving the adequacy evaluation of the interface with the State and local governments are made available to them. Review results are retained for five years. 6.5.7 Annually, emergency action levels are reviewed with State and local government authorities.

June 2016 cc 6-3 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 6.6 Records 6.6.1 Plant procedures describe retention requirements for records generated as a result of the implementation of the Emergency Plan. 6.6:2 Records pertaining to the independent review of the emergency preparedness program will be collected; stored,

• maintained and retrieved according to plant procedures.

Independent review records include:*

1. Review report (includes findings and recommendations).

2. Review findings and recommendations resolution.

3. Reports pertaining to interface with off-site agencies shall be made available to the appropriate state or local government.

June 2016 cc 6-4 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear SECTION 7: DEFINITIONS AND ACRONYMS 7 .1 Abbreviations

& Acronyms June 2016 ALARA As Low As Reasonably Achievable ANSI AOP CCNPP CFR OHS DOE DOT EAL RM EOC EOF EOP EPA EPZ EPlan EPIP EWP FEMA

• FRMAP HEW HP HSM INPO ISFSI JIC LNG LOCA MOE MEMA NFPA NRC American National Standards Institute Abnormal Operating Procedures Calvert Cliffs Nuclear Power Plant Code of Federal Regulations Department of Homeland Security Department of Energy Department of Transportation Emergency Action Level Recovery Manager Emergency Operations Center Emergency Operations Facility Emergency Operating Procedures Environmental Protection Agency Emergency Planning Zone. Emergency Plan Emergency Plan Implementation Procedure Emergency Work Permit Federal Emergency Management .Agency Federal Radiological Monitoring and Assessment Program Health Education and Welfare Health Physics Horizontal Storage Module Institute of Nuclear Power Operations Independent Spent Fuel Storage Installation Joint Information Center Liquefied Natural Gas Loss of Coolant Accident Maryland Department of the Environment Maryland Emerg.ency Management Agency National Fire Prevention Association Nuclear Regulatory Commission cc 7-1 EP-AA-1011 (Revision

1)

,._,c' Calvert Cliffs Annex Exelon Nuclear NRR NSRB 01 OP osc PAG PAR PAXNAS PORC PPRP REACffS RMS RPM SCBA TSC U-1 U-2 USCG UFSAR Nuclear Reactor Regulation (Branch of NRG) Nuclear Safety Review Board Operating Instructions Operating Procedures Operational Support Center Protective Action Guidelines Protective Action Recommendation Patuxent River Naval Air Station Plant Operation Review Committee Power Plant Research Program Radiation Emergency Assistance Centerffraining Site Radiation Monitoring System Radiation Protection Manager Self-Contained Breathing Apparatus Technical Support Center Unit 1 Unit 2 United States Coast Guard Updated Final Safety Analysis Report 7.2 Definitions o Emergency

-situation that may result in undue risk to public/site personnel health and safety, or significant damage to plant equipment.

Emergency phases: a) Occurrence

-actual physical event with associated alarms, warning signals, and immediate protective actions provided within the facility.

b) Emergency

-actions taken to protect lives and property.

These actions are taken by on-site personnel at the time of event. Only equipment and resources immediately available are of value in this phase. c) Recovery/Restoration

-actions are planned, organized, and directed towards recovery from the results of the event. Actions include restoring equipment and condition to original, or acceptable intermediate state. Off-site equipment and personnel may be used. When situation control is established, restoration efforts are abandoned.

o Emergency Operations Center (EOG) -designated State and local facilities designed and equipped for agency emergency operations coordination and control. o Emergency Planning Zones (EPZs) June 2016 cc 7-2 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear a) Plume EPZ area, about 10 miles in radius from Calvert Cliffs Nuclear Power Plant centerpoint, for which plume exposure emergency planning considerations have been given to protect people and property.

b) !ngestion EPZ area, about 50 miles in radius from Calvert Cliffs Nuclear Power Plant centerpoint, for which ingestion exposure emergency planning consideration has been given to protect people and property.

o Exclusion Boundary -That area of CCNPP site within 1150 meter radius of either containment as defined in Section 100.3(a) of 10 CFR 100. o Ingestion Exposure Pathway -Pathway where principal exposure would be from ingestion of contaminated water or food (e.g., milk, fresh vegetables).

Potential exposure time could range from hours to months.

• o Off-site -area outside Calvert Cliffs property boundary.

o On-site -area within Calvert Cliffs property boundary.

o Plume Exposure Pathway -Pathway where principal exposure source is from: a) Plume and deposited materials for whole body external gamma radiation exposure.

b) Passing radioactive plume for inhalation exposure.

Exposure time could range from hours to days. o Position Specific Checklist

-Checklist directing actions of an ERO position.

o Projected Dose -calculated or estimated radiological dose that the affected population could receive if no protective actions are taken. o Projected Dose Commitment

-calculated or estimated future dose commitment which could be received by population-at-risk individlial(s) from inhalation or ingestion of radioactive material if no protective actions are taken. o Property Boundary -outer limits Calvert Cliffs Nuclear Power Plant property.

o Protected Area -the site specific area which normally encompasses all controlled area within the security Protected Area fence (does not include ISFSI). o Protective Actions -measures taken to prevent or minimize a projected dose. o Protective Action Guides -projected total effective dose equivalent to individuals in the general population that warrants protective action as described in the Environmental Protection Agency's Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, October 1991 (EPA-400-R-92-001

). o Protective Action Recommendations (PAR) -protective actions recommended by Calvert Cliffs Nuclear Power Plant to State and County decision makers to prevent or minimize a projected total effective dose equivalent to individuals in the general population.

o Radiation Incident -unexpected event, occurrence, or circumstance involving radiation exposure or radioactive contamination requiring a report pursuant to 1 OCFR20.2203.

o Radiologically Controlled Area (RCA) [Restricted Areal -Any plant area(s) June 2016 cc 7-3 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear where radiation levels are equal to or greater than 2.0 mrem in one hour, OR where a person could receive a Total Effecting Dose Equivalent (TEDE) of 100 mrem in a year, OR removable radioactive contamination exists at levels detectable above background, OR any room which contains radioactive materials in excess of 1 O times the quantity of material specified in 1 O CFR 20, Appendix C. o Recovery Actions -actions taken after an emergency to restore the plant as nearly as possible to pre-emergency condition.

SECTION 8: REFERENCES 8.1 ANSl/ANS-3.7.1.-1979, American National Standard for Facilities and Medical Care in On-site Nuclear Power Plant Radiological Emergencies.

8.2 ANSl/ANS-3.7.2.-1979, American National Standard for Emergency Control Centers for Nuclear Power Plants. 8.3 ANSl/N320-1979, American National Standard Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation.

8.4 ANS-3.2/ANSI N18.7-1976, Administrative Controls and Quality Assurance for the operations Phase of Nuclear P9wer Plants. 8.5 "Decontamination and Treatment of the Radioactively Contaminated Patient," Calvert Memorial Hospital and Calvert Cliffs Nuclear Power Plant. 8.6 Calvert Cliffs Nuclear Power Plant Operating License Unit 1, NO. DPR-53 and Unit 2 NO. DPR-69, including:

a. Appendix A, Technical Specifications (Safety) b. Appendix B, Technical Specifications (Environmental)

8. 7 Calvert Cliffs Nuclear Power Plant Procedures:

c. Nuclear Program administrative interdepartmental, departmental and section/unit Procedures

d. Radiation Protection Procedures . e. Nuclear Engineering Operating Instructions

f. Operating Procedures (Emergency Operating Procedures, Abnormal Operating Procedures, Operating Instructions)

g. Security Plan Implementation Procedures

h. Security Plan i. Calvert Cliffs Safety Parameters Display System Alarm Manual j. Fleet Industrial Safety Manual k. Off-site Dose Calculation Manual 8.8 Department of Health, Education, and Welfare, Food and Drug Administration, 21 CFR Part 1090, "Accidental Radioactive Contamination of Human Food. and Animal Feeds" Proposed Rules, Federal Register, Vol. 43, No. 242, December 15, June 2016 cc 7-4 EP-AA-1011 (Revision

1)

-_r,,J Calvert Cliffs Annex Exelon Nuclear 1978. 8.9 Department of Health, Education, and Welfare, Food and Drug Administration Notice on "Potassium Iodide as a Thyroid-Blocking Agent in a Radiation Emergency," Federal Register, Vol. 43, No. 242, December 15, 1978. 8.10 Federal Radiation Coundl Report NO. 7, May 1965, Background Material for the Development of Radiation Protection Standards.

8:11 Final Safety Analysis Report (FSAR), Calvert Cliffs Nuclear Power Plant, Inc., Calvert Cliffs Nuclear Power Plant. 8.12 Markee,/E.

H., "On the Relationships of Range to Standard Deviation of the Wind Fluctuations, "Monthly Weather Review, Vol. 91, No. 2 (February 1963). 8.13 National Council on Radiation Protection Report NO. 39, January 15, 1971, "Basic Radiation Protection Criteria." 8.14 National Council on Radiation Protection Report 53 March 1, 1977, "Review of NCRP Radiation Dose Limits for Embryo and Fetus in Occupationally-Exposed Women." 8.15 8.16 8.17 8.18 8.19 8.20 8.21 National Council on Radiation Protection Report NO. 55, August 1, 1977, "Protection of the Thyroid Gland in the Event of Releases of Radioiodine." NUREG-75/087, Revision 1, USNRC Standard Review Plan Section 9.5.1, Fire -Protection Program, and Section 13.3, Emergency Planning.

NUREG-0396, EPA 520/1-78-016, November 1978, Planning Basis for the Development of Site and Local Government Radiological Emergency Response Plans in Support of Light Water Nuclear Power Plants. NUREG-0578 (extraets), July 1979, TMl-2 Lessons Learned Task Force Status Report and Short-Term Recommendations.

NUREG-0600 (extracts), Investigation into the March 28, 1979. Three Mile Island Accident by Office of Inspection and Enforcement, dated August 1979. NUREG-0610, USN RC Draft Emergency Action Level Guidelines for Nuclear* Power Plants, September 1979. NUREG-0654/FEMA-REP-1, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans for Preparedness in Support of Nuclear Power Plants, November, 1980. 8.22 NUREG-0696, Functional Criteria for Emergency Response Facilities, February, 1981. 8.23 D. Ramsden, F.H. Passant, C.O. Peabody, and R.G. Speight "Radioiodine Uptake in_ the Thyroid Studies of the Blocking and Subsequent Recovery of the Gland Following and Administration of Stable Iodine, "Health Physics 13, 633, Pergamon Press, 1967 (RA67). 8.24 Slade, D.H., "Dispersion Estimates from Pollutant Releases of a Few Seconds to 8-hours in Duration," Technical Note 2-ARL-1,ESSA, Washington, DC, (August, 1965). 8.25 Sfate of Maryland Radiological Emergency Plan, (July, 2007 Revision 10), Annex June 2016 cc 7-5 EP-AA-1011 (Revision

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• . Calvert Cliffs Annex Exelon Nuclear Q. 8.26 Title 10, Code of Federal Regulations.

I. Part 20, Standards for Protection Against Radiation.

m. Part 50, Licensing of Production and Utilization Facilities.

n. Part 50, Appendix E, Emergency Plans for Production and Utilization Facilities.

o. Part 50, Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities, Proposed Rule, Published in the Federal Register on August 29, 1979 p. Part 100, Reactor Site Criteria.

8.27 U.S. NRC, Emergency Planning Review Guideline Number One-Revision Emergency Planning Acceptance Criteria For Licensed Nuclear Power Plants, dated September 7, 1979. 8.28 8.29 8.30 8.31 8.32 U.S. NRC, SEGY-79-450, dated July 23, 1979, Action Plan for Promptly Improving Emergency Preparedness.

U.S. NRC Regulatory Guide 1.16, Revision 4, dated August 1975, Reportinp, of Operating Information

-Appendix A, Technical Specifications.

• .. U.S. NRG Regulatory Guide 1.21, .Revision 1, Dated June 197 4, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.

• U.S. NRC Regulatory Guide 1.23, proposed Revision 1, September 1981, Meteorological Programs in Support of Nuclear Power Plants. U.S. NRC Regulatory Guide 1.97, Revision 2, December 1980, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an 8.33 U.S. NRC Regulatory Guide 1.70, Revision 3, Standard Format and Content of Safety *Analysis Reports for Nuclear Power Plants, Section 13.3, "Emergency Planning." 8.34 U.S. NRC Regulatory Guide 1.120 (for comment), Revision 1 dated November 1977, Fire Protection Guidelines for Nuclear Power Plants. 8.35 U.S. NRC Regulatory Guide 1.109, Revision 1, Dated October, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I. 8.36 Report to NRC prepared by Combustion Engineering, Inc., and submitted by Baltimore Gas and Electric as "Environmental Impact of Extended Fuel Cycles in Calvert Cliffs Units 1 and 2." November, 1979. 8.37 Calvert Cliffs Fire Fighting Strategies Manual. 8.38 Emergency Plan Implementation Procedures, Calvert Cliffs Nuclear Power Plant. 8.39 "Emergency Resources Manual (RP/EP-1)," Institute of Nuclear Power Operations.

June 2016 cc 7-6 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 8.40 NUREG/CR-1311, October, 1979 "Examination of Off-site Radiological Emergency Protective Measures for Nuclear Power Accidents Involving Core Melt." 8.41 CCNPP Operating Procedures, OP-2 Rev. 5, April 1979, "Measurements of Radionuclides in Milk." 8.42 CCNPP Operating Procedures, OP-4 Rev. 9, March 1980 "Procedures for Collection and Radioanalysis of Aquatic Samples." 8.43 CCNPP Operating Procedures, OP-5 Rev. 7, August 1979, "Collection and Radioanalysis of Terrestrial and Atmospheric Samples." 8.44 CCNPP Op,erating Procedures, OP-6 Rev. 3, June 1978, "External Radiation Dose Rate Measurements." 8.45 Commonwealth of Virginia, Radiological Emergency Response Plan (RERP). 8.46 State of Delaware, Radiological Emergency Plan (REP). J 8.47 District of Columbia, District Response Plan. 8.48 NUREG-0818, October 1981, "Emergency Action Levels for Light Water Reactors" Draft Report for Comment. 8.49 QUpgraded Public Alert and Notification System Design Report for Calvert Cliffs Nuclear Power Plant," 8.50 Updated Safety Analysis Report for Independent Spent Fuel Storage Installation.

8.51 Regulatory Guide, 1.101, U.S. NRC, Emergency Planning For Nuclear Power Plant. 8.52 USNRC Safety Guide 23, February 1972, "Onsite Meteorological Programs." 8.53 NUREG -0737, November 1980, "Clarification of TMI Action Plan Requirements.;'

8.54 NUREG-0737, Supplement 1, January 1983, "Clarification of TMI Action Plan Requirements:

Requirements for Emergency Response Capability." 8.55 Updated Final Safety Analysis Report (UFSAR), Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Calvert Cliffs Nuclear Power Plant, Inc. 8.56 Nuclear Crisis Management Protocol, Business Continuity Program. 8.57 Calvert County REP and SOP. 8.58 St. Mary's County REP and SOP. 8.59 Dorchester County REP and SOP. 8.60 EPA manual of PAGs and Protective Actions for Nuclear Incidents, October 1991 (EPA-400-R-92-001 ) .. 8.61 "Public Protection Strategies for Potential Nuclear Accidents," "Sheltering Concepts with Existing Public and Private Structures" (SAND 77-1725), Sandia Laboratory.

8.62 "Examination of Off-Site Radiological Emergency Measures for Nuclear Reactor Accidents involving Core melt" (SAND 78-0454), Sandia Laboratory.

8.63 "Protective Action Evaluation, Part II, Evacuation and Sheltering as Protective Actions Against Nuclear Accidents Involving Gaseous Releases" (EPA 520/1-78-0018). June 2016 CC7-7 EP-AA-i 011 (Revision

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Calvert Cliffs Annex Exelon Nuclear 8.64 "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" (EPA 400-R-92-001

). 8.65 "Criteria for Protective Action Recommendations for Severe Accidents" (NUREG-0654/FEMA-REP-1, Rev. 1, Supp. 3). 8.66 "RTM-96, Response Technical Manual" (NUREG/BR-0150, Vol. 1, Rev. 4.). 8.67 "Accidental Radioactive Contamination of Human Food and Animal Feeds: Recommendations for State and Local Agencies" (Center for Devices and Radiological Health, FDA, August 13, 1998). June 2016 cc 7-8 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear APPENDIX 1 NUREG-0654 Evaluation Criteria Cross Reference This appendix cross references the Emergency Plan with NUREG-0654, Revision 1, November, 1980. Numbered items in this appendix correspond to NUREG-0654.

Missing items are items from NUREG-0654 that do not apply to the licensee.

June 2016 A1-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex NUREG-0654 Reference A1 -Item a A1 -Item b A1 -Item c A1 -Item d A1 -Item e A2-Item a A2-Item b A3 A4 B1 B2 B3 B4 B5 B6 B7 B7-Item a B7-Item b B7-Item c B7-Item d BS B9 C1 June 2016 Exelon Nuclear APPENDIX 1 NUREG-0654 Evaluation Criteria Cross Reference Criteria Identification of Response Organizations Organization of Concept of Operations Organizational Inter-Relationships

-Block Diagrams Designation of Organization Director 24 Hour Response/Communication Organization Authority Legal Basis for Organization Authority Formal lntra-governmenVOrganization Agreements Designated Authority for Organization Resource Continuity Provision for Onsite Shift Emergency Organization Designation of Onsite Emergency Director Line of Succession for the Emergency Director Functional Responsibilities of the Emergency Director Assignment of On-Site Emergency Personnel Onsite Emergency Organization Interface Designation of Minimum Staffing Requirements for Plant Emergencies Logistics Support for Emergency Personnel Technical Support for Planning/Re-entry/Recovery Operations Management Level Interface with Governmental Authorities Information/Press Releases Contractor

& Private Organization to provide assistance Designation/Responsibility/Limitations of Local Agency Assistance Licensee shall make provisions for incorporating the Federal response capability into its operation plan Plan Reference Section No. 1.2, 1.3, 2.6, 2.7 1.3, 2.1, 2.3-2.7 Fig. 2-3 -Fig. 2-6 2.3, 2.4 2.1, 4.2, Fig. 4-2 N/A (not required in Licensee Plans) N/A (not required in Licensee Plans) 2.5 -2.7, App. 2 2.1, 2.3, 2.4 2.1, 2.3, Fig. 2-1, Fig. 2-2, Fig-4 2.3.1 2.3.1, 2.3.2 2.3.1, 2.3.2 Sect. 2, 4.3, Fig 2-1 Sect. 2 2.3, Fig. 2-1 App. 4 2.4, Fig. 2.3 2.3.2, 2.4.1 App. 4 2.5, 2.6 2.5 -2.7 2.7.4 A1-2 EP-AA-1011 (Revision

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Calvert Cliffs Annex C1 -Item a C1 -Item b C1 -Item c C2-Item a C2-Item b C3 C4 01 02 03 04 E1 E2 E3 E4 ES E6 E7 F1 F1 -Item a F1 -Item b F1 -Item c June 2016 Exelon Nuclear APPENDIX 1 NUREG-0654 Evaluation Criteria Cross Reference Authority to Request RAP/I RAP Resources Federal Resources Expected and Time of Arrival Specify Support Available to Federal Response Organization Representative at Near-Site Emergency Operations Facility Licensee Representative at Governmental EOC Radiological Laboratory Capabilities Nuclear Assistance Sources Facility Emergency Classification System Initiating Conditions State and Local Emergency Classification System State and Local Procedures Bases for NotificationNerification Personnel Notification/

Alert/Mobilization Procedures Contents of Initial Plant EmergencyMessages Provisions for Content of Plant Follow-up Messages Dissemination of Information from Plant Operators Means for Population Notification Provision for Written Public Instruction Messages 24-Hour Notification/Activation of Emergency Response Network 24-hour per day notification and activation 2.3.1, 2.3.2, 2.4.1 2.7.4 2.7.4 N/A (not required in Licensee Plans, see State & County Plans) App. 4 5.1.6 2.5 -2.7, App. 2 Sect. 3 Addendum 3 N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, *see State & County Plans) 3.1, 4.2. Fig. 4-1, Fig. 4-2 4.2.1, 4.3.1 4.2.3 4.2.3 N/A (not required in Licensee Plans, see State & County Plans) 4.2.2, 4.2.4, 5.2 . Fig. 5-6 App. 4, 5.1.5 5.2 2.3. 4.2.2, 5.2 Fig. 4-3, 5.2 Communications with State/local governments

5.2 Communications

with Federal organizations 5.2 A 1-3 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex Exelon Nuclear APPENDIX 1 NUREG-0654 Evaluation Criteria Cross Reference F1 -Item d Communications between the facility and the EOF, 5.2 State/local EOCs, and radiological monitoring teams; F1 -Item e Alerting or activating emergency personnel 4.2.1, 4.2.2, 5.2 F1 -Item f Communications with NRG 5.2 F2 Communications with Medical Support Facilities 5.2 F3 Periodic Communications System Testing 6.2, 6.4 G1 Public Emergency Education/Information 6.1.3 G2 Public Emergency Education Program 6.1.3 G3 Public Information Control Point 2.4.4, 5.1.5, App. 4 G4-ltem a Designated Public Information Spokesperson 2.4.5, 5.1 .5, App 4 G4-ltem b Timely Exchange Among Spokespersons 2.4.5, 5.1 .5, App 4 G4-ltem c Arrangements for Rumor Control 2.4.5, 5;1.5, App 4 GS News Media Education Program 6.1.3.2 H1 NUREG-0696 Technical

& On,..site Operations Support 5.1.3; 5.1.4 Centers H2 Near-Site Emergency Operations Facilities 5.1.2 N/A (not required H3 State & Local Emergency Operations Center in Licensee Plans, see State & County Plans) H4 Provision for Activation/Staffing of Facilities 2.3, 2.4, 4.3 HS Onsite Monitoring Systems Section 5.3 H6-Item a Offsite Geophysical Phenomena Monitors 5.3.1 H6-Item b

• Off-site Radiological Monitors/Dosimetry 5.3.3, 5.3.6, 5.3. 7 H6-Item c Laboratory Facilities

' 5.1.6 H7 Off-site Radiological Monitoring Equipment 5.3.6, 5.3.7, 5.4 H8 Provision for Meteorological Instrumentation/Procedures 5.3.1, App. 2 H9 Provision for. On-site Operations Support Center . 5.1.4 H10 Inspection/Inventory/Calibration of Emergency 6.4 Equipment/Instruments H11 Categories of Emergency Equipment Section 5 H12 Centralized Point for Receipt and Analysis of All Field 5.1.2, Fig. 5-1 Monitoring Data June 2016 A1-4 EP-AA-1011 (Revision

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Calvert Cliffs Annex 11 12 13-Item a 13-ltem b 14 15 16 17 18 19 110 111 J1 J2 J3 J4 JS J6 J7 JS J9 June 2016 Exelon Nuclear APPENDIX 1 NUREG-0654 Evaluation Criteria Cross Reference Identification of Plant Condition Parameters and Corresponding Emergency Classes NUREG-0578 Post-Accident Sampling and Monitoring Capabilities Methodsffechniques for Source Term Determination Methodsffechniques to Determine Release Magnitude Onsite/Offsite Exposures and Contamination for Various Meteorological Conditions Acquisition of Meteorological Information . Determination of Release Rate/Projected Doses Given Inoperable Instrumentation Capabilities for Field Monitoring within the Plume Exposure EPZ Capability for Assessment of Actual/Potential Magnitude and Location of Radiological Hazards Capability to Detect Airborne Radioiodine Concentrations as Low as 1 E-07 microcurie/cc Estimation of Integrated Doses; Comparison with Protective Action Guides Arrangements to Locate and Track the Plume Capability to Warn Personnel Offsite Sheltering/Evacuation of Onsite Personnel Radiological Monitoring of Personnel Evacuated from Site Onsite Non-Essential Personnel Evacuation/Decontamination at Offsite Facility Accountability for Onsite Personnel Onsite Personnel Protection Prompt Notification of Offsite Authorities for Protective Actions Onsite Plan Contains Plume Exposure EPZ Evacuation Time Estimates Protective Action Guides (Personnel Exposure/Food Stuffs) Addendum 3 Section 5.3 Sect. 4.4 Sect. 4.4 Sect. 4.4 4.2.3, 5.3.1, 5.3.2 Sect. 4.4 5.3.6 2.3, 4.2.1, 4.2.2, 4.3, 4.4, 5.3, App 4 5.3.6 4.4, 5.3.2. N/A (not required in Licensee Plans, see State & County Plans) 4.2.1 4.6.2 4.8.2 4.6.2, 5.1. 7 4.6.1 5.5 -5.7 4.4.2, 4.2.3,4.6.3, Fig. 4-2 EP-AA-1012, Addendum 2 N/A (not required in Licensee Plans, see State & County Plans) A1-5 EP-AA-1011 (Revision

1)

Calvert Cliffs Annex J10-Item a J10-Item b J10-Item c J10-Item d J10-Item e J10-Item f J10-Item g J10-Item h J10-Item i J10-Item j J10-Item k J10-Item I J10-Item m J1t June 2016 Exelon Nuclear APPENDIX 1 NUREG-0654 Evaluation Criteria Cross Reference Maps of Evacuation Routes/Sectors Relocation Centers Population Distribution by Sector/Zone Means of Notification of Transient/Resident Population Protection of Impaired Persons Radioprotective Drug Distribution Radioprotective Drug Administration Means of Relocation Relocation Centers 5 to 1 O miles Beyond the EPZ Evacuation Routes/Traffic Capabilities Evacuated Area Access Control Evacuation Route Impediments/Contingency Measures Evacuation Time Estimates for EPZ Basis for Protective Actions used in EPZ during Emergency Conditions Protective Measures for the Ingestion Pathway 5.3.6 EP-AA-1012, Addendum 2 4.2, Fig. 4-2, 6.1.3 N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans,* see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see Stafe & County Plans) EP-AA-1012, Addendum 2 4.6.3 N/A (not required in Licensee Plans, see State & County Plans) A1-6 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear APPENDIX 1 NUREG-0654 Evaluation Criteria Cross Reference N/A (not required J12 Registration

& Monitoring of Evacuees in Licensee Plans, see State & County Plans) K1 -Item a Exposure Guidelines for the Removal of Injured Persons 4.7.2. K1 -Item b Exposure Guidelines for the Undertaking of Corrective

4.7.2. Actions

K1 -Item c Exposure Guidelines for Performing Assessment Actions 4.7.2. Kt -Item d Exposure Guidelines for Providing First Aid 4.7.2. K1 -Item e Exposure Guidelines for Providing Personnel

4.7.2. Decontamination

K1 -Item f Exposure Guidelines for Providing Ambulance Service 4.7.2. K1 -Item g Exposure Guidelines for Providing Medical Treatment

4.7.2. Services

K2 Onsite Radiation Protection Program 4.7 K3 24-Hour Dosimetry Service 2.1,4.7.1 N/A (not required K4 Authorization for Personnel Exposure in Excess of the in Licensee Plans, Protective Action Guides see State & County Plans) KS Determination of Need for Decontamination 4.7.2, 4.8, 5.1.7 K6 Onsite Controls 4.8, 4.4.H. K7 Capability for Decontamination of Relocated Onsite 4.8, 5.1.7 Personnel L1 Ability of Medical/Health Services to Evaluate Radiation 2.5, 2.6, 5.1.8.2, Exposure/Handle Contaminated Individuals 6.1.2, 6.2 L2 Onsite First Aid Capability 4.9, 5.1.8, 6.1.2 N/A (not required L3 Identification of Medical Services Facilities in Licensee Plans, Equipped/Trained to Treat Radiological Accident Victims see State & . County Plans) L4 Transportation to Medical Facilities 2.5, 2.6, 5.1.8 M1 Plans for Recovery/De-escalation of Protective Measures 2.4, 4.4.H. M2 Designation of Facility Recovery Organization 2.4, App. 4, Fig. 2-3. M3 Notification of Recovery Operation Initiation 2.4, 4.4.H. M4 Methodology for Periodic Exposure Estimate 4.4.G. June 2016 A1-7 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear APPENDIX 1 NUREG-0654 Evaluation Criteria Cross Reference N1 -Item a Drills to Simulate Offsite Releases 6.2 N1 -Item b Drills to Test All Elements, Time, & Weather Conditions 6.2 N2-Item a Communication Drills 6.2 N2-Item b Fire Drills 6.2 N2-Item c Medical Emergency Drills 6.2 N2-Item d Radiological Monitoring Drills 6.2 N2-Item e Health Physics Drill 6.2 N3 Drill Scenarios 6.2 N4 Official Observers/Critique 6.2 NS Improvements/Corrective Actions 6.2 01 -Item a Onsite Emergency Response Training for Offsite 6.1.2.7 Emergency Organizations N/A (not required 01 -ltemb Offsite Emergency Organization Training in Licensee Plans, see State & County Plans) . \ 02 Onsite Training/Corrective Actions 6.1.2, 6.2 I 03 Onsite First Aid Team Training 6.1.2.6 04 Response Personnel Training 6.1.2.1 thru 10 OS Annual Retraining of Personnel 6.1

• P1 Planning Personnel Training 6.1.4 P2 Designation of Planning Authority 6.3 P3 Designation of Emergency Planning Coordinator 6.3 P4 Annual Review and Update of Response Plan 6.5.1, 6.5.4 Provisions for Plan Distribution

!ind Promulgation of Plan 6.5.2, App. 1, PS 6.5.3 Revisions

• P6 Listing of Supporting Plans Section 7, References Table of P7 Procedures for Plan Implementation Contents, App. 1 P8 Table of Contents Table of Contents App. 1 pg Independent Audit of Emergency Preparedness Program 6.5.6, 6.6 P10 Updating of Telephone Numbers 6.5.5 June 2016 A1-8 EP-AA-1011 (Revision

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Calvert Cliffs Annex Appendix 2 Letters of Agreement Exelon Nuclear Letters of agreement between non-CCNPP q.nd non-Exelon agencies and individuals are maintained on file by the Emergency Preparedness Manager. ATTACHMENTS

• Calvert County Volunteer Fire & Rescue Association

• Memo from Site Vice President assigning Corporate Authority to Emergency Directors

• Calvert Memorial Hospital Emergency Department Staff Letter of Support -update not required per letter

• Radiation Emergency Assistance Center!Training Site (REAC!TS)

• Department of Energy Brookhaven Area Office dated 2002 -update not required per letter.

• Institute of Nuclear Power Operations dated 2010 -update not required per letter

• Delaware Geological Survey, University of Delaware.

• Memorandum of Understanding Regarding Communications Between Cove Point LNG Plant and the Calvert Cliffs Nuclear Power Plant *

• CCNPP Health Physics (Radiation Protection)

Guidance and Assistance for Calvert Memorial Hospital

• Maryland Emergency Management Agency *

• Maryland State Police Barrack "U" Prince Frederick

• Office of the Sheriff Calvert County

• MedStar St. Mary's Hospital

• College of Southern Maryland June 2016 A2-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Appendix 3 Emergency Plan Implementing Procedures Procedure Number Procedure Title NUREG0654 Reference EP-CE-113 Personnel Protective Actions 11.J.5, 11.J.6.c, 11.K.1, 11.K.2, EP-AA-112-500-F-53 CCNPP Offsite Monitoring Team Guidance 11.H.6.b, 11.H.7, 11.1.7, 11.J .4, 11.J.10, 11.K.3.b, 11.K.5.b, 11.K.6.b, 11.K.7, EP-CE-111 Emergency Classification and Protective 11.D.1, 11.D.2, 11.J.7, Action Recommendations 11.J.10.m, EP-CE-114-100 Emergency Notifications 11.E.2, 11.E.3, 11.E.4.a-n, 11.F.1.e, 11.F.1.f, EP-AA-112-600 Public Information Organization Activation 11.B.7.d, 11.E.7, 11.G.3, and Operation 11.G.4, 11.H.4, EP-AA-112-400 EOF Activation and Operation 11.B.2, 11.B.3, 11.B.4, 11.B.5, 11.B.7.a, 11.B.7.c, 11.B.8, l.C.2.b, 11.E.1, 11.E.2, 11.E.6, 11.F.1.b, 11.F.1.e, 11.F.1.f, 11.H.2, 11.H.4, 11.H.6, 11.H.6.b, 11.H.7, 11.H.12, 11.1.5, 11.1.7, 11.1.8, 11.1.9, 11.1.10, 11.J.1, 11.J.2, 11.J.4, 11.J.5, 11.J.7, 11.J.10, 11.J.1 O.m,11.K.5.a, 11.K.5.b, 11.K.6, 11.M.3, 11.M.4, EP-AA-112-100 Control Room Operations 11.B.2, 11.B.3, 11.B.4, 11.B.5, 11.E.1, 11.E.2, 11.E.6, 11.F.1.a, 11.F.1.b, 11.F.1.e, 11.F.1.f, 11.H.4, 11.1.2, 11.1.5, 11.1.8, 11.J.1, ILJ.4, 11.J.5, 11.J.7, 11.J.1 O.m 11.K.5.b, 11.K.7, 11.L.2, 11.L.4, 11.M.3, 11.M.4, EP-AA-112-200 TSC Activation and Operation 11.B.5, 11.B.7.b, 11.B.8, 11.H.1, 11.H.4, 11.1.5, 11.J.1, 11.J.2, 11.J.5, 11.J.6.c, 11.K.3.a, 11.K.3.b, 11.K.6, 11.K.6.c, EP-AA-112-300 OSC Activation and Operation 11.B.5, 11.H.1, 11.H.4, 11.H.5, 11.H.9, 11.1.2, 11.1.8, 11.1.9, 11.J.2, 11.J.5, 11.K.2, 11.K.3.a, 11.K.6.a, 11.K.6.b, 11.K.6.c, EP-CE-115 Termination and Recovery 11.B.7.b, 11.M.1, 11.M.3, EP-AA-110-202 CCNPP Dose Assessment 11.H.5, 11.1.3, 11.1.4, 11.1.5, 11.1.8, 11.1.9, 11.1.10, 11.J.10 ERPIP-B.1 Equipment Checklists 11.H.5.b, 11.H.6.b, 11.H.7, 11.H.9, 11.H.10, 11.H.11, June 2016 A3-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Appendix 3 Emergency Plan Implementing Procedures Procedure Number Procedure Title NUREG0654 Reference 11.1.8, 11.1.9, 11.J.6.a, 11.J.6.b, 11.K.7, ERPIP-B.2 Offsite Survey Points 11.H.5.b, 11.H.7, 11.J.4, 11.J.10 ERPIP-600 Severe Accident Management 11.1.1, ERPIP-601 Severe Accident Management Initial 11.1.1, Diagnosis ERPIP-602 Severe Accident Management Verification of 11.1.1, Diagnosis ERPIP-603 Candidate High Level Actions BD/CC 11.1.1, ERPIP-604 Candidate High Level Actions BD/CH 11.1.1, ERPIP-605 Candidate High Level Actions BD/I 11.1.1, ERPIP-606 Candidate High Level Actions BD/B 11.1.1, ERPIP-607 Candidate High Level Actions EX/CC 11.1.1, ERPIP-608 Candidate High Level Actions EX/CH 11.1.1, ERPIP-609 Candidate High Level Actions EX/I 11.1.1, ERPIP-610 Candidate High Level Actions EX/B 11.1.1, ERPIP-611 Severe Accident Management Restorative 11.1.1, Actions ERPIP-612 Candidate High Level Actions SFP Fuel 11.1.1, Uncovered ERPIP-730 Radiation Protection Hospital Assistance 11.L.1, 11.L.4, ERPIP-800 Core Damage Assessment (CDA) 11.1.1, ERPIP-801 CDA Using Containment Radiation Dose 11.1.1, Rates ERPIP-802 CDA Using Core Exit Thermocouples 11.1.1, ERPIP-803 CDA Using Hydrogen 11.1.1, ERPIP-804 CDA Using Radiological Analysis of 11.1.1, Samples ERPIP-821 Accidental Radioactivity Release Monitoring 11.H.5, 11.1.6, and Sampling Methods ERPIP-824 Dose Assessment Reference 11.1.3, 11.1.4, ERPIP-825 Meteorological Data Acquisition Methods 11.H.5, 11.1.5, ERPIP-903 Monitoring Equipment and Instrumentation 11.H.5.b, 11.H.6.b, 11.H.10, 11.1.8, 11.1.9, BG&E-EP9 Calvert Cliffs Nuclear Power Plant Accident 11.1.3 Source Term June 2016 A3-2 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities Note: The positions and responsibilities described in this Appendix apply to Calvert Cliffs station and supersede the list of ERO positions and respective ERO responsibilities identified in the Exelon Standard Plan. 1 .0 Staff Positional Responsibilities The Shift/Corporate E;mergency Director tasks are to:

• Assume overall command and control of emergency response.

• Ensure all emergency response facilities are properly staffed and activated.

• Classify emergencies.

• Direct and approve off-site emergency notifications to state and local authorities.

• Make Protective Action Recommendations to off-site authorities.

• Direct ENS communications with the NRG.

• Ensure appropriate evacuation actions for plant personnel.

• Approve the issuance of Kl.

• Approve emergency exposures.

• Integrate ERO activities with the ICP response activities.

• Authorize and prioritize requests for external assistance (governmental) as necessary.

• Authorize and prioritize requests for external assistance (off-site technical support, manpower) as necessary.

• Ensure other organization's management/decision makers (NRG, State, Exelon Generation, etc.) are kept informed of the emergency situation.

• Ensure flow of information within and between the emergency response facilities.

• Approve technical content of media statements.

• Coordinate integration of the NRG site team.

• Authorize and direct extreme measures (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Terminate the emergency event.

• Establish a recovery plan and organization.

• Conduct facility briefs and updates.

• Conduct an Inter-Facility briefing to communicate and obtain event and response information.

Direct reports to the Corporate Emergency Director are the:

• EOF Director

• Station Emergency Director

• JIG Manager C. Station Emergency Director June 2016 The Station Emergency Director reports to the Corporate Emergency Director.

This person directs the on-site ERO to provide guidance and technical assistance to the A4-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Control Room with the objective of taking the plant to a safe condition with minimal effect on the health and safety of plant personnel and the public. The Station Emergency Director tasks are to:

• Manage all on-site emergency activities in support of plant operations.

• Establish plant/station response priorities.

• Integrate ERO activities with the Incident Command Post (ICP) response activities.

• Authorize and prioritize requests for external assistance (on-site technical support, manpower) as necessary.

• Assist with emergency classification.

• Provide informational updates and recommendations to the ED, regarding plant status and activities.

• Direct ENS communications with the NRC.

• Authorize emergency response facility relocations.

• Evaluate event assessments and mitigative strategies to determine operational and response actions.

• Authorize and direct extreme measures (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Ensure appropriate accountability and search and rescue actions for plant personnel.

• Ensure accountability, once established, is maintained in all occupied areas of the station.

• Ensure appropriate evacuation actions for plant personnel.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility briefing to communicate and obtain event and response information.

• Coordinate integration of the NRC Site Team

• Assist in the development of recovery plans. Direct reports to the Station Emergency Director are the:

• TSC Director

• Technical Manager

• Operations Manager

• Maintenance Manager

• TSC Radiation Protection Manager

• Security Coordinator D. TSC Director The TSC Director oversees activation and operations of the TSC. The TSC Director tasks are to:

• Activate the Facility.

• Establish and maintain facility accountability.

• Manage the operation of the facility.

• Review and ensure facility displays are maintained current.

• Coordinate ERO shift relief rosters for the on-site facilities.

• Develop ERo'shift relief rosters for the facility.

• Perform or direct emergency PA announcements.

June 2016 A4-2 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear

• Coordinate integration of the NRC Site Team.

• Arrange for logistics support.

• Ensure flow of information within and between the emergency response facilities.

• Provide input for facility briefs and updates.

• Coordinate TSC relocation.

Direct reports to the TSC Director are the:

• TSC Administrative Staff

• RMS Communicator E. Technical Manager The Technical Manager has authority and responsibility for providing direct mechanical, and electrical engineering oversight to TSC Engineering personnel.

The Technical Manager has authority and responsibility for providing engineering support in connection with the UFSAR, ISFSI, USAR, the license, and modifications, and for overseeing activities of engineers and technicians in response to requestsfrom the on-site ERO. This support includes core protection and analysis.

This function is supported by Core I Thermal Hydraulic Engineers, a Mechanical Engineer, and an Electrical Engineer.

If necessary, contractor services may be brought to bear by these Engineering positions.

This action does not preclude the Station Emergency.

Director from soliciting contractor engineering support. The Technical Manager reports to the Station Emergency Director.

The Technical Manager tasks are to:

• Manage the activities of TSC engineering I technical staff.

• Ensure additional personnel and/or equipment is arranged for, as necessary.

• Provide engineering support for accident detection and assessment.

• Develop mitigative strategies based on assessment of the event.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Provide input for facility briefs and updates. Direct reports to the Technical Manager are the:

• Core I Thermal Hydraulic Engineers

• Electrical Engineer

• Mechanical Engineer

• TSC/OSC Computer Specialist F. Operations Manager

• June 2016 The Operations Manager is the operating supervisor in the TSC. This person provides general assistance to the Shift Manager; overall coordination of maintenance and related activities necessary to support Control Room needs; and liaison with the Station Emergency Director.

The Operations Manager reports to the Station Emergency Director.

A4-3 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear The Operations Manager tasks are to:

• Manage the activities of the TSC Operations staff.

• Assist with emergency classification.

• Provide technical assistance communication path to the Shift Manager.

• Support the establishment of plant/station response priorities.

• Provide operations support for accident detection and assessment.

• Recommend operations actions to the Shift Manager in support of restoration and accident mitigation.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Coordinate operations activities outside of the Control Room between the Shift Manager and OSC.

• Provide input for facility briefs and updates. Direct reports to the Operations Manager are the:

• Shift Manager

• ENS Communicator

• TSC Ops Communicator

• CR Ops Communicator G. Maintenance Manager The Maintenance Manager has authority and responsibility for mechanical, electrical and instrument corrective actions and for providing support for on-site protective actions, plant operations, and reentry and recovery.

The Maintenance Manager tasks are to:

• Provide input into mitigative strategies.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Coordinate repair and OSC team task information between the TSC and OSC.

• Provide input for facility briefs and updates. Direct reports to the Maintenance Manager are the:

• OSC Director H. Operations Support Center Director June 2016 The Operations Support Center (OSC) Director reports to the Maintenance Manager, or in this person's absence, the TSC Operations Manager or the Shift Manager. The OSC Director tasks are to:

• Activate the Facility.

• Manage the operation of the facility.

• Develop ERO shift relief rosters for the facility.

• Ensure flow of information within and between the emergency response facilities.

• Support the establishment of plant I station response priorities.

A4-4 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear

• Direct accountability and search & rescue activities.

• Establish and maintain facility accountability.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Coordinate OSC team dispatch and control.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility Briefing to communicate and obtain event and response information.

Direct reports to the OSC Director are the:

• Assistant OSC Director

• OSC Team Tracker

• OSC Ops Communicator

• OSC Admin Staff The Assistant OSC Director coordinates in plant task and team development and team dispatch.

Direct reports to the Assistant OSC Director are the:

• Maintenance Group Leads (Electrical, l&C, Mechanical),

• Chemistry Lead

• RP Lead

• Operations Lead NOTE: OSC Group Leads can be pre-designated or assigned from qualified individuals in the OSC personnel Pool. The Maintenance Group Leads coordinate their teams' activities for repair and damage control (mechanical, electrical, instrument).

The teams are responsible for assessing equipment damage and affecting repairs. Maintenance Group Leads report to the OSC Director.

Technicians reporting to and coordinated by the Maintenance Group Leads include:

• Mechanical Technicians

• Electrical Technicians

• Instrument Technicians The Operations Lead directs extra operators who comprise the Operations Team for support as requested by the Control Room. The Operations Team supplements on shift operators for operations tasks. The Operations Lead reports to the OSC Director.

I. TSC Radiation Protection Manager June 2016 The TSC Radiation Protection Manager (RPM) has authority and responsibility for site radiation protection and personnel radiation exposure control. The TSC RPM also coordinates with the EOF Radiation Protection Manager for support. The TSC RPM reports to the Station Emergency Director.

A4-5 . EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear The TSC RPM tasks are to:

• Manage and direct the radiological activities of the RP personnel.

• Ensure additional personnel and/or equipment is arranged for, as necessary.

• Provide radiological support for accident detection and assessment.

• Monitor, evaluate and communicate conditions involving any release of radioactivity.

• Provide support and logistics for site evacuation activities.

• Evaluate the need for and ensure proper use of Kl.

• Ensure habitability is established and maintained for occupied on-site areas.

• Ensure proper emergency exposure controls are taken for personnel.

• Provide radiological assistance for planning rescue operations and repair team monitoring.

• Direct personnel decontamination activities.

• Provide radiological assistance for the transfer of injured and/or contaminated personnel.

• Provide input for facility briefs and updates. The Shift Radiation Protection Technician (staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) assumes this position at . emergency onset and retains it until relieved by augmenting personnel.

The TSC RPM coordinates radiation protection and assessment activities with the OSG Radiation Protection Lead. They are responsible for Iodine Sampling, Radiological Job Coverage, Radiological Access Control and Emergency Response Facility monitoring (Control Room, Technical Support Center, Operations Support Center, Nuclear Security Facility, and the South Service Building Cafeteria).

J. Security Coordinator June 2016 The Security Coordinator coordinates security activities with the radiological emergency response.

The Security Coordinator tasks are to:

• Integrate ERO activities with the ICP response activities.

• Manage the activities of the site security force.

• Request and coordinate emergency activities with Local Law Enforcement Agencies (LLEAs).

• Provide security related communications with the NRC.

• Direct accountability and search & rescue activities.

• Direct site evacuation activities.

• Direct site access controls activities.

• Coordinate security activities between the SSS and OSC.

• Determine radiation protection measures for security force personnel and law enforcement agency personnel on site.

• Provide input for facility briefs and updates. The Security Shift Supervisor reports to the Security Coordinator when the TSC is activated.

The Security Shift Supervisor has the authority to and is responsible for implementing the Nuclear Security Plan. The Security Shift Supervisor position also supports personnel accountability activities.

A4-6. EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear K. Emergency Operations Facility Director The Emergency Operations Facility (EOF) Director oversees EOF operations.

This responsibility includes information flow, interfacing with State and County Representatives and assisting Corporate Emergency Director as directed.

The EOF Director tasks are to:

• Activate the Facility.

• Manage the operation of the facility.

• Assist off-site agency personnel responding to the facility.

• Coordinate integration of the NRC site .team.

• Assist with emergency classification.

• Support the completion of timely off-site event notifications to State and local authorities.

• Evaluate conditions and determine recommendations for PARs.

• Assist in the development of recovery plans.

• Participate in the Inter-Facility briefing to communicate and obtain event and response information.

• Provide input for facility briefs and updates. Direct reports to the EOF Director are the:

• State I Local Communicator

• EOF Technical Advisor

• EOF Radiation Protection Manager

• EOF Logistics Manager

• EOC Communicator

• L. EOF Radiation Protection Manager June 2016 The EOF Radiation Protection Manager (RPM) reports to the EOF Director.

This position has authority and responsibility to assess, map, and coordinate calculations of radiological data required to depict on-site and off-site radiation dose and/or exposure rates. This position evaluates radiological conditions and makes recommendations to the Corporate Emergency Director.

The EOF RPM tasks are to: * * * * * * * *

• * *

• Manage and direct the radiological activities of the offsite RP personnel.

Coordinate activities with the external agency field monitoring teams . Coordinate the comparison and exchange of dose assessment results with off-site agency personnel.

Assist with emergency classification . Monitor, evaluate and communicate conditions involving any release of radioactivity . Oversee the performance and evaluate the results of dose projection activities . Perform dose assessment.

Oversee the performance and evaluate the results of OMT activities . Provide support and logistics for site evacuation activities . Evaluate the need for and ensure proper use of Kl. Evaluate conditions and determine recommendations for PARs . -Ensure proper emergency exposure controls are taken for personnel.

A4-7 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear

• Provide assistance to state and federal agencies for ingestion pathway radiological activities.

• Provide input for facility briefs and updates. Direct reports to the EOF RPM are the:

• HPN Communicator

• Dose Assessor(s)

• Environmental Coordinator M. EOF Logistics Manager The EOF Logistics Manager reports to the EOF Director.

This position has authority and responsibility to provide administrative support to the EOF and logistics support to the entire ERO. The EOF Logistics Manager tasks are to:

• Ensure ERO personnel have been properly notified and are responding to the facilities.

• Oversee staffing of EOF and assist with staffing for other facilities.

• Develop ERO shift relief rosters for the facility.

• Coordinate ERO shift relief rosters for all facilities and the notification of personnel.

• Manage the administrative support staff.

• Review and ensure facility displays are maintained current. * . Manage the procurement and logistical support activities for the on-site and off-site emergency response personnel and facilities.

• Monitor and maintain access controls for the *facility.

• Comrriunicate with and coordinate support for ERO responders or plant personnel sent off-site to relocation areas.

• Provide input for facility briefs and updates Direct reports to the EOF Logistics Manager are the: *

• EOF I JIG Computer Specialist

• EOF Admin Staff N. EOG Communicator June 2016 The EOG Communicator reports to the EOF Director.

This position has the responsibility to coordinate information flow to the off-site representatives located in the EOF and Calvert Cliff liaisons located at the off-site Emergency Operations Centers. The EOG Communicator tasks are to:

• Monitor plant conditions and event response activities.

• Provide information updates to and address questions and support requests from the off-site liaisons.

• Notify and brief external agencies and groups (INPO, ANI) of the emergency event.

• Provide input for facility briefs and updates. A4-8 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Direct reports to the EOG Communicator are the:

• State Liaison

• County Liaisons 0. EOF Technical Advisor The EOF Technical Advisor provides technical expertise to the EOF Staff. The EOF Technical Advisor tasks are to:

• Assist with emergency classification.

• Monitor plant status and Control Room activities.

• Provide input for facility briefs and updates. Direct reports to the EOF Technical Advisor are the:

• EOF Operations Communicator P. Joint Information Center Manager June 2016 The Joint Information Center (JIG) Manager oversees operations of the JIG. The JIG Manager tasks are to:

• Activate the Facility.

• Manage the operation of the facility.

• Assist off-site agency personnel responding to the facility.

• Coordinate integration of the NRG Site Team.

• Provide liaison to the NRG Site Team.

• Arrange for support for Emergency Alert System (EAS) information.

• Ensure flow of information within and between the emergency response facilities.

• Interface with off-site agency Public Information Officers (PIOs) to coordinate overall information flow to the media and public.

• Coordinate facilitation of the media briefing schedule.

• Ensure news media briefings are held regularly during the course of the emergency.

• Oversee conduct of media briefings.

• Integrate ERO activities with the Incident Command Post (ICP) response activities

• Assist in the development of recovery plans.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility Briefing to communicate and obtain event and response information.

Direct reports to the JIG Manager are the:

• Company Spokesperson

• Media Monitoring I Rumor Control Coordinator

• JIG Logistics Manager A4-9 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Q. Company Spokesperson The Company Spokesperson interfaces with Corporate Communications and acts as spokesperson to the media at the JIC.

• Establish ongoing contact with the communications personnel in the corporate office.

• Interface with offsite agency Public Information Officers (PIOs) to coordinate overall information flow to the media and public.

• Provide interviews to the media.

• Serve as Company Spokesperson during press conferences at the JIC.

• Participate in the Inter-Facility Briefing to communicate and obtain event and response information.

• Provide input for facility briefs and updates. R. Media Monitoring I Rumor Control Coordinator The Media Monitoring I Rumor Control Coordinator oversees the media monitoring and rumor control staffs. The Media Monitoring I Rumor Control Coordinator tasks are:

• Supervise media monitoring and Inquiry Phone Team personnel.

• R_eview Media Monitoring team information for trends, misinformation and rumors.

• Review Phone Team information for trends, misinformation and rumors.

• Ensure adequate staff is available to perform media monitoring and phone team functions.

• Provide input for facility briefs and updates. Direct reports to the Media Monitoring I Rumor Control Coordinator are the:

• Inquiry Phone Team

• Media Monitoring Team S. JIC Logistics Manager June 2016 The JIC Logistics Manager oversees development of media statements and administrative support of the JIC. The JIC Logistics Manager tasks are:

• Manage the administrative support staff.

• Develop ERO shift relief rosters for the facility.

• Arrange for logistics support.

• Oversee set-up and testing of JIC equipment.

• Maintain access control to the JIC.

• Provide input for facility briefs and updates.

• Oversee collection of technical data and station activities for drafting Media Statements and answering JIC questions.

• Coordinate preparation, review and distribution of Media Statements.

• Obtain Corporate ED approval for the technical content of Media Statements.

A4-10 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Direct reports to the JIG EOF Logistics Manager are.:

• JIG Administrative Staff

• Media Liaison

• JIG Security

• News Writer

• JIG Technical Advisor T. Communicators June 2016 Communicators report to the director of their respective emergency center. Communicators have responsibility for communications according to Emergency Plan Implementation Procedures.

Communication responsibilities include initial and up communications with Calvert Cliffs Nuclear Power Plant, State, local and Federal personnel; communications with regulatory agencies through the Emergency Notifications System; and communication of plant parameter status data, environmental status data, Radiological Monitoring System status data; and communications between emergency response facilities.

A4-11 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear APPENDIX 5 Liquefied Natural Gas Contingency I. DEFINITIONS A. Liquefied Natural Gas Liquefied natural gas is mainly methane gas cooled to about -260°F so it changes from a gas to a liquid. B. Methane Methane is a colorless, odorless gas that is flammable in concentrations of 5% and greater. It is positively buoyant with respect to air above about 60°F. II. POTENTIAL THREAT The relative proximity of the Cove Point Liquefied Natural Gas Terminal to Calvert Cliffs Nuclear Power Plant creates the possibility that abnormal occurrences at the Liquefied Natural Gas Terminal, such as a spill of Liquefied Natural Gas, could pose a potential threat to the safety to equipment and/or personnel at Calvert Cliffs Nuclear Power Plant. The worse case occurrence at Cove Point with respect to Calvert Cliffs Nuclear Power Plant would be a large scale 25,000 m3 spill of Liquefied Natural Gas from an Liquefied Natural Gas tanker directly onto the surface of the Chesapeake Bay in the vicinity of the unloading pier. Such a spill is postulated to occur if a Liquefied Natural Gas-laden tanker is involved in a collision with another vessel whereby one or more of the Liquefied Natural Gas tanks aboard the tanker is ruptured.

• Releases of a smaller size or release from an onshore storage tank have been analyzed and shown to pose no significant threat at Calvert Cliffs Nuclear Power Plant (Liquefied Natural Gas References A, B, and C). A significant Liquefied Natural Gas spill to the Chesapeake Bay from a ruptured tank of an Liquefied Natural Gas tanker in the vicinity of the Calvert Cliffs Nuclear Power Plant poses two potential hazards to the personnel and/or operations of the plant. With appropriate atmospheric and bay conditions, a methane vapor cloud emanating from a spill could extend from the spill area to the plant vicinity, engulf portions of the plant, and then ignite. The resultant heat energy released could be hazardous to personnel and could damage equipment.

Additionally, should a flammable concentration of methane vapor fill a confined space or room, an explosion could occur if it ignited. A specific hazard created by methane vapor is the possibility of asphyxiation if the concentration is great enough to reduce oxygen to below minimum life-support levels (approximately 17%). June 2016 A5-1 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear The development and subsequent dispersion of a methane vapor cloud could occur as follows: Liquefied Natural Gas (a very cold liquid) is lighter than water and insoluble in water and will form a pool on the surface of water if spilled. As it pools, it absorbs heat from the water. Heating Liquefied Natural Gas causes it to vaporize i_nto methane gas. As the Liquefied Natural Gas pool spreads, the rate of vapor generation increases because there is more surface area for heat absorption.

The diameter of the resulting vapor cloud normally will be muGh greater than its height, since vertical mixing will be inherent due to local temperature inversion by the still cold methane gas cloud. Although methane vapor is colorless, the cloud will appear white due to condensation and/or freezing of water vapor condensed from atmosphere onto the cloud surface. The initial bulk temperature of newly vaporized methane is approximately

-250°F. At this temperature and at atmospheric pressure, methane vapor is approximately 50% more dense than ambient air. Consequently, there is no tendency for the cloud to rise. Experimental datc:t indicates that the vapor cloud continues to spread radically, and there is very little vertical dispersion.

Entrainment of air increases the cloud temperature, but generally, the density of the mixture remains above that of the diluting air. In instances where the heat input from the surface of the water, and/or heat input from the condensing and freezing of atmospheric water vapor is significant, the vapor cloud may become positively buoyant, thus terminating the threat to Calvert Cliffs Nuclear Power Plant since the methane will rapidly mix vertically and disperse.

Once a methane cloud begins to form, atmospheric and wind conditions may be such that the cloud could propagate toward Calvert Cliffs Nuclear Power Plant. Wind speeds of 5-15 mph with stable atmospheric conditions and wind direction from the spill to the plant are necessary to transport the cloud to Calvert Cliffs Nuclear Power Plant. As the cloud moves downwind, it is further diluted and dispersed by turbulent mixing with surrounding air. In the absence of ignition, this process would continue until the concentration of methane in the cloud reduced to the Lower Flammability Limit, about 5% methane, and the methane is totally dispersed into the. atmosphere (on the order of 20 minutes).

If at any point in the vapor cloud the methane concentration is between 5%.and 15% (Lower Flammability Limit and Upper Flammability Limit, respectively) and an ignition source is present, the vapor cloud will ignite. It will then slowly burn back to the source of the spill at a rate dependent upon the wind conditions.

The cloud continues to burn until the concentration of methane is reduced below 5%. A land-based spill at Cove Point will present no hazard to the plant or to plant personnel.

This is principally due to the limited heat source provided by land versus water for Liquefied Natural Gas vaporization and intervening terrain between Cove Point and Calvert Cliffs Nuclear Power Plant. An accident will threaten the safety of the plant and personnel only if it is a major Liquefied Natural Gas spill from a tanker and the meteorological and bay conditions are such that the resulting vapor cloud can travel the 3 to 4 miles to Calvert Cliffs Nuclear Power Plc:tnt. If there is no vapor ignition, the major concern is protection of the plant personnel in an oxygen deficient atmosphere.

If the plume* ignites away from the plant structure additional concern is to heat flux generated by the burning cloud that could harm exposed personnel.

By taking appropriate actions, hazards to plant personnel could be avoided, and threats to safety of the plant can be minimized.

J_une 2016 A5-2 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear III. CONCERNS AND ACTIONS IN A LIQUEFIED NATURAL GAS EMERGENCY The exclusion of methane from the Control Room is vital to plant safety and should be of utmost concern. Control Room ventilation system alignment must be considered as soon as a Liquefied Natural Gas threat is identified.

Plant operational needs will have to be considered and adjustments made if warranted.

Ventilation systems including the battery ventilation systems may have to be secured or isolated from outside intakes. Electrical lineups may have to be changed to preserve the ability of the plant to supply vital loads. Doors and other outside openings to plant structures may have to be secured. Methane ignition could result in a large scale fire in the vicinity of plant structures.

Such a fire could place a significant heat load on equipment or could result in serious personnel injury .. Methane incursion into confined spaces with subsequent ignition could result in an explosion.

Methane concentrations may vary from area to area. Careful monitoring for methane concentrations in specific locations of interest, (i.e., inside a pump motor casing or inside of an electrical panel, etc.) should be performed prior to starting up equipment.

Methane can asphyxiate and can result in dizziness, unconsciousness or even death if inhaled in sufficient concentrations.

Personnel must take appropriate precautions such as the use of self-contained or airline respiratory devices. Access to the site could be affected by the presence of methane or a methane fire. Alternate means of routing assistance on-site and of removing personnel (e.g., for medical purposes) will be considered.

The free movement of personnel outside of plant structures may be impossible, and thus early, prompt actions and decisions may be required.

IV. COMMUNICATIONS Emergency Plan Implementation Procedures describe communication networks between Calvert Cliffs Nuclear Power Plant and the Cove Point Liquefied Natural Gas Plant. V. LIQUEFIED NATURAL GAS REFERENCES A. Liquefied Natural Gas (LNP) Hazards for Calvert Cliffs Nuclear Power Plant Final Report, May 28, 1993. B. Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Liquefied Natural Gas Hazards Study, "Safety Evaluation by the Office of Nuclear Reactor Regulations (USNRC) Regarding the Proximity of the Cove Point Facility," March 13, 1978. June 2016 A5-3 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear C. Calvert Cliffs Nuclear Power Plant, Units 1 and 2, "Liquefied Natural Gas Hazards Update," March 9, 1978. D. Risk Assessment Study for the Cove Point, Maryland Liquefied Natural Gas Facility, Science Applications, Inc. La Folla, CA, SIA-789-626-LJ, March 23, 1978. E. Cove Point LNG Project Docket No. CPo1-76-000.

July 2001 F. NRC Letter to Calvert Cliffs Nuclear Power Plant, "Liquefied Natural Gas Hazard Analysis -Calvert Cliffs Nuclear Power Plant, Unit No. 1 (TAC No. M86704) and Unit No. 2 (TAC NO. M86705)." August 31, 1995. G. Maryland Power Plant Research Program, "Cove Point LNG Terminal Expansion Project risk Study." June 28, 2006. DNR 12-7312006-147, PPRP-CPT-01.

H. Constellation Energy Nuclear Generation Group Letter to the U.S. Nuclear Regulatory Commission. "Calvert Cliffs Nuclear Power Plant; Unit Nos. 1 &2; Docket Nos. 50-317 & 50-318, Independent Spent Fuel Storage Installation; Docket No. 72-8, revision to Hazards Analysis Related to Liquefied Natural Gas Plant operations at Cove Point." February 20, 2008. I. NUREG-1407, "Protocol and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities." Final Report Published June 1991. June 2016 A5-4 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Appendix 6 Calvert Cliffs Communication Equipment 1 . Plant Page A.

Description:

CCNPP is divided into six paging zones with an All Call and Priority Paging option. 2. Administrative Telephone System -Commercial phones system located at each of the ERFs that provide communications between facilities and outside agencies.

3. 4. Dedicated Offsite Agency Telephone A.

Description:

1. Provides communications between CCNPP locations and offsite emergency facilities.

2. Provides offsite agencies with the capability to independently dial other outside agencies and CCNPP or Emergency Operations Facility locations.

3. Utilizes dedicated, leased telephone lines via CCNPP telephone system network. 4. Battery-backed power supply provides for full system operability in the event of loss of AC power. 5. Dedicated Offsite Agency phone bcated onsite is equipped with one or more standard outside telephone lines for access to Administrative Telephone System features (for example, plant page) and routine outside system dialing. 8. The dedicated Offsite Agency Telephones are located in the Control Room, EOF, Safe Shutdown Panels .

• Microwave Telephones

("Hot Li.nes") The Microwave telephones provide direct, point-to-point communications via company owned microwave system. The Microwave Telephones are located at the following locations:

• From Emergency Operations Facility (Dose Assessment Room) to the Electric Operations Building

• From the Emergency Operations Facility (Dose Assessment Room/ State Room) to the Maryland Department of Environment

• From the Emergency Operations Facility to. the Information Technology, Operations and Technical Support Dept (Owings Mills Facility)

• From the Emergency Operations Facility (Security Room) to the Corporate Security (Owings Mills Facility)

5. FTS-2001 Telephone System The FTS 2001 Telephone System provides CCNPP and onsite NRC personnel direct communications with NRC Operations Center using dedicated telephone systems. FTS-2001 provides separate phones for:

• Emergency Notification System (ENS) -Initial Notification by CCNPP to NRG June 2016 A6-5 EP-AA-1011 (Revision

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Calvert Cliffs Annex Exelon Nuclear Operations Center (identified by the red label). (MGR, EOF, TSC)

• Health Physics Network (HPN) -Initial Notification by CCNPP to NRG Operations Center (identified by the red label). (EOF, TSC, TSC Annex)

• Reactor Safety Counterpart Link (RSCPL) -For discussions between onsite and offsite NRC representatives on plant and equipment conditions. (TSC, EOF)

• Protective Measures Counterpart Link (PMCPL) -For internal NRC discussions on radiological releases, meteorological conditions, and the need for protective actions. (TSC, EOF)

• Management Counterpart Link (MCL) -For internal discussions between NRC Executive Team Director and NRC .Director of Site Operations. (TSC, EOF) 6. Plain Old Telephone System (POTS) Plain Old Telephone System (POTS) phones provide backup communications for the Emergency Response Organization to utilize when needing to communicate information between CCNPP Emergency Response Facilities and to Offsite_ Agencies.

The POTS phones are located in the following locations: 1 . Control Room 2. TSC 3. osc 4. SAS 7. Emergency Response Radio Network Description

-The Calvert Cliffs Radio system consists of a CCNPP-owned 800 MHz radio system which provides communications between emergency centers. The system consists of Communication Control Units, Desk Set Control Units, Mobile Radios and Hand Held Units. The Radio system provides backup communications between CCNPP and otfsite agencies, as well as communication between CCNPP radiological monitoring teams and emergency centers, Security, NPO/First Aid/Fire Brigade and Control Room. Radio Units are located in the following locations:

• Central Alarm Station

• Secondary Alarm Station

• Control Room (CRS desk)

• Operational Support Center

• Technical Support Center

• Technical Support Center Annex

• Emergency Operations Facility -Dose Assessment Room

• Emergency Operations Facility -Security Room

• Emergency Operations Facility -Communicator

• Farm Demo Building

• Nuclear Office Facility

• Secondary Fire Brigade Locker (B.5.b Equipment)

• Mobile radios are maintained in several vehicles assigned to CCNPP. June 2016 A6-6 EP-AA-1011 (Rev.ision

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Calvert Cliffs Annex Exelon Nuclear 8. LNG.( Cove Point) Automatic Ringdown Telephone A.

Description:

1. Cove Point owned/operated commercial dedicated phone line. 2. A dedicated line between the Cove Point LNG Monitoring Station and the CCNPP Control Room. This line is to be used by Cove Point personnel to notify CCNPP of expected tanker arrivals and emergency situations concerning the LNG operations.

B. Location:

1. CCNPP Control Room 2. Cove Point LNG Monitoring Station 9. LNG (Cove Point) Emergency Radio A.

Description:

Provides back-up communications for the dedicated phone between CCNPP Control Room and Cove Point LNG Plant Monitoring Station via the Control Room console and LNG Plant hand-held radio. B. Location:

June 2016 1. Cove Point LNG Plant Monitoring Station (hand-held radio) 2. CCNPP Control Room (communications console programmed with dedicated group LNG Plant hand-held radio) A6-7 EP-AA-1011 (Revision

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ATTACHMENT 3 EP-AA-1012, Revision 3, "Exelon Nuclear Radiological Emergency Plan Annex for Ginna Station" Emergency Plan Annex Revision

% ,If Exelon Generation EXELON NUCLEAR EP-AA-1012 Revision 3 RADIOLOGICAL EMERGENCY PLAN ANNEX FOR GINNA STATION Ginna Annex Exelon Nuclear REVISION HISTORY Revision 0: 02/15 Revision 1: 07/15 Revision 2: 09/15 Revision 3: 06/16 June 2016 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Section 1: 1.1 1.2 1.3 Section 2: 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 TABLE OF CONTENTS Page No. Introduction

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

1-1 Purpose .......................................................................................

1-1 Management Oversight

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

1-2 Summary of Emergency Plan ............ .........................................

1-3 Organizational Control of Emergencies

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

2-1 On-Shift Emergency

_Response Organization Assignments

.........

2-1 Authority Over the Emergency Response Organization

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

2-1 Criteria for Assuming Command and Control (Succession)

.........

2-1 Non-Delegable Responsibilities

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

2-2 Emergency Response Organization Positional Responsibilities

.. 2-2 Emergency Response Organization Block Diagram ....................

2-3 _ Corporate Emergency Response Organization

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

2-3 Augmentation of the Emergency Organization and Interface with Other Plans .............

_. ............................................................

2-3 2.9 Industry/Private Support Organizations

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

2-6 2.1 O Supplemental Emergency Assistance to the ERO .......................

2-6 2.11 Other Emergency Plans ...............................................................

2-9 Table 2.1 Minimum Staffing Requirements for the ERO ....................

2-10 Figure 2.1 Shift ERO ...........................................................................

2-14 Figure 2.2 ERO Management Structure

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

2-15 Figure 2.3 TSC Staffing .... : .........................................*.......................

2-16 Figure 2.4 OSC Staffing ......................................................................

2-17 Figure 2.5 EOF Staffing ......................................................................

2-18 Figure 2.6 JIC 2-19 Figure 2.7 Inter-Relationships of Ginna Station Emergency Section 3: 3.1 3.2 3.3 3.4 3.5 Section 4: 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 June 2016 Response Organizations

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

2-20 Classification of Emergencies

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

3-1 Local Radiation Emergency

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

_ .........................

..........

3-1 Unusual Event .............................................................................

3-2 Alert .............................................................................................

3-2 Site Area Emergency

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

3-2 General Emergency

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

_ ....................................................

3-3 Emergency Measures ..................

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

4-1 Local Radiation Emergency

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

4-1 Unusual Event ...................*.........................................................

4-1 Alert .........................................................

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

.' ............

4-2 Site Area Emergency

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

4-4 General Emergency

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

4-4 Activation of Emergency Response Organization

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

4-5 Immediate Assessment.

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

4-6 Subsequent Actions ........ ............................................................

4.:.7 -ii EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 4.9 Onsite Protective Actions .............................................................

4-9 4.10 Major Release to Lake Ontario or Deer Creek ...........................

4-13 4.11 Public Relations

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

4-17 Figure 4.1 Ginna Notification Process ................................................

4-3 Figure 4.2 Evacuation Routes ..........................................................

4-12 Table 4.1 Recommended Protective Actions to Reduce Whole Body and Thyroid Dose ........................................

4-15 Section 5: Emergency Facilities and Equipment

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

5-1 5.1 Emergency Response Facilities

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

5-1 5.2 Communications Systems (Ginna Station) ..................................

5-6 5.3 Assessment Facilities

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

5-8 5.4 Protective Facilities

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

5-22 5.5 First Aid and Medical Facilities

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

5-24 Figure 5.1 Ginna Station Emergency Centers Interfaces

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

5-2 Figure 5.2 Dosimeter Locations

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

5-19 Table 5.1 A Effluent Radiation Monitors ..............................

• ...............

5-11 Table 5.1 B SPING 4. Radiation Monitoring System ...........................

5-13 Table 5.1C Area Monitors ..................................................................

5-14 Section 6: 6.1 6.2 6.3 6.4 Maintaining Nuclear Emergency Preparedness

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

6-1

• Training and Drills ........................................................................

6-1 Annual Review and Revision of the Plan and Procedures

...........

6-4 Emergency Equipment and Supplies ...........................................

6-5 Auditing ........................................................................................

6-5 Section 7: Recovery ..........................................................................................

7-1 7 .1 Recovery Actions .........................................................................

7-1 Section 8: Definitions

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

8-1 APPENDICES

1. NUREG-0654 Evaluation Criteria Cross Reference

2. Letters of Agreement

3. Emergency Plan Implementing Procedures

4. Emergency Response Organization Responsibilities

5. Summaries of Interfacing Emergency Plans ADDENDUMS Addendum 1, Ginna Station On-Shift Staffing Analysis Report Addendum 2, Evacuation Time Estimates for the Ginna Station Emergency Planning Zone Addendum 3, Emergency Action Levels for Ginna Station June 2016 iii EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Section 1: Introduction As required in the conditions set forth by the Nuclear Regulatory Commission (NRC) for . the operating licenses for the Exelon Nuclear Stations, the management of Exelon recognizes its responsibility and authority to operate and maintain the nuclear power stations in such a manner as to provide for the safety of the general public. The Exelon Emergency Preparedness Program consists of the Exelon Nuclear Standardized Emergency Plan (E-Plan), Station Annexes, emergency plan implementing procedures, and associated program administrative documents.

The Exelon E-Plan outlines the basis for response actions that would be implemented in an emergency.

Planning efforts common to all Exelon Nuclear stations are encompassed within the E-Plan.

• This document serves as the Radiological Emergency Plan Annex for Ginna Station and contains information and guidance that is unique to the station. This includes the facility geography location for a full understanding and representation of the station's emergency response capabilities.

The Station Annex is subject to the same review and audit requirements as the Exelon Nuclear Standardized Emergency Plan.* 1.1 Purpose The Exelon Nuclear Standardized Emergency Plan and Ginna Station Annex describes the total preparedness program established, implemented and coordinated by R. E. Ginna Nuclear Power Plant LLC and the resources and capabilities available from Exelon, hereinafter referred to as "the Company", to ensure the capability and readiness for coping with and mitigating both onsite and offsite consequences of radiological emergencies at Ginna Station. The plan covers the spectrum of emergencies from minor localized incidents to major emergencies involving protective measures by offsite response organizations.

Included are guidelines for immediate response, assessment of emergency situations, defined action criteria and delineation of support and recovery functions.

Emergency Plan Implementing Procedures (EPIPs) and fleet procedures provide detailed information for individuals who may be involved with specific emergency response functions.

The Emergency Plan Annex provides for a graded scale of response for distinct classifications of emergency conditions, actions within those classifications, and criteria for escalating to a more severe classification.

This classification system is identical to that used by the State of New York and the local (Wayne and Monroe County) emergency response agencies.

The plans have four categories of emergencies:

Unusual Event, Alert, Site Area Emergency and General Emergency.

A fifth condition, Local Radiation Emergency, has been added. A Local Radiation Emergency is less severe than an Unusual Event and does not involve any offsite organization.

The Emergency Plan describes the activities and provisions other than engineered safety systems which are intended to limit exposures to the general June 2016 GN 1-1 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear public as well as to plant personnel.

The Emergency Plan covers the following

• conditions:

1) Major release to the atmosphere.

2) Major release to the lake. 3) Abnormally high radiation or airborne radioactivity in a particular area of the plant. 4) Plant conditions that may lead to potential releases.

NOTE: Offsite Transportation accidents are covered by Radiation Protection Procedures (RP Procedures) and do not require classification in this Plan. The Company has the immediate and continuing responsibility for limiting the consequences of an incident at the Ginna Nuclear Power Plant. Limiting the consequences to public health and safety should take *clear precedence over limiting financial loss or adverse publicity.

During a radiological emergency, the Company should take whatever action is deemed necessary to limit the consequences to* public health and safety, even if that action violates the Ginna Technical Specifications.

Such actions would req1;1ire prior approval, as a minimum, by a licensed Senior Reactor Operator and follow-up notification to the NRC in accordance with 1 OCFR50.54 (x) and (y). The Company is responsible for keeping Federal, State and local authorities informed of the status of the emergency as it relates to protection of the public health and safety. The Company will recommend to Federal, State and local authorities specific protective actions to limit the danger to the public, including evacuation.

The Company understands that it is the Nuclear Regulatory Commission's policy that the emergency should be managed by the licensee.

The NRG Headquarters Staff is *limited in its ability to provide detailed recommendations to plant personnel or plant managers at the site. The Company understands that the NRC Operations Center will be the primary location where this agency will monitor and evaluate licensee actions. During that time, the normal response roles for the NRC Operations Center will be to monitor, inform, and, upon request, advise licensees and other Federal, State and local authorities.

The authority for managing the NRC's emergency response efforts will be transferred to a senior onsite NRG representative when the NRG Headquarters Staff is confident the onsite representatives are prepared to receive that authority.

Their role will continue to be monitoring, informing, and advising plant and local authorities.

1 .2 Management Oversight:

Management oversight of the Emergency Preparedness program is provided by the Emergency Preparedness Advisory Committee.

The details of the board's activities are contained in EP-AA-120-1004, Emergency Preparedness Advisory Committee.

June 2016 GN 1-2 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 1.3 Summary of Emergency Plan The primary objective of this plan is to protect the public and onsite personnel in the event of a radiation emergency.

This plan describes in general the actions to be taken by Company personnel in coordination with Federal, State and local authorities.

Through an emergency organization which is described, the magnitude and impact of radioactive releases will be assessed and the need for the activation of a more extensive emergency response will be determined.

The systems for notification of emergency personnel, Federal, State and local authorities, and the public are described along with the emergency facilities and equipment which are available for the trained emergency staff. The goal of the Ginna Station emergency organization is the safe shutdown and recovery of the Station and protection of the health and safety of the public and employees.

The general actions to be taken in the event of a radiation .accident include the following:

1) Observation and determination of.the classification of the occurrence.

2) Prevention or minimization of radiation hazards by the. Emergency Director and the on-duty operators.

3) Evacuation of all non-essential personnel from the *plant to the Ginna Training Center or other location, as appropriate.

4) Involvement of plant security personnel, supervisory personnel, Chemistry and Radiation Protection personnel, and other plant staff. 5) Notification of NRC Operations Center and State and local authorities, issuance of news releases, and emergency medical treatment.

6) Activation of Emergency Response Organization.

7) . Recovery and restoration of the plant to normal operation.

The extent of response to. an emergency situation is determined by the seriousness of potential consequences.

With the potential for effects to the

• general public, the assistance of Federal, State and loc?I agencies will be required.

For situations which only affect onsite operations, the situation will be handled by the Company. The awareness of an emergency situation will most likely originate in the Control Room. From an evaluation of plant parameters, the seriousness of the incident can be determined and the appropriate classification determined.

The on-duty plant operators, under the direction of the Shift Emergency Director, in consultation with the Shift Technical Advisor, will take action to mitigate the incident and to obtain the assistance of other plant and Company personnel.

Personnel onsite will be alerted by a warning signal if evacuation is deemed advisable and off-duty personnel will .be called in through an established call procedure.

Federal, State and county officials will be notified so that they may begin to set up their response organizations.

If the level of the incident requires June 2016 GN 1-3 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear activation of the emergency organization, trained people will staff the Technical Support Center, Operations Support Center, Emergency Operations Facility and Joint Information Center. These centers will be activated, per procedure, by designated people who have been trained in the duties required to meet the incident.

Sufficient individuals are trained so that the positions can be filled regardless of who is onsite or available for call-in. Public officials will be kept informed of the situation as it progresses.

For certain classes of events, the EOF will be activated for continuing management of the incident and to assist in restoring the plant to normal operation.

A Joint Information Center will be activated to keep the public aware of the situation and news releases will be coordinated among the Company, New York State and other government agencies.

June 2016 GN 1-4 . EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Section 2: Organizational Control of Emergencies This section describes the Exelon Emergency Response Organization (ERO), its key positions and associated responsibilities.

It outlines the staffing requirements which provide initial emergency response actions and provisions for timely augmentation of on-shift personnel when required.

It also describes interfaces among emergency response personnel and specifies the bffsite support available to respond to the nuclear generating stations.

Figures 2.1 through 2.7 show the interfaces between and among the ERO functional areas. 2.1 On-Shift Emergency Response Organization Assignments The initial phases of an emergency situation at a nuclear station will most likely involve a relatively small number of individuals.

These individuals must be capable of (1) determining that an emergency exists; (2) providing initial classification and assessment; and (3) promptly notifying other groups and individuals in the emergency organization.

The subsequent phases of the emergency situation may require an increasing augmentation of the emergency organization.

All Exelon Nuclear stations have the capability at all times to perform detection, mitigation, classification, and notification functions required in the early phases of an emergency.

2.2 Authority

Over the Emergency Response Organization The Emergency Director in Command and Control is the designated Exelon individual who has overall authority and responsibility, management ability, and technical knowledge for coordinating all emergency response activities at the nuclear power station. The Emergency Director will immediately and unilaterally . initiate any emergency actions, including providing protective action recommendations to authorities responsible for implementing offsite emergency measures.

The Shift Manager is available at all times to . assume the responsibilities of Emergency Director.

A qualified individual is on-call to respond to the EOF and assume Command and Control. In accordance with the Ginna Emergency Plan, the TSC Emergency Director does not take Command and Control responsibilities.

2.3 Criteria

for Assuming Command and Control (Succession)

The responsibility for initial assessment of and response to an emergency rests with the Shift Manager (Shift Emergency Director).

Emergency personnel assume responsibility for their positions upon receiving notification to activate when an event has been declared.

The Emergency Director responsibilities are initially assumed by the Shift Manager. If the event is classified at an Alert or Higher level, or the Shift Emergency Director deems it appropriate, the Shift ERO will be augmented by the on-call ERO. The Corporate Emergency Director will report to the EOF and assume the Emergency Director's responsibilities.

June 2016 GN 2-1 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear The Shift Emergency Director is relieved of Command and Control as soon as possible after the declaration of an Alert or higher classification.

Command and Control does not transfer until the following criteria have been met:

• Adequate EOF staff levels are present in support of the non-delegable responsibilities.

• The staff has been fully briefed as to the status of the event and the currently proposed plan of action.

• A formal turnover between the Emergency Director relinquishing Command and Control and the Emergency Director assuming Command and Control has been made. 2.4 Non-Delegable Responsibilities Functional responsibilities of the Emergency Director that may not be delegated include: *

• Classify and declare emergencies.

• Direct and approve offsite emergency notifications to state and local authorities.

• Make Protective Action Recommendations to offsite authorities.

• Ensure appropriate evacuation actions for plant personnel.

• Approve emergency exposures and/or the issuance of Kl. 2.5 Emergency Response Organization Positional Responsibilities Table 2.1 outlines ERO positions required to meet minimum staffing (within 60 minutes) and full augmentation of the on-shift complement at an Alert or higher classification, and the major tasks assigned to each position.

The full augmentation levels are used as a planning basis to cover a wide range of possible events. For extended events (one which lasts for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), actual staffing will be established by the Corporate Emergency Director based on the event and personnel availability.

However, additional staffing or reduced staffing will only occur after discussion concerning the impact on plant operations and emergency response.

• The station's ERO consist of three major sub groups reporting to the Corporate Emergency Director:

• Onsite ERO, consisting of Control Room, TSC, OSC and Security personnel.

The primary functions of the Onsite ERO is perform mitigative actions and ensure appropriate onsite protective actions are taken.

• Offsite ERO, consisting of EOF staff. The primary functions of the Offsite ERO is to interface with offsite authorities and perform offsite radiological assessment.

• Public Information ERO, consisting of JIC staff. The primary function of the Public information ERO is to provide accurate information to the public through News Media. June 2016 GN 2-2 EP-AA-1012 (Revision

3)

.. .::/ Ginna Annex Exelon Nuclear 2.6 Emergency Response Organization Block Diagram Figures 2.1 through 2.7 show the reporting chains and interfaces of the ERO. 2.7 Corporate Emergency Response Organization In the event of a declared emergency at one of Exelon's Nuclear Stations, a Corporate Duty Officer is notified.

The. Duty Officer will notify senior company management personnel of the event. The Corporate Emergency Director will keep senior management informed of events and any need for assistance.

Specific departments of the company may be called on to assist as necessary to provide support for logistics, public information, finance, technical issues, etc .. Senior management may assist with interfacing government authorities and other outside organizations.

2.8 Augmentation.

of the Emergency Organization and Interface with Other Plans: The Ginna emergency organization is augmented by a number of offsite services.

Figure 2.6 shows the relationship of non-Company offsite organizations in emergency response.

Letters of agreement are referenced in Appendix 2. These agreements are considered valid until changed by the author during the annual review of the Emergency Plan. The authors of the letters of agreement are contacted in person or by telephone and the content of the letters is verified.

• Plant procedures contain the phone numbers and alternate means of contact needed to initiate emergency response actions. The communicator will initiate a call to New York State, Monroe County and Wayne County EOC, using the NYS Radiological Emergency Communication System (RECS). During working hours, the EOC staff will respond. During off hours, the County 911 Centers and the State Watch Center will respond for each Emergency Director to RECS calls. The ERO is alerted by a call from an automated notification system or from the Ginna Control Room. Other offsite assistance, such as Department of Energy -Radiological Assistance Plan (DOE-RAP) team or Westinghouse, is alerted by a call from the Emergency Director or designee to their duty officer at the phone numbers listed in procedures.

2.8.1 State

of New York, Wayne and Monroe Counties Emergency Actions: The Company is responsible for promptly notifying State and county authorities when conditions affect, or may affect, safe plant operations.

It is the responsibility of these offsite agencies to provide prompt notification to their parent and support organizations if it is determined that conditions or circumstances, either onsite or offsite, have affected or may affect normal and safe plant operations or conditions in the environs.

• Wayne and Monroe County's decision processes are based on EPA Pr9tective Action Guidelines (PAG), current road and weather conditions, time requirements for implementing PAGs and accident diagnosis and prognosis received from the licensee, New York State, USNRC and DOE. June 2016 GN2*3 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear The NRC has established, and the State of New York has accepted, four Emergency Classification Levels for which the Company shall provide early and prompt notification to both State and County authorities.

These Classification Levels are consistent with those described in Sections 3.2 through 3.5 in this plan. The "Unusual Event" and "Alert" classifications provide early and prompt notification of minor events which could lead to more serious consequences or which might be indicative of more serious conditions which are not yet fully realized.

A gradation is provided to assure more complete offsite response . preparations for more serious indicators.

At the Alert or higher classification, full mobilization of offsite emergency personnel is required.

The "Site Area Emergency" classification reflects conditions indicating significant releases are likely or are occurring but where a core-melt situation is not indicated.

The "General Emergency" classification involves actual or imminent substantial core degradation or melting with the potential for loss of containment.

The "General Emergency" classification requires immediate consideration of Protective Action Recommendations by the Company and communication of these recommendations to Wayne and Monroe Counties and New York State. Although Protective Action considerations

• are mutually discussed by *each county, the Chairman of the N.Y.S. Disaster Preparedness Commission and both County Executives may decide to take actions of different magnitude.

Protective Actions are based. on current and forecasted weather conditions, road construction and other possible impediments to evacuation.

• 2.8.2 Local Disaster Coordinator (Wayne County Emergency Management Office and Monroe County Office of Emergency Management):

In general, the responsibilities of the Local Emergency Preparedness Coordinator in each county include the following:

a) On receipt of notification from the State of New York, or Ginna Station Control Room, alert local authorities and officials in accordance with established plans. b)

• Coordinate response of local authorities and provide for available local assistance to the Company and State authorities in . accordance with established plans. The participation of the counties, upon notification of an event involving the general public, is outlined in their Radiological Emergency Plans, which are reviewed in Appendix 5. The Office of Emergency Management in each county consists of smqll administrative staffs and a pool of reserve personnel located throughout the county. Members receive training in monitoring, establishing relocation centers and providing medical attention, food, and lodging for evacuees.

Extensive communication resources are available for use by the Local Disaster / Coordinators and staff, including a number of radios for contacting the county fire coordinator, the police forces, public works and commercial radio stations.-

A June 2016 GN 2-4 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear roster of telephone numbers and contacts is maintained to communicate with agencies on State and local levels. Monitoring teams are available and radiological kits are maintained in shelters and firehouses located throughout the counties.

2.8.3 United

States Coast Guard (USCG): The USCG provides emergency support upon request by Wayne and Monroe Counties, -in accordance with the Wayne County Radiological Emergency Preparedness Plan and Monroe County Radiological Emergency Preparedness Plan. 2.8.4 United States Nuclear Regulatory c*ommission, Region 1, Incident Response (

Reference:

NUREG-0728, NRC Incident Response Plan): This NRC Plan describes the notification, communication decision-making and mobilization of the NRC Incident Response Organization in the event of an event/incident related to Ginna Station. The extent of mobilization will depend upon the emergency classification and associated plant conditions.

The Company will supply whatever support services and resources are needed -to maintain Federal assistance.

2.8.5 United

States Department of Energy Radiological Assistance Program, Region I, Brookhaven Area Office, Upton, New York (DOE RAP/I RAP): Since Ginna Station is located in DOE Region I, the Brookhaven Office of the U.S. Department of Energy (DOE) has the responsibility to provide radiological assistance in the event of an emergency.

Their principal goal is to be prepared in the event of a major accidental release, or other loss of control of radioactive material.

Radiological assistance can be requested at any time by calling and indicating the nature of the incident, the location, and how to contact utility and local authorities in order to coordinate the Department of Energy response.

The assistance includes advice and emergency actions essential for the_ control of the immediate hazards to health and safety. This preparedness includes plans -and procedures for: effective and economic use of resources; minimization of radiation exposure of individuals and the public; prevention of the spread of radioactive materials into the environment; and appropriate countermeasures to control and remove radiological hazards. Large numbers of qualified radiation, nuclear and medical specialists are the principal resource that can be made available in an emergency, along with quantities of radiation monitoring equipment and specialized detector and test equipment.

Most assistance requests can be handled by giving advice, by sending radiological safety experts to the incident scene, or by transferring the request to another Federal agency or a State agency. The Department of Energy, Brookhaven Office, has agreed to provide such assistance upon notification of a hazard to the general public. Available resources are noted in the county plans. Assistance could be onsite within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a request. The Company will supply whatever support services and resources are needed to maintain Federal June 2016 GN 2-5 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear assistance.

RAP/I RAP teams initially report to the EOF for. briefing and coordination.

It should be understood that this Federal advice, assistance and equipment is provided to the local government institutions to assist in carrying out their responsibilities and authority for protecting the health and safety of the local population and in no way supersedes that local responsibility.

Furthermore, this assistance may be terminated as soon as the immediate hazards are brought under control and there is reasonable assurance that' public health and safety are being protected.

2.9 Industry/Private Support Organizations Exelon retains contractors to . provide supporting services to the company's nuclear generating stations.

For station specific support, copies of current contracts and letters of agreement with these groups are maintained by the Emergency Preparedness Department.

Current contracts and letters of agreement are maintained in each Emergency Preparedness Department's files. 2.1 O Supplemental Emergency Assistance to the ERO Agreements are maintained (for each nuclear station) with outside support agencies who do not take part in the organizational control of the emergency that provide assistance when called on during an emergency or during the recovery phase. These agreements identify the emergency measures to be provided, the mutually criteria for implementation, and the arrangements for exchange of information.

These support agencies provide services of: a. Law enforcement;

b. Fire protection;

c. Ambulance services;

d. Medical and hospital support Support groups providing transportation and treatment of injured station personnel are described in Section 5.5 of this plan. Current contracts and letters of agreement with these groups are referenced in Appendix 2 of this plan. 2.10.1 County Sheriff: The Wayne County Sheriff's Department will assume responsibility for necessary police services in Wayne County. They respond to dfrections and requests from the Director of the Wayne County Emergency Management Office, who identifies problems and designates responsibilities.

Ginna Station does not make direct contact with the Sheriff's Department for a radiation emergency.

The same arrangement is true for the Monroe County Sheriff's Department which is directed by the Monroe County Director of the Office of Emergency Management.

The Wayne County Sheriff's Office, in conjunction with the National Incident

• Management System (NIMS), will respond to a radiological event, including a June 2016 GN 2-6 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Hostile Action-Based Event, upon notification by the station in accordance with established communications protocols.

2.10.2 Ontario Volunteer Emergency Squad (OVES): OVES is an organization located approximately 5 miles from Ginna Station. OVES is certified to Paramedic Care by the New York State Department of Health (NYS DOH) and operates under 10 NYC RR Part 800 State Emergency Medical Code and Public Health Law Article 30. In the event of an emergency situation at Ginna including a Hostile Action-Based Event, OVES will provide emergency medical services when requested through established communications protocols via 911 Dispatch.

To include the transport of person(s) who may have been exposed to radiation or who have injuries complicated by radioactive contamination, to either Rochester General Hospital or Newark-Wayne Community Hospital.

2.10.3 Ontario Fire Company (OFC): OFC is a town fire district.

The Fire Station is located approximately 5 miles from Ginna Station. OFC is operated under Section 209 of New York.State General . Municipal Law and is part of the New York State Mutual Aid Plan. Should an emergency situation, including a Hostile Action-Based event occur at Ginna, Ontario Fire Company agrees to provide assistance to the extent of their capabilities.

This assistance includes; fire response, fire apparatus and volunteer firefighters as requested by Ginna. It may be necessary for Ontario Fire to request mutual aid in order to receive additional support. 2.10.4 Radiation Emergency Medical Response:

The Ginna Station emergency medical response is detailed in procedure A-7. Control Room personnel are notified of any medical emergency.

The location and known information about the emergency is announced over the plant page and the medical response team responds.

Emergency medical services (EMS) may be contacted via the 911 dispatcher.

Advanced Life Support (ALS), Mercy Flight and mutual aid can also be requested via the Control Room to augment the local EMS. 2.10.5 Rochester General Hospital/Newark-Wayne Community Hospital:

Arrangements have been made with the designated hospitals to receive and assume control of patients from Ginna Station, if* requested.

• Implementing procedures include the means of communication between the utility and the hospital.

If an emergency situation, to include a Hostile-Action ba*sed event, should occur at Ginna, Rochester General Hospital and Newark-Wayne Community Hospital agree to ensure the capability for the evaluation of radiation exposure and intake, including assurance that personnel providing these services are adequately prepared to handle contaminated individuals and are capable of providing medical support for any injured individuals who may be contaminated.

Rochester General Hospital is equipped with a dedicated room for treatment of radiologically contaminated victims. Newark/Wayne has an area within the June 2016 GN 2-7

• EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear hospital which can be converted to a radiation treatment room. Adequate contamination control and procedures are maintained in each facility.

Hospital personnel are trained in the treatment of radiation accident patients and each hospital has an approved radiological emergency plan specific to their facilities and resources.

Annual training is provided to hospital staff. Radiation Protection instrumentation is supplied to the hospital by the Company. Annual training drills are conducted by the Company and the hospitals and include critiques.

Hospital staffs also attend training seminars on treatment of radiation accident victims. 2.10.6 Medical Emergency Consultant:

Radiation Emergency.

Assistance Center!f raining Site (REAC!fS) will respond as follows upon request from one of the medical responders or from the Company: a) Dispatch a radiation emergency medical team, which is available on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> basis. b) Make available the services of a radiation/decontamination treatment facility.

c) Make transportation arrangements (air or ground) for patients to the radiation/

decontamination treatment REAC!fS has laboratory and medical facilities at the Oak Ridge National Laboratories.

Ginna has an arrangement with the hospital for management and treatment of radiation accident victims and ensures that facilities necessary for treatment are readily available by equ*ipping the hospital with the medical and radiological equipment needed. Ginna has conducted an initial evaluation and made recommendations for an effective local medical emergency program, coordinating the planning for local medical support with REAC!fS: Periodic site visits are made to coordinate and review emergency medical support with . company officials and local medical personnel.

REAC!fS and other vendors can provide radiological emergency training for plant, hospital and ambulance personnel if not provided by Company personnel.

2.10.7 The Company Medical Department and Contract Physicians:

The Company medical department is contacted for all medical emergencies occurring at Ginna Station. The medical department provides contract physicians to interface between the hospital health care organization and the Company. REAC!fS may be contacted for assistance during or after a radiation medical emergency.

Contract physicians can facilitate the integration of REAC/TS, or other responders, with the hospital health care organization treating the victim. 2.10.8 Consultants and Contractors:

Implementing procedures give the name and phone contacts for additional consultants and contractors who may be requested to provide technical . assistance to the emergency organization.

In case of a radiation event, the Emergency Director has the authority to procure the services of any consultant group that may be needed. The Company, as part of the Institute of Nuclear Power Operations (INPO), can. call upon INPO June 2016 GN 2-8 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear resources to supplement Company efforts in executing emergency response plans. Support may be requested directly from licensees and service companies listed in the INPO Emergency Resources Manual or may be obtained by using INPO as an agent to arrange and coordinate the required support. The Company also has agreements with upstate New York State licensees for mutual assistance in times of emergency.

• 2.10.9 Laboratories:

There are two radiochemical laboratories at Ginna. One is adjacent to the controlled area and is used for primary coolant and other plant samples. The second laboratory is used for environmental samples and is located in the Ginna Training Center East, remote from the plant. This laboratory contains some of the equipment found in the main laboratory and could be used for diluted post-accident samples if needed. The laboratory at the Fort Smallwood Road Complex is operated by Exelon and is available for analysis of samples. The laboratory is located in Baltimore, Md. 2.11 Other Emergency Plans: Ginna's Emergency Plan and other implementing procedures are coordinated with the following external organizations' plans: 1 . Rochester General Hospital Radiological Medical Emergency Plan 2. Newark-Wayne Community Hospital Radiological Medical Emergency Plan 3. Monroe County Radiological Emergency Preparedness Plan 4. Wayne County Radiological Emergency Response Plan 5. New York State Radiological Emergency Preparedness Plan for Commercial Nuclear Power Plants. June 2016 GN 2-9 EP-AA-1012 (Revision

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Ginr *-

Table 2.1: .,. **Functional**

.*. *. *Area 1. Plant Ops and Assessment

2. Emergency Direction and Control Exelon Nuclear Minimum Staffing Requirements for the ERO MajOrTasks Control Room Staff Command and Control * ,., *;"J ' j;:' *** *::.'. .'+i:'c_*/i

',,* ' *J .*. *;* ,, '

• Positions Shift Manager (Shift) Control Room Supervisor (SRO) (Shift) Contro.1 Room Operator (RO) (Shift) Auxiliary Operator (AO) (Shift) Shift Manager (Shift) Corporate Emergency Director (EOF) Station Emergency Director (TSC) .......................................

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

• • • • • • -***-******

........... . Facility Control TSC Director (TSC) EOF Director (EOF) 1* 1* 2* 4* See above 1 1 1 1 "FG1F***.

(: Augmentation

3. Notification Emergency Shift Communicator (Shift) State/Local Communicator (EOF) ENS Communicator (TSC) 1* 1 1 & Comm. Communications June 2016 HPN Communicator (EOF)

• 1 -***-**----"'" ...................

--*--*********--*---"'"---*-**-*******-*****

.. -,,_ ......................

_, .. _____ ,, .. ,,, .. _, __ ,,, ..... _ .. _ ........................

_,,, ..............................

,,, ____ ,,,, .... _, _____ .....................

• ----*-****-**-

• • • • • -----*---

.. *-*-.. -*---*--*!--*

• • • -*-.. **----*--******-***----

.. ***---* Plant Status & Technical CR Operations Communicator 1 Activities TSC Operations Communicator 1 OSC Operations Communicator 1 EOF Operations Communicator 1 **-*---*-**

.. -*--****-***********""""""""""*---****-***-..................................... . ............

• • -*-*** ...................

-.. -*----*******-**

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

-.... -*--******-********

• • • • • • • • • -

.. -******* .......................

___ ........................................................................

• • • • • • -**-

• -.................

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

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

_ ..................................

_ In-Plant Team Control Team Tracker (OSC) 1 Governmental EOC Communicator (EOF) State Liaison (EOF) County Liaison (EOF) Incident Command Post Liaison GN 2-10 1 1 2 Note 2 EP-AA-1012 (Revision

3)

Exelon Nuclear

• Ful1ctiona1

• ** ,ii 11 1r:, 1 1 '** * * * * * * /.*. ,.,. * **1.*> ::A. '1* * * . Minirnu'*m

• *** . *.** **** Fuf1* * :* '*** * :*

• Area

• . .Emergency

• .. Staff** Augmentation

4. Radiological Offsite Dose Assessment . Dose Assessor (EOF) 2 Assessment Offsite Surveys Environmental Coordinator (EOF) 1 5. Plant System Engineering , Repair, arid Corrective Actions June 2016 Offsite Monitoring Team (EOF) f.,,,,,,,,,,,,,,,,,.,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, ** _,,,,,,,,,,,,,,,,,,,,,,,,,,_,,,,,,,,,,,,,,,_,,,,,,,,,,,,,,,,,,,,,,ll*-,,,,,,,,,,,,,,,,,,, ___ ,.,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,.,,,,,,,,,,,,,,,,_, __ 4 Onsite Surveys Shift RP Technician (Shift) 1* RP Technician (OSC) 2 In-plant Surveys RP Technician (OSC) 1 Chemistry Shift Chemistry Technician (Shift) 1* ......................

-........................ , ___ ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,.

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

,, .. ,_ .. _, _______ .............

• • • • • • • • • • • --***

............................................................. , ... _,,, .... , .... _ .. ,, ........ ,_ ...................................................

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

_ .........................

_._ .......................

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

________ _ Chemistry Technician (OSC) 1 OSC Chemistry Lead 1 ____ ,,,,,,.,,,, __ ,,,,,,,,,,, __ , __ ,,,,,,_,_,_,, ___ ,, __ .. , ____ .. ___________________________________________________

.. __ .... , ................

___________

,., ___ , ...... ,_, _____ .................

,,, ____ ,, __ . __ -****--*-**--*--,,*-*----*-*

RP Supervisory Technical Support I Accident Analysis Radiation Protection Manager (TSC) Radiation Protection Manager (EOF) Shift Technical Advisor (Shift) Technical Manager {TSC) Electrical Engineer (TSC) Mechanical Engineer {TSC) Core I Thermal Hydraulic Engineer {TSC) Operations Manager {TSC)

• EOF Technical Advisor (EOF) 1 1 1* 1 1 1 1 1 1 __ ,, __ ,, ___ ,,,.,,,,,,,,,,,,, __ ,,,,.,,,,,,., ___ ,,,,,,_,,,,_,,,,,_,,,_,,.11*-

.. *-.. * ..........

-.. -._--*-***********"-

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

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

---

*-........ *-***-*-*-****-

.. --.. --........ -... _ ...................

____ ...... ---* --............

-*----*-*---

..........

--*--Repair and Corrective Actions Maintenance Manager (TSC) OSC Director (OSC) Assistant OSC Director (OSC) Electrical Technicians (OSC) Mechanical Technicians (OSC) l&C Technicians (OSC) Operations Personnel Craft Leads (Elec, Mech, l&C) GN 2-11 1 1 1 1 1 1 (Note 2) (Note 2) (Note 2) (Note 2) 3 (Note 3) EP-AA-1012 (Revision

3)

• Functional Area 6. In-Plant Protective Actions 7. Fire Fighting 8. First Aid I Rescue 9. Site Access Control 10. Resource Allocation and Admin Support 11. Public Information Exelon Nuclear

• Major Tasks* Radiation Protection . Emergency Po$itions .

• RP Technician (OSC) RP Lead Fire Brigade (Shift) Fire Brigade Lead (Shift) First Aid provided by trained Shift Personnel Rescue support provided by shift personnel or

• osc personnel.

Security & Accountability Security Shift Supervisor (Shift) Security Personnel Logistics Security Coordinator (TSC) EOF Logistics Manager (EOF) JIC Logistics Manager (JIC) .....................................

--***-** .. *******-*-

.. *-****.. . ........ ,_,, ...................

,_, ___ ......................................

_,_ .. ,_ .. _, __ , .. ,,.,,_,,_

....... -.... *-**-*-*******--**-**-****--

Administration Administrative Staff (TSC)

Staff (OSC) Administrative Staff (EOF) Administrative Staff (JIC) . Minimum * *Staff** 1 1 (Note 4) 1* Fire Brigade members (3) (collateral duty) (Note 5) (Note 5) 1 Full Augmentation

• 1 1 2 2 2 (Note 6) 2 (Note 6) t--**---***---------********--**--***---****-***-----1>

... -.... -*---***-*--*-

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

_____ ,_ .. , __ ,_ .. ,_ .. __ ,, ___ , __ ,,_,_,_ .............

---*-** .. -* .. *---.......................

,_, ___ ,,,._,_,,, ___________

• • • • • -**---**-*

................. , ____________

,,,, .. ,, __ _ Facility Operations Media Interface Computer Specialist (TSC I OSC) Computer Specialist (EOF I JIC) Company Spokesperson (JIC) Media Liaison (JIC) ..................................................................................

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

.......................... . Information Development News Writer (JIC) 1 Technical Advisor (JIC) 1 1 1 1 1 ***-**""""",."""'""_",.*-*--*-*****-**--**--HHHH*--HHHH-**-*-HHHHHHH*-*-*-**

oooooooo-HHHHHHO*HHHH*-****-**-*--*-****H-*---""'-

""""""""""""'""""""*H*****"*H**OH******oo**OOOOO***-***O*******--*"OOOOOOOOOOOOooOoo--**-""'"-'

oOoHHO*--.,,_,, ___ ,_ .. ,_ .... ,._,_,, .. , ... , ** , ** _ .. , .. ,_ .. ,_ ... ,,. ... , .. ,.,.,.,, __ *-oooooooo-*-***Hooooooo

.... o .... ooOoo .. oo---**H***-****-*

Media Monitoring and MM/RC Coordinator (JIC) 1 Rumor Control Inquiry Phone Team (JIC) Media Monitoring Team (JIC) 2 (Note 2) 2 (Note 2) -------+*-

.... ---*-***-*****-*--**--

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

-..........

,_ .. ___ , ............

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

-*--*-* ... -............................

--.. ***--***-******---*-*-

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

• • • • • • • • • • • • -*******--******---****

.... ********-*--*-

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• -***-* .........

--*-**--***-

• • • • • • • • • • • • • • • • • • • • • --

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

-............... , .. ,_._ ..............

_ ...........................

--*****--*-**

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

.. *Facility Operation and JIC Manager (JIC) 1 Control

• JIG Security (JIC) 1 June 2016 GN 2-12 EP-AA-1012 (Revision

3)

Gim .... ,.,nnex Functional Area Major Tasks Emergency Positions TOTALS: Notes:

• Minimum Shift Staffing ** Minimum Staff will respond within 60 minutes. (1) Provided by On-Shift personnel , denoted by an asterisk. (2) Personnel numbers depend on the type and extent of the emergency.

(3) Craft Lead positions can be filled by senior technicians or craft supervisors. (4) Fire Brigade per FSARffechnical Specifications , as applicable.

May be a collateral duty. (5) Per Station Security Plan. (6) EOF and JIC may share Administrative Staffs June 2016 GN2-13 Exelon Nuclear Minimum Full Staff** Augmentation Shift staff: 13 37 Other: 34 EP-AA-1012 (Revision

3)

Gim.u '"'nnex June 2016 Figure 2.1 Shift ERO Shift Manager --------r----------1 Title Block Guide Upper Right Number of members to Control Room Supervisor Satisfy positions requirements Lower Right S = Shift Position ---------Indicates direct report that Resides in another facility GN 2-14 Shift RP Technician Shift Chem Technician Shift Technical 1 Advisor Head Control Operator Control Operator Auxiliary Operators Communicator (1) Fire Brigade Captain (1) Fire Brigade Members (4) Exelon Nuclear EP-AA-1012 (Revision

3)

Ginr *-.-.nnex I EOF Director Offsite ERO Interface with Offsite Response Organizations (Federal, State and Local) to coordinate Protective Actions for the public Figure 2.2 ERO Management Structure Corporate Emergency Director I Station Emergency Director Onsite ERO Onsite (OCA) Protective Response and Mitigative Actions Note: The Emergency Director, with overall Command & Control , is normally located in the EOF. June 2016 GN 2-15 Exelon Nuclear I JIC Manager Public Information ERO Provides information to the Public through the News Media , addresses phone inquiries, conducts Rumor Control operations.

EP-AA-1012 (Revision

3) c 1 Annex Exelon Nuclea. Figure 2.3 TSC Staffing Stat i on E m ergency D i rector OSCC h e m TSC lead* I D i rector j T S C . Admin Staff I I I I I -*"-T ec h n i ca l I I l Rad Protect i on I Secu ri ty Manage r Operat i ons Manager I Ma in tenance Ma n age r Manager I Coordinator ,j I I I E l ect ri ca l E n g in eer ii (Co n t r o l Room) I {OSC) I (OSC) (A C F) --j .. .. Secur i ty Sh i ft Sh i ft Manage r OSC D i rector RP lead Supervisor --Mec h anical -NS Comm u n i cator; Secur i ty For Eng i neer -ce Co r e Th e r mal I -Hyd r au lic T SC Ope r at i o n I -Commu ni cator j Eng i neer I I -TSC/OSC C o m p u te r I_ {Control Room) Spe ci a li st Ops Communicator

• OSC Chemistry Group Lead only part of TSC Staffing at UE Dotted lines indicate positions located in other facilities.

June 2016 GN 2-16 EP-AA-1012 (Revision

3) c 1 Annex I I E l ectrical l&C Group Lead Group Lead I Electrical l&C -Techs Techs I Figure 2.4 OSC Staffing osc Director OSC Admin Staff **--*-----**---Assistant OSC OSCTeam Director Tracker I I I Mechanical 1 RP I ; Exelon Nu i... __ _. I OSC Operat i ons Communicator

-I I OSC Chem Group Lead j I Group Lead I Group L ead J Ops tJ Group Lea 'i Mechanica l I RP Chem Operators C::: -Techs -Techs -Techs -Ii *Minimu m numbe r of op erators e qu a l to Sh if t S t affing June 201 6 G N2-17 E P-AA-1012 (Rev i s i o n 3)

G Annex Exelon Nuc. __ _ Figure 2.5 EOF Staffing Corporate Eme r gency D i rector . .r I I EOF ! i D ir ector ! i q State/Loca l -Communicator " I I I EOF Log i st i cs I EOF EOF Techn i ca l Advisor EOC Communicator Rad Protect i on Manager j ,, Manager EOF Operat i ons ! -Communicator HPN -EOF /J I C Comp u ter J State Communicator I Specialist

-Lia i son I I I Dose Assessor Env i ronmental

-EOF Adm i n Staff -County Liaison(s)

Coordinator Off s i te -Mon.Team I Members June 2016 GN 2-18 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Figure 2.6 JIC Staffing JIC Manager i Company Spokesperson

.. I I MM/RC JIC Logistics Coordinator Manager I nquiry News -Phone Team -Writer I Media Monitoring JI C Technical

-Advisor Team JIC j -Admin Staff I Media -Liaison JIC -Security J June 2016 GN 2-19 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Figure 2.7 Inter-Relationships of Ginna Station Emergency Response Organizations Ginna Station CR or TSC I I Medical Security Fire Radiation Emergency Event Emergency OVES EOF I--Wayne County Ontario Fire Sheriff Company NRCIRT Company Med I--DOE RAP Department FRMAP NWCH New York I--State RGH Wayne -County Medical Emerg. Monroe -Consultant County USCG June 2016 GN 2-20 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Section 3: Classification of Emergencies Emergencies are classified into four categories, which cover the entire spectrum from probable incidents to postulated major accidents.

This system is coordinated with the NRC, New York State, Wayne County and Monroe County to ensure that the classification system is compatible with that used by all organizations.

The system provides for notification of appropriate emergency response organizations and implementation of actions immediately applicable to a specific condition.

Provisions are included for revising the classification level and the corresponding responses in the event of a change in severity of the emergency condition.

This section identifies the events which comprise each of the four emergency classifications requiring formal offsite notification.

This section also describes a condition known as a Local Radiation Emergency which does not require formal notification.

Criteria for characterizing, recognizing and declaring each emergency classification are given along with appropriate emergency classifications.

Recognition and classification criteria a're based, to the extent feasible, on readily available information such as Control Room instrumentation.

Plant parameter values and the corresponding emergency classifications are given in appropriate implementing procedures.

Immediate actions to be taken in response to plant conditions are detailed in plant operating and emergency procedures.

Other emergency actions in

• response to radiation emergencies are identified in Section 4, Emergency Measures and described in detail in applicable Emergency Plan Implementing Procedures as listed in Appendix 3. A comprehensive listing of Ginna-specific initiating conditions for each emergency classification*

is provided in EP-AA-1012, Addendum 3, Radiological Emergency Plan Emergency Action Levels (EALs) for Ginna Station. EP-AA-1012, Addendum 3 is based on NEI guidance provided in NEI 99-01 and demonstrates how an initiating condition leads directly to the appropriate emergency classification, based on the magnitude of the event. In some cases, extensive assessment is necessary to determine the applicable emergency classification.

In any case, continuing reassessment is required to ensure that the classification is upgraded or downgraded commensurate with the severity of the condition.

Emergency Plan Implementing Procedures can be found in the Control Room, Technical Support Center, Emergency Operations Facility, Document Control, and on the internal Ginna website. 3.1 NOTE: Local Radiation Emergency:

The Local Radiation Emergency is not one of the four NRC Emergency Classifications and does not require any offsite notification.

Incidents may occur which require response only within the plant. A Local Radiation Emergency is defined as a radiation emergency condition whose consequences affect only personnel onsite. EPIP-1-13, Local Radiation Emergency, provides for the identification of local radiation emergencies and the

• actions necessary to ensure worker safety. June 2016. GN 3-1 EP-AA-1012 (Revision

3)

Ginna Annex NOTE: The following are the four NRC Emergency Classifications.

3.2 Unusual

Event: Exelon Nuclear Events within this Emergency Classification generally characterize off-normal plant conditions which, by themselves, do not constitute significant emergency conditions.

Some of these events could, however, indicate a potential degradation in the level of plant safety and/or could escalate to a more severe condition if appropriate action is not taken. The primary purpose for this classification is to ensure that the plant operating*

staff recognizes initiating conditions, takes appropriate action, and comes to a state of readiness to respond in the event that the condition becomes more significant.

The Unusual Event classification or higher also requires that offsite authorities be promptly informed of the abnormal condition by use of the Radiological Emergency Communications System (RECS) and the New York State Radiological Emergency Data Form, Part I, found in procedure EP-CE-114-100 . No response by offsite authorities is necessary for non-hostile action events within this classification.

The TSC or EOF will not usually be activated, although the Station Emergency Dfrector, *Operations Manager, OSC Chemistry Lead and Technical Manager will normally report to the TSC to provide assistance.

When giving notice to State and county officials, the Company will make sure that they clearly understand the Unusual Event classification and that, if conditions change, there will be further notification.

3.3 Alert

This Emergency Classification is characterized

• by events which indicate an actual or potential substantial degradation of the level of plant safety or a security threat that involves probable life-threatening risk to site personnel or damage to site equipment because of hostile action. This classification requires response by the plant ERO and augmentation of onsite emergency resources.

It constitutes the lowest level where emergency offsite response for non-hostile action events may be anticipated.

All Ginna emergency facilities will be staffed at an Alert or higher. Prompt notification of an event within this classification will be made to the NRC, State of New York and Monroe and Wayne Counties.

While the initial assessment would not require immediate response, potential releases of radioactivity make it advisable to. alert offsite organizations.

Periodic status updates will be made to keep authorities aware of the situation.

3.4 Site Area Emergency:

A Site Area Emergency is characterized by events involving actual or probable major failures of plant functions needed for protection of the public or hostile . action that results in intentional damage or malicious acts: (1) toward site personnel or equipment that could lead to the likely failure of equipment needed for the protection of the public; or (2) that prevent effectives access to equipment needed for the protection of the public. Most events within this classification June 2016 GN 3-2 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear constitute actual or clear potential for significant releases of radioactive material to the environment.

For a Site Area Emergency, all emergency response facilities are activated.

Although emergency actions involving members of the public may not be necessary, offsite emergency response organizations should be mobilized and ready to impfement protective measures.

Protective actions taken onsite are: the evacuation, if deemed necessary, of all persons in areas other than the Control Room, Technical Support Center and OSG; initiation of onsite and offsite radiation monitoring; and close monitoring of plant status s*o that the licensee and other authorities can be advised of changing conditions, whether increasing or decreasing in severity.

Meteorological and release data and survey results will be used to provide offsite dose estimates.

For the purpose of classifying an emergency, instrument indications in the Control Room will be used. The instruments of interest and appropriate action points are part of the implementing procedures.

3.5 General

Emergency:

A General Emergency is characterized by events which involve actual. or imminent substantial core degradation or melting with potential for loss of containment integrity or hostile actions that result in an actual loss of physical control of the facility.

Initial declaration that a General Emergency may exist is based on a situation which may have the potential for serious radiological consequences to . the health and safety of the general public.* A Site Area Emergency most likely would been declared earlier and, if events are in progress which may involve core degradation with potential for loss of containment integrity, a General Emergency should be declared.

For a General Emergency, all emergency response facilities are activated.

The Emergency Director will promptly notify State and local authorities and ttie NRC of the plant status and reasons for declaring a General Emergency.

The Emergency Director will also make recommendations for offsite emergency measures to be ,taken. The responsibility for this recommendation to offsite authorities may*not be delegated.

June 2016 GN 3-3 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Section 4: Emergency Measures The following sections provide the guidelines for implementing procedures of the four emergency classifications and the Local Radiation Emergency condition which are described in Section 3.0. 4.1 Local Radiation Emergency:

A Local Radiation Emergency condition is established to provide a level of response to a radiological incident which is less serious than the four NRC Emergency Classifications.

Jt has no effect offsite and has no potential for any offsite effects. There is normally no notification or action required by offsite agencies.

a) EPIP-1-13, Local Radiation Emergency, contains the details of the response.

In general, any individual aware of an incident shall notify the Control Room of this fact. b) The Control Room shall announce over the plant public address* (PA) system that a local evacuation of the area is required.

c) All personnel in the affected area shall leave the area as directed.

4.1 .1 Subsequent Action: The situation will be evaluated and actions taken to terminate the emergency.

The plant shall determine the course of action to be taken to clean up the affected area,* correct the cause of the incide.nt, and return the area to normal operation.

State and county authorities may be notified of the incident for informational purposes but no actions are required offsite. NOTE: Sections 4.2, 4.3, 4.4 and 4.5 are NRC Emergency Classifications that require State, county, and NRC notification.

4.2 Unusual

Event: The purpose of the Unusual Event Classification is to provide early warning of minor events which could lead to more serious consequences.

The Unusual Event conditions indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. Declaring an Unusual Event assures that the first step for any response later found to be necessary has been carried out by bringing onsite staff and offsite organizations.

to a state of readiness, thereby providing a system for handling information and decision-making.

The NRC, State and county authorities will be promptly notified to assure that the. first step of any necessary response can be initiated.

The Plant Manager will be notified of the Unusual Event Emergency to bring the plant staff to a state* of readiness and provide for responsible decision-making.

On-shift resources can be augmented so as to be -able to assess and respond as needed. Offsite organizations will stand by for further information or closeout.

June 2016 GN 4-1 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear 4.3 Alert: Events of the Alert classification involve actual or potential degradation of the level of safety of the plant or a security threat that involves probable life-threatening risk to site personnel or damage to site equipment because of hostile action. Any radioactivity released during an Alert would result in exposures well below the . guidelines for required offsite action. By assuring that emergency personnel are available to respond if the situation should become worse, protective actions could be taken much quicker, such as performing confirmatory radiation monitoring and providing offsite authorities with current status information.

For events which fall in the Alert classification, Ginna Station will promptly notify the NRC, State and county authorities of the. Alert status and the reasons for the classification.

All Ginna emergency facilities will be staffed so as to assist in the assessment of the incident and determination of a proper response.

Periodic plant status updates will be given to offsite authorities who will also be advised of any change in the classification of the incident.

Unless they are already in the plant, persons so notified will report to the plant, the Emergency Ope'rations Facility (EOF) or, if directed by Security, to the Training Center, :where jobs *are assigned in line with the trained capabilities*

of the individual.

Procedures provide for staffing of. all Ginna emergency facilities.

The organization is *normally activated via an automated system activated from the . Control Room. The Joint Information Center will be staffed by Company, county and State personnel in order to coordinate public information activities warranted by the emergency.

Offsite agencies wili activate primary response centers to standby status and will alert other key emergency personnel, such as monitoring teams and communications centers, the Emergency Alert System, or law enforcement.

They will be ready to escalate to a more severe classification, if appropriate.

June 2016 GN 4-2 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Figure 4.1 Ginna Notification Process CONTROL ROOM I (VIA RECS) (VIA ENS) (VIA PHONE) *-NUCLEAR ERO MONROE WAYNE NEW YORK REGULATORY NOTIFICATION COUNTY COUNTY STATE COMMISSION SYSTEM I I I MONROE WAYNE COUNTY NEW YORK STATE NRC GINNA STATION MONROE COUNTY WAYNE COUNTY EMERGENCY EMERGENCY EMERGENCY COUNTY 911 911 EMERGENCY EMERGENCY RESPONSE RESPONSE RESPONSE RESPONSE RESPONSE ORGANIZATION ORGANIZATION ORGANIZATION ORGANIZATION ORGANIZATION June 2016 GN 4-3 EP-AA-1012 (Revision

3)

Ginna Annex Figure 4.1 (Cont'd) Ginna Notification Process (EOFITSC) (Supersedes Standard Plan EP-AA-1000, Figure F-1) EOF (VIA RECS) State/local Comm. MONROE WAYNE COUNTY COUNTY I I I MONROE WAYNE COUNTY MONROE COUNTY COUNTY911 WAYNE COUNTY 911 EMERGENCY EMERGENCY RESPONSE RESPONSE ORGANIZATION ORGANIZATION June 2016 GN 4-4 Exelon Nuclear TSC I I (VIAHPN) (VIA ENS) HPN Comm. ENS Comm. I I I NEW YORK NUCLEAR STATE REGULATORY COMMISSION I NEW YORK STATE NRG EMERGENCY EMERGENCY RESPONSE RESPONSE ORGANIZATION ORGANIZATION EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear 4.4 Site Area Emergency:

A Site Area Emergency is declared when events are in progress or have occurred which involve actual or likely major failures of plant functions needed for the protection of the public or hostile action that results in intentional damage or malicious acts: (1) toward site personnel or equipment that could lead to the likely failure of equipment needed for the protection of the public; or (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.

In the event that a Site Area Emergency is declared, the actions to be taken by various plant groups are detailed in the implementing procedures for the plant. The Control Room will make the initial notification to the NRC,-State and county authorities.

The purpose of the declaration of a Site Area Emergency is to assure that personnel required for evacuation of near-site areas are at their duty stations if such an evacuation is called for. Also, offsite agency authorities will be available at primary response centers for consultation and updates on the situation, and to provide information to the public. 4.5 General Emergency:

The General Emergency will be declared when the conditions described in Section 3.5 exist. Actions associated with the General Emergency declaration p.re to: (1) initiate protective actions for the public as predetermined or as indicated by actual releases; (2) provide continuous assessment of information from Ginna Station and offsite measurements; (3) provide consultation with offsite authorities; and (4) keep the public informed through updates of the -situation through the Joint Information Center. 4.5.1 Company Actions: A General Emergency requires that all actions prescribed for the Site Area Emergency (see Section 4.4) be implemented.

_The NRC, State of New York, and county authorities, who will already have been contacted for lower classifications, will now be updated. The Emergency Director or designee may request the assistance of offsite groups, which could include REACffS, Company medical department, and Department of Energy, Brookhaven Radiological Assistance Program. Technical personnel from other Company departments and/or consultants will be called as needed. The EOF Radiation Protection Manager has the responsibility to determine the magnitude and extent of the incident by evaluating information from the Control Room and the Offsite Monitoring Teams. This information will consist of instrumentation readings and any survey results available.

EOF staff shall update the State and local .authorities with new survey data and other information and recommend protective actions. Protective action recommendations will be based on NUREG-0654 I FEMA-REP-1, Rev. 1, Supplement 3, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and June 2016 GN 4-5 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Preparedness in Support of Nuclear Power Plants". A summary dose based recommended actions is presented in Table 4.1. The methodology for implementation of the Protective Action Recommendation (PAR) process is contained in EP-CE-111, Emergency Classification and Protective Action Recommendations, which also provides guidance for upgrading an initial PAR based on pertinent factors. In making the recommendation for sheltering or evacuation, the EOF Radiation Protection Manager should evaluate the weather forecast in relation to changing winds and precipitation.

The offsite authorities should evaluate the calculated evacuation times in relation to predicted start, length . and termination of a release*.

Emergency staff at Wayne and Monroe Counties and New York State shall determine, by evaluating the information given by the Corporate Emergency Director, if area evacuation or sheltering is necessary, to what extent, and how to undertake protective action including evacuation.

A projection of population distribution in the 10 mile plume exposure zone is included in the Evacuation Time Estimates contained in EP-AA-1012, Addendum 2. A summary of evacuation time estimates for various conditions is provided in EP-AA-1012, Addendum 2. All surveys will be retained by the EOF Radiation Protection Manager and sample analysis results will be retained by the Chemistry Group Lead for appropriate documentation.

Formal reports shall be written and distributed as required by 1 OCFR20 and the Ginna Technical Specifications.

Information concerning the offsite consequences of. the incident and protective actions to protect the public will be coordinated in accordance with the New York State

• Radiological Emergency Plan and County Emergency Plans. A Company spokesperson in the JIG will release the information concerning the plant, plant safeguards and its employees, and assistance being provided to State and local authorities.

Severe Accident Management Guidelines (SAMG) entry conditions are defined in the Station Emergency Operating Procedures.

4.5.2 Offsite

Authorities Actions: All actions of paragraph 4.9.6 for Site Area Emergency will be reviewed and enacted for a General Emergency.

All emergency personnel will have been activated and all response centers are operating.

Information is evaluated and forwarded to the proper authorities and the public. Protective actions will be instituted as needed for the public and milk animals. 4.6 Activation of Emergency Response Organization:

Emergency procedures necessary to cope with the plant system malfunction will be implemented.

All on-duty operations personnel will report to the Control Room. Control Room ventilation*

dampers will be switched from outside to inside air and the charcoal filters will be put into service. June 2016 GN 4-6 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Plant Security:

During a plant evacuation, the plant security officers assist in the activation of the plan as follows:

• The Security Shift Supervisor will deploy resources to restrict access to the owner controlled area during an Alert or higher. They will inform the TSC Security Coordinator or Corporate Emergency Director of any security issues.

• At least one security officer will remain in the Access Control Facility to instruct all evacuating personnel leaving the plant to proceed to the Training Center or alternate assembly area until released.

The security officers at the plant entrance will stop all personnel and their vehicles from entering the site and direct them to the Training Center or alternate assembly area until the TSC Security Coordinator or his designee notifies them that the condition has been corrected.

Radiation Protection:

The EOF Radiation Protection Manager shall assist the Corporate Emergency Director in evaluating the emergency.

The TSC Radiation Protection Manager will report directly to the Technical Support Center. Other Radiation Protection section personnel will: a) Report to the Technical Support Center and assume responsibilities as stated iri the implementing procedures.

• Radiation Protection personnel shall ensure that dosimeter readings of evacuated personnel who were in radiologically controlled areas of the plant are recorded.

• During off-duty hours, RP technicians shall report to their emergency response locations as stated in the implementing procedures.

The duty RP Technician shall report to the Control Room and provide radiological assessment support as deemed necessary by the Shift Manager.

• Chemistry:

The Chemistry Group Lead shall assist the Shift Emergency Director and the Corporate Emergency Director in evaluating the emergency.

The Chemistry Group Lead compares plant effluent monitors to release rate limits. The Chemistry Group Lead will report directly to the Operations Support Center. Off-Duty Personnel:

Off-duty personnel, upon notification, shall report to their emergency response locations, unless directed to the Training Center, where they would pick up the equipment needed for safe plant entry. 4.7 Immediate Assessment:

The Shift Emergency Director (Shift Manager) shall immediately assess the incident.

The Shift Emergency Director is responsible for the implementation of the Emergency Plan until command and control is transferred.

The Shift Emergency Director will evaluate plant conditions by checking control and June 2016 GN 4-7 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear safeguards systems, plant data and radiation monitors.

The Shift Emergency Director shall ensure all offsite agencies are notified in accordance with EP-CE-114-1 ooand that the following information is given: a) Name of facility and communicator b) Date/time of incident c) Class of Emergency (Unusual Event, Alert, Site Area Emergency, General Emergency) d) Brief Description of Event e) Radioactive Material Release (None, Atmospheric, Ground, Lake) f) Protective Actions Recommended for appropriate population g) Temperatures and wind sp*eed and direction The Wayne County Emergency

_Management Office and the Monroe County Office of Emergency Management will be notified at the same time through the use of the New York State Radiological Emergency Communications System (RECS). An Emergency Communicator is part of each shift and will maintain contact with New York State and the counties during an emergency.

As the RECS line is a closed system, call-back verification by the State and counties is not necessary.

The Comm*unicators will also maintain communications with the NRC via the Emergency Notification System (ENS}: If necessary, the Shift Emergency Director shall issue radiation protection equipment

• and dispatch an RP Technician team to conduct in-plant or area surveys. Prior to augmentation, the Ginna RP Technician is dedicated to on-site activities.

If necessary, a relief schedule will be determined. (See Radiation Protection During an Emergency, Section 4.9.1 ). 4.8 Subsequent Actions: To ensure that immediate and direct action is taken in an emergency situation, the Technical Support Ceriter, Operations Support Center and the assembly area in the Training Center or Warehouse will be staffed. Details for staffing are in the implementing procedures.

During normal working hours, individuals assigned to the* Technical Support Center and the Operations Support Center will go there directly.

During off-duty hours, upon notification of an emergency through the call out procedure, personnel may report to the TSC and OSC using normal procedures unless directed to the Training *Center. At the Training Center, implementing procedures provide guidance for site entry. When qualified individuals arrive, they shall the responsibilities of TSC Director.

The Station Emergency Director shall assume responsibility for the activation of onsite Emergency Centers and establish contact with the Control Room. The Station Emergency Director will request from the on-duty Shift Manager an evaluation of plant conditions and all data which has been relayed to the state in preparation for assisting the Corporate Emergency Director in the EOF in the transfer of command and control. June 2016

• GN 4-8 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear The EOF Radiation Protection Manager or Environmental Coordinator will dispatch monitoring teams to areas of concern and request each team to report by telephone or radio. Offsite Monitoring Teams shall not be placed in a position where they might receive a whole body dose greater than 1 Rem without special permission from the Corporate Emergency Director.

The Corporate Emergency Director will report conditions to company management.

• -The Corporate Emergency Director will evaluate radiological data and plant parameters.

Current conditions and follow-up actions will be reported to management periodically.

The New York State officials and Monroe County and Wayne County Directors of Emergency Management will be kept advised of changing conditions.

Responders are assigned as the Ginna Liaisons at the State and County Emergency Operating Centers to provide information and data to offsite agency.officials.

Follow-up messages to offsite authorities will contain the following information as appropriate:

a) Location, name of caller . b) *Class of emergency and date and time of inCident c) Type of actual or projected release, estimated duration and impact time

• d) Estimated quantity of release for various materials e) Chemical and physical form. of release material (noble gases, iodine, particulate) f) Current weather conditions g) Actual or projected dose rate and time integrated dose at site boundary h) Projected dose rate and integrated doses in affected sectors i) Estimation of any surface radioactive contamination j) Recommended emergency response actions or protective measures k) Prognosis for course of the event I) Status of in-plant emergency actions, and licensee response m) Request for further support The Emergency Medical Plan will be instituted, if necessary.

The Shift Emergency Director shall be provided with any survey data necessary to meet his/her responsibilities.

The Corporate Emergency Director will determine if additional personnel should be called to the plant to cope with emergency conditions.

• Personnel and cars shall be monitored and surveyed to assess the extent of contamination before leaving the site unless personnel safety or emergency actions require immediate response.

All non-essential personnel should be allowed to leave the site. June 2016 GN 4-9 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear 4.9 Onsite Protective Actions: During a radiological emergency, protective actions will be employed as follows: 4.9.1 Radiation Protection During an Emergency:

During a radiological emergency, precautions and limitations to minimize doses shall be observed by personnel entering an incident area. In general, doses will be limited to station administrative control levels for occupational radiation exposure in accordance with station procedures.

Every effort shall be made to keep exposure As Low As Reasonably Achievable (ALARA) while accomplishing the necessary tasks. Radiation exposures in an emergency shall be evaluated on an ALARA basis. Offsite Monitoring Teams are limited to 1 Rem TEDE dose during the incident unless special permission is given by the Corporate Emergency Director or the EOF Radiation Protection Manager. Information on post-accident doses is provided in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) for Ginna Station. For lifesaving actions such as the removal of an injured person and providing first aid, ambulance service, medical treatment or other actions required to reduce severe health effects to the public, volunteers may receive greater than 25 Rem TEDE whole body exposure.

The limit set for performing assessment actions or undertaking mitigative actions to prevent substantial radiological releases is 25 Rem TEDE. Authorization to receive doses greater than station administrative limits can be given only by the Corporate Emergency Director.

Offsite Monitoring Teams will consist of at least two persons. All entries into high radiation areas must be carefully planned from available survey data, review of personnel current exposure records, and pre-planning of the activities to be accomplished.

Whenever planning to enter an incident area, use the applicable EP Implementing procedures to adequately protect the responders by determining the appropriate survey instruments, protective clothing, dosimetry, respiratory protection or other resources needed. Close communications between team members shall be maintained as much as possible.

The radiation protection program during an emergency will be based on the program defined in the RP series of procedures.

Dosimeters are available in the onsite and offsite emergency facilities for the Offsite Monitoring Teams. Provisions for round-the-clock capability to issue dosimeters and maintain dose records will be established to meet long-term needs of the plant procedures.

The capability to read dosimeters will be used to maintain control of individual doses. 4.9.2 Site Evacuation:

EP-CE-113, Personnel Protective Actions, provides specific instructions for evacuation of the Protected Area. The evacuation alarm (special tone) will be activated from the Control Room per direction from the Shift Emergency Director.

Upon becoming aware of the evacuation alarm, all personnel, except those whose duties during an emergency specify otherwise, shall immediately leave their area of work by the nearest exit. All building exits to the outdoors may be June 2016 GN 4-10 EP-AA-1012 (Revision

3)

Ginna*Annex Exelon Nuclear used. Normal egress of the radiologically controlled area should be used if possible.

If not possible, workers should use the nearest exit and remove their protective clothing, if worn, as directed by procedures.

Personnel will walk to the Assembly Area and stand by for further instructions.

All dosimeters will be retained by the individual.

The "Assembly Area" refers to the Training Center or alternate locations defined in emergency procedures depending on plume direction and habitability considerations.

The escort accompanying any visitors is responsible to see that visitors are taken to the Assembly Area. Other personnel who may be onsite outside the Protected Area would .hear the site evacuation signal. After evacuation of the plant areas, an accounting will be made of all personnel who were onsite. Accountability of personnel is carried out by plant security using the "onsite" computer list to determine that all persons are accounted for. The Security Shift Supervisor or TSC Security Coordinator initiates a process to verify accountability for all individuals inside the protected area. Drills have indicated that this process can be completed within 30 minutes. This process is verified to be complete by the Corporate Emergency Director using their checklist.

Cars will be monitored and surveyed as necessary before they are allowed to leave the site. Personnel leaving the site will take* a route selected by the Corporate Emergency Director, after consultation with the Wayne County Emergency Operations Center (EOC), giving consideration to the 'wind direction or road impediments. (see Figure 4.2) Before leaving, persons will be monitored for contamination.

Normally, private cars will be used for leaving the site. If cars are contaminated, buses wiil be brought in for the evacuation.

The Corporate Emergency Director will consult with the Wayne County Emergency Director concerning numbers of evacuating personnel and vehicles, and which evacuation routes will be used. 4.9.3 Emergency Medical Treatment: . All emergency medical treatment will be carried out using an emergency medical treatment plan. This plan specifies the types of medical action to be taken in any type of radiation or contamination emergency.

First aid team members maintain their proficiency through Red Cross First Aid Training or equivalent as a minimum. The Emergency Plan Implementing Procedure for Emergency Exposures and Kl, provides guidelines for the administration and use of potassium iodide (Kl) for onsite personnel arid Offsite Monitoring Teams. The determination of need for Kl is the responsibility of the TSC Radiation Protection Manager or the EOF Radiation Protection Manager. Approval of the Corporate Emergency Director is required.

Radio-protective drugs will be issued for the general public only if approved by the New York State Department of Health.

• June 2016 GN 4-11 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 4.9.4 Search and Rescue: Following site evacuation, all personnel will be accounted for using security records, sign-in sheets, log sheets, etc. The Corporate Emergency Director and Station Emergency Director will determine the necessity for a search and rescue operation.

Such an operation will be coordinated by the Shift Emergency Director and the TSC Director.

The search and rescue team will consist of at least two persons including a Radiation Protection technician.

The search should start at the last known location or work assignment of the unaccounted-for individual.

Radiation surveys should be made as the team progresses.

It may be necessary to administer first aid to the individual after he or she is located. The Corporate Emergency Director, TSC Director or Control Room shall be advised of the situation.

June 2016 GN 4-12 EP-AA-1012 (Revision

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Ginna Annex ML June 2016 Exelon Nuclear FIGURE 4.2 EVACUATION ROUTES --

WL GN 4-13 . . EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 4.9.5 Decontamination:

A Radiation Protection procedure provides guidance for graduated measures to. be used for decontamination.

The objective of decontamination is to prevent the spread of radioactive material on the individual, to the environment or to other personnel and to reduce the resultant dose. Decontamination is essentially the removal of radioactive material and is performed starting with the highest level of contamination using the simplest procedures.

Continued decontamination may show diminishing effectiveness and require a decision to stop or use more potent agents. Decontamination kits, which contain items to decontaminate the skin and for wound cleansing, are available.

Decontamination should continue until it is no longer effective but not so as to abrade skin. This procedure should be effective against iodine and other contaminants.

If personnel cannot be decontaminated to the limits of Procedure RP-AA 350, Contamination Monitoring, Decontamination and Reporting", Radiation Emergency Assistance Centerff raining Site (REACffS) may be contacted.

Instruments are available to determine contamination levels of personnel or equipment and the effectiveness of decontamination.

Waste drums are available as containers for radioactive waste and emergency clothing is available, if needed. 4.9.6 Offsite Authorities Actions: Offsite authorities will provide assistance as needed to protect the public. In the . event a Site Area Emergency is declared, this may include activating the public notification system and providing information and periodic updates of the situation through the EAS (Emergency Alert System) and/or press briefings.

Resources at primary response centers will be augmented by calling other emergency services to standby status and dispatching certain emergency personnel to initiate their functions (i.e., monitoring and communications).

Information from the licensee, monitoring teams and weather stations will be continually evaluated with regard to changes in protective actions already initiated for the public, such as sheltering of people or milk animals. Monitoring results and any actions taken should be reported to the licensee and others having a need to know. 4.1 O Major Release to Lake Ontario or Deer Creek: If a major release to Lake Ontario or Deer Creek occurs which exceeds the Technical Specifications limit or the limiting concentrations specified in 1 OCFR20, Appendix B, Table II, Column 2, at the point of discharge, the following actions shall be taken: The release will be classified per EP-AA-1012, Addendum 3, Radiological Emergency Plan Emergency Action Levels (EALs) for Ginna Station, and appropriate notifications will be made, if necessary, per the classification and corresponding procedures.

The Ontario Water District will be notified.

The waste discharge will be isolated, grab samples will be obtained, and dilution will be estimated in accordance with EPIP-1-16, Radioactive Liquid Release to Lake June 2016 GN 4-14 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Ontario or Deer Creek. The Chemistry Department will be instructed to monitor the Ontario Water District Station water. June 2016 GN 4-15 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear TABLE 4.1 Recommended Protective Actions to Reduce Whole Body and Thyroid Dose PROJECTED DOSE TO RECOMMENDED ACTION COMMENTS THE POPULATION Total Whole Body <1 No planned protective None. REM(b) actions. Local authorities or State may issue an advisory to seek shelter and await further instructions.

Monitor environmental radiation levels. Total Whole Body Conduct evacuation. (c) Evacuation should be REM(b) Monitor environmental initiated at 1 REM TEDE or radiation levels and adjust 5 REM COE Thyroid (child). area for mandatory

• evacuation based on these Seeking shelter would be Committed Dose Equivalent levels. an alternative if evacuation to the thyroid (child) ;;:::5 Control access. were not immediately REM. possible.

Implement Kl plan. GUIDANCE ON .DOSE-LIMITS FOR WORKERS PERFORMING EMERGENCY SERVICES TEDE Limit Activity (rem) 5 All activities during the emergency 10 Protecting valuable property 25 Lifesaving or protection of large populations

>25 Lifesaving or protection of large populations, only if individuals receiving exposure is a volunteer, and fully aware of risks involved.

June 2016 GN 4-16 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear (a) Sum of the external dose equivalent and committed dose equivalent to pregnant adults from exposure or intake during emergency situation.

Workers performing services during emergencies should limit dose to the lens of the eye to three times the listed values and doses to any other organ (including skin and body extremities) to ten times the listed value. These limits apply to all doses from an incident, except those received in unrestricted areas as members of the public during the intermediate phase of the incident. (b) The sum of the effective dose equivalent resulting from exposure to external sources and the committed effective dose equivalent incurred from all significant inhalation pathways during the early phase. (c) Sheltering may be the preferred protective action determined and implemented by the County when it will provide protection equal to or greater than evacuation, based on consideration of factors such as source term characteristics, and temporal or other on site-specific or off-site conditions.

June 2016 GN 4-17 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 4.11 Public Relations:

Public information will be released by a Company spokesperson operating from the Joint Information Center. Public information personnel will be assisted by a Technical Advisor who keeps in contact with the Corporate Emergency Director and EOF operations.

Company personnel will exchange information with government Public Information officers on a timely basis. All news releases will be coordinated among Federal, State, County and Company sources. The Company communications department will be notified of any activation of this plan beginning at the Unusual Event classification level. Initial notification at the Unusual Event will be from the Control Room using an automated notification system. Instructions for notifying public information personnel at higher classifications are .contained in EP-CE-114-1 oo, Emergency Notifications.

The Joint Information Center will be activated during* a nuclear emergency at an Alert or more severe event. The Emergency Plan Implementing Procedures provide for staffing this Center and outline the duties of various positions.

Individuals who are qualified to assume these positions are designated.

Space is . allocated in the Joint Information Center for use by various regulatory and government officials to coordinate and facilitate the flow of accurate information to the public. A Company spokesperson who has access to the EOF will be available to the news media for briefing and questions.

Information concerning plant employees is available through the Public Inquiry function located in the Joint Information Center .. Information concerning the status of the plant, employees and Protective Action Decisions is released by the public information officers representing the Company and Federal, State and local governments.

A public information program to acquaint the public with the proper actions to be taken in the event of a nuclear emergency at Ginna Station will be implemented on an annual basis. This program will provide information about radiation, protective actions which can be taken, suggested evacuation routes, assistance for those with special needs, proper responses to warning signals, and where additional information can be obtained.

The program will be coordinated

• between Company, State and county officials, and consists of items such as printed calendars, brochures and, for Wayne County only, telephone directory instructions.

Material for placement in parks, motels and retail establishments to which transients have access will be provided on an annual basis. An annual briefing and training session will be held to acquaint the news media with the Ginna Nuclear Emergency Response Plan and related government agency emergency plans. Information on plant operation, radiation effects and concerns, the implementation of our Emergency Plan, points of contact for the release of public information at the Company and other relevant topics will be kept current through these June 2016 *

• GN 4-18 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Section 5: Emergency Facilities and Equipment Emergency facilities comprise a number of categories including emergency response facilities, communications systems, assessment facilities, protective facilities and first aid and medical facilities.

Each is briefly described as follows: 5.1 Emergency Response Facilities:

Locations have been designated to be used for evaluation and control of an . emergency situation:

the Control Room, Technical Support Center, Operations Support Center, Emergency Operations Facility, and . the Joint Information Center. Figure 5.1 shows the relationship of these Centers during an emergency.

5.1.1 Control

Room: The Ginna Station Control Room is designed for continuous occupancy following the most limiting accident; therefore, control of plant systems will take place from this center, and on-shift crew activities relating to mitigating the consequences of the accident will be initiated and coordinated by the on-duty Shift Manager in the Control Room. Equipment for radiation monitoring, protective clothing and respiratory equipment are kept in an emergency cabinet. 5.1.2 Technical Support Center (TSC): An area at the east end of Ginna Station Turbine Building has been constructed

\ for use as the TSC. It is equipped for direct communication with the Control Room, Operations Support Center and the Emergency Operations Facility.

The TSC also has direct phone lines to the NRC, New York State, Monroe and Wayne Counties, as well as radios and normal phones. A terminal to the plant process computer data link is installed in the Center for obtaining plant Operations data. Piping and equipment drawings are also available.

A radiation monitor is mounted in the Technical Support Center. The Center has filtered air supply and is shielded to meet the same habitability requirements as the Control Room. A continuous air monitor is installed to indicate the activity of airborne iodine, noble gas and particulate.

This Center meets the criteria of NUREG-0696 and is within 2 minutes walking time of the Control Room. Protective clothing and breathing apparatus are available, if needed; June 2016 GN 5-1 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear FIGURE5.1 GINNA STATION EMERGENCY CENTERS INTERFACES Emergency Operations Facility I I I I I I NRC Joint Information Operational Technical Support State EOC Center -----Support Center Center County EOCs I I I I I I Control Room June 2016 GN 5-2 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 5.1.3 Operations Support Center COSC): An area within the Ginna Administration Building has been designated as the OSC. The facility is co-located with the Outage Control Center (OCC). Personnel who are capable of providing support to the Operations needs of the plant will be assigned to this area in case of an emergency.

Telephones and the plant GAl-Tronics page are available.

Personnel designated by the implementing procedures who are onsite will report directly to the OSC. OSC personnel responding from offsite will report to the OSC unless directed to the Training Center or EOF. The OSC is staffed by the Maintenance personnel, Integrated Work Management and other requested organizations.

The planners will prepare work packages for the craft personnel.

The overall management of the OSC is provided by the OSC Director.

The TSC Maintenance Manager is located near, and works directly with, the TSC Operations Manager to determine equipment needs vital to safe plant operation.

The TSC Maintenance Manager receives input on equipment problems and priority of Operations concern from the Control Room via the TSC Operations Manager. The TSC Operations Manager and TSC Maintenance Manager receive information via wireless headsets or telephones from the Control Room staff. The TSC Maintenance Manager provides direct input to the OSC via the OSC Director.

The OSC is not a "hardened" facility and, therefore, does not have any protection from airborne radioactivity.

The procedure for activation of the OSC has provisions that, if the ambient radiation levels or airborne radioactivity levels become too high, the OSC will be relocated to the TSC. The OSC is directed by the OSC Director.

The TSC Maintenance Manager communicates with the TSC Operations Manager and the Control Room. The TSC Maintenance Manager is located in the TSC near the Operations Manager.

• This allows the maintenance organization to get input on maintenance priorities from the TSC staff. The TSC Maintenance Manager has a dedicated telephone in the TSC. Each OSC position has a dedicated telephone extension.

Supplies in the OSC include respiratory protection equipment, protective clothing, portable lighting and portable radios. Potassium iodide tablets and self-reading pocket dosimeters are also included in the OSC locker. Radiation monitoring equipment for surveys of the OSC or for use out on a job is available in the TSC or in the Radiation Protection office. Emergency equipment necessary to repair, control or mitigate the consequences of an accident is available in shops and in the stockroom within the plant. 5.1.4 Emergency Operations Facility CEOF): The Emergency Operations Facility (EOF) for the Ginna Nuclear Power Plant is located at 1255 Research Forest, Macedon, NY, approximately 12 miles from the plant. The EOF shares the structure with the Joint Information Center (JIC). The June 2016 GN 5-3 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear building is a single story structure of 19,000 square feet situated on a 7.23 acre land parcel with parking space for 200+ vehicles.

Approximately 7 ,500 square feet is designated and kept in readiness to operate

• as an EOF. An additional 4,000 square feet is utilized for training space but can be activated for use during a nuclear event. It will accommodate the numbers of people anticipated and provides facilities for .these people. During an emergency, the entire building will be secured for exclusive use by emergency personnel.

Space is allocated for Exelon personnel, NRC, Federal, State, and Local Government officials.

In addition, sufficient space for Ginna emergency personnel and support groups, such as vendors and consultants, is available in the building.

Facilities and briefing areas are provided for the Exelon Communications personnel, news media and general public. Facilities are provided for the news media and the Company emergency

• communications personnel in the front portion of the building.

Ample telephone and data communications are provided for the emergency personnel and news media. Emergency personnel are provided with communications redundancy:

digital and Centrex lines are provided through multiple vendors; and dedicated lines to Baltimore (MD), Albany (NY), Lyons (NY), Rochester (NY), Ginna Station and the NRC are available.

A satellite phone system is also provided.

The data/computer system has its own network server and is supported on T1 lines back to Ginna and Exelori in Baltimore, MD. way radio communications are installed for use by radiological Offsite Monitoring Teams. Cable TV service is provided by the local cable provider.

To aid in emergency-assessment, pertinent information (such as engineering drawings, UFSAR, Technical Specifications, etc.) is stored at the facility and available via computer.

A terminal to the plant process computer data link is installed in the facility for obtaining plant Operations data. As the emergency is evaluated, accurate and up-to-date information of the situation is relayed to appropriate governmental . agencies and the public through this center. Communications equipment and radiation monitoring equipment for use by field teams from the EOF are maintained and readily available to them. The EOF is also the alternative emergency facility for the TSC and OSC for planned and unplanned maintenance.

The EOF has been designated as the Alternative Facility as required by 1 OCFR Part 50 Appendix E Section IV.E.8.d to be used in the event of a hostile action. 5.1.5 Joint Information Center (JIC): The* Joint Information Center (JIC) for the Ginna Nuclear Power Plant is located at 1255 Research Forest, Macedon, NY. The JIC shares the structure with the Emergency Operations Facility (EOF). The building is a single story structure of 19,000 square feet situated on a 7.23 acre land parcel with parking space for 200+ vehicles.

The structure was erected in early 2005 and was built in accordance with the Town of Macedon and the State of New York building codes. June 2016 GN 5-4 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear The auditorium will be used for press conferences during the emergency.

When not used for press conferences, it may be used as a conference room or classroom.

The auditorium is 3,500 square feet and has a 1po seat capacity.

The media work area adjacent to the auditorium will be used for phone communications by the news media. Sixteen phones are available for use by the news media. Basic information regarding the status of the Ginna Nuclear Power Plant will come from the EOF. After review by Company technical personnel, -news releases will be issued from the Joint Information Center. A telephone center for response to the general public will be established and the EOG Communicator in the EOF will be in GOntact with elected officials.

5.1.6 Habitability

The offsite facilities are located approximately 12 miles south of the Ginna plant. Since their location is not in the direction of the prevailing wind patterns and considering the relative distance from the plant, radiation protection equipment is not a consideration.

Building heat at Research Forest is provided by natur.al gas fired, forced air, furnaces.

Cooling is provided with electric split* units. The building's electric supply is 480 volt three phase, 600 amp service. Both the gas and electric mains are underground.

A secondary electric source is supplied by natural gas fueled generator, which provides 50 KV at 480/208/120 voltages.

The building is also supported with a UPS/battery system and provides 208/120 volt service for approximately 30 minutes. This is to allow for a delayed sta*rt of the generator.

Lavatory . facilities are available and can accommodate the emergency personnel anticipated.

5.1.7 Alternative

Facility:

The Alternative Facility maintains the capability for staging the TSC/OSC emergency response organization personnel in the event of a hostile action. This alternative facility has. the capability for communications with the emergency operations facility, control room, and plant . security and the capability for engineering assessment activities, including damage control team planning and preparation.

Consistent with NRC EPFAQ No. 2013-005, the EOF will satisfy the offsite notification responsibilities for the Alternative Facility.

The Alternative Facility is located at the Ginna EOF/JIC located at 1255 Research Forest, Macedon, NY. 5.1.8 .Categories of Emergency Equipment Equipment used for responding to a radiation emergency is stored in Emergency Response Facilities (ERFs), (i.e., Technical Support Center, Control Room, Operations Support Center and Emergency Operations Facility).

Implementing procedures establish minimum quantities of equipment and describe inventory and testing requirements.

Equipment may include survey and air sample instruments, respiratory protection, communications, dosimetry, and protective clothing.

Equipment used for responding to a radiation emergency which would* necessitate site evacuation is stored in strategic storage locations:

Training Center and Warehouse.

Implementing procedures establish minimum quantities June 2016 GN 5-5 EP.:AA-1012 (Revision

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Ginna Annex Exelon Nuclear

• of equipment and describe inventory and testing requirements.

Equipment may include survey and air sample instruments, respiratory protection, communications, dosimetry and protective clothing.

Minimum quantities of equipment are stored in each location and periodically inventoried as described in implementing procedures.

5.2 Communications

Systems (Ginna Station):

A broad range of communication equipment is available at Ginna Station. Several systems are installed for communication between Ginna Emergency Facilities and for communication with outside agencies.

Equipment is periodically verified operable by plant procedure.

The use of particular types is specified in* the appropriate implementing procedures as first choice and backup systems. All services other than radio are underground between centers. Communication systems are tested periodically.

5.2.1 Evacuation

Warning: A special warbling tone* on the GAl-Tronics page system is sounded from the Control Room to warn personnel of a site evacuation.

Warning is immediate to all persons on site as directed by the Emergency Plan Implementing Procedures.

High noise areas have, in addition to the Public Address system, red warning lights with signs to direct personnel to evacuate.

Special announcements on the page and special tones are used for other emergencies.

5.2.2 Phone

Systems: Communications among the Control Room, Technical Support Center, Emergency Operations Facility and Joint Information Center can be established using telephone, radio or plant PA System. A description of the specific telephone methods of communication are as follows: 1) Dedicated ring down lines between:

• Station Emergency Director and Corporate Emergency Director

• TSC Radiation Protection Director and EOF Radiation Protection Director 2) PBX between all facilities

3) Commercial lines in the EOF and CR Communication systems are tested periodically according to* the schedule in the implementing procedure.

The telephone system at Ginna affords a great deal of flexibility and capacity.

Calls can be received or made to either the Frontier telephone system or the local Verizon telephone system. The telephone system has its own power supply* located onsite which could maintain house phones independent of offsite lines. There are Ontario direct lines powered by the Verizon telephone system. The Control Room, Technical Support Center, Emergency Operations facility and the Central Alarm Station also contain satellite telephones for redundant communications in the event of phone system problems.

June 2016 GN 5-6 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear In case of an emergency, personnel not at the plant can be summoned using either the on site phones or direct lines to the Verizon and Frontier systems. A contracted notification system is used to notify responders of an emergency at the site. Offsite radiation Offsite Monitoring Teams are also provided with portable cellular telephones as back-ups for their portable radio$. 5.2.3 Radio Systems: There are three frequencies available for use at Ginna Station. They are assigned to the Fire Brigade, Security, and Radiation Monitoring.

The base stations and antennas are located for maximum transmission coverage of the areas of use. The security channel is monitored at the Central Alarm Station, the Secondary Alarm Station, and the Access Control Facility.

The Radiation Monitoring and Fire Brigade channels have operator capability at the Technical Support Center and at the Emergency Operations Facility.

Portable radios are available for use by Offsite Monitoring Teams in the field. Security has a *radio channel for communication with the Wayne County Sheriffs.

Portable low power hand radio sets are located in the Technical Support Center to be distributed in the event of an emergency for backup or mobile communication.

Portable hand radio sets are also located in the EOF and Training Center for use by the Offsite Monitoring Teams. Offsite Monitoring Teams can communicate with the Technical Support Center or EOF. i 5.2.4 Offsite Communications:

\ Extensive phone communications capability exists at the EOF at the Research Forest building.

There is installed capacity for 400 _telephone lines from Research Forest to local telephone exchanges.

Approximately 140 telephone lines are maintained as active. Each one of these lines can have several handsets at different locations sharing a common circuit. The Research Forest system is powered by an AC power supply which is backed up with a generator and battery uninterruptible power supply. A satellite telephone is installed in the TSC. This phone can be used if the commercial telephone system is inoperable or if there are transmission or grid problems that affect the offsite phone system. Additional circuits to the Ginna plant are provided by five outgoing and five incoming lines provided by the Verizon system. A 25 line Centrex system to the EOF and Joint Information Center is totally separate from the site Nortel PBX. A direct line is connected between EOF Dose Assessment and the TSC. There are four satellite phones at the EOF. A radio communications system provides the backup to the Ginna phone system. Three other .frequencies are available in the Control Room and Technical Support Center for the use of Fire Brigades, Radiation Offsite Monitoring Teams, and Plant Security.

The use of these channels is explained in Section 5.2.3. The EOF has access to all channels except security and provides monitoring of the Radiation Offsite Monitoring Teams during an incident.

Direct contact between the EOF and the TSC or Control Room is possible on the 153.50 MHz channel in case of telephone failure. June 2016 GN 5-7 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear The New York State Radiological Emergency Communications System (RECS) has drops at 9 locations across the State connecting the Ginna plant, TSC, EOF, Wayne County, Monroe County and New York State Emergency Operations Centers (EOCs). There is also a network of facsimile machines connecting key areas as well as telephone paging units for key staff position persons. 5.2.5 Offsite Notification:

Notification to State and county emergency response organizations is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day. The State Warning Point is staffed ,around the clock by the New York State Office of Emergency Management.

The Monroe County Office-of Emergency Management and Wayne County Emergency Management Office answer the RECS line during the workday. During non-business hours, weekends and holidays, the RECs line is covered for Wayne and Monroe Counties at their 911 Centers. At Ginna Station, there are always Control Room personnel to originate calls. New York State has responsibility for communications to other counties which may fall within the ingestion pathway exposure zone. Any contacts with Canada would also be through the State agencies, To contact appropriate offsite agencies, the telephones would normally be used as previously noted in Section 5.2.2, with direct lines or the commercial telephone system. If necessary, offsite agencies can be contacted using satellite phones. Communications with Federal emergency response organizations consists of telephone contact to the Department of Energy, Brookhaven . Radiological . Assistance Program. This call would be made by the EOF Director per our letter of agreement with Brookhaven.

Their assistance may also be requested by the State or Counties.

The NRC Emergency Telecommunications System (ETS) consists of the NRC Emergency Notification System (ENS) "red phones". They are installed in the .. Control Room, the EOF and the Technical Support Center (including the NRC office). NRC Health Physics Network phone$ are also available in the Technical Support Center and EOF. There are additional ETS telephones in the EOF and TSC. 5.3 Assessment Facilities:

Facilities are provided for the assessment of post-accident radiological conditions in order to determine the appropriate emergency measures.

They consi$t of onsite monitoring systems, laboratory facilities and environmental radiological monitoring and sampling equipment.

5.3.1 Safety

Assessment System and Plant Process Computer System (SAS/PPCS):

The PPCS incorporates the Safety Assessment System. The PPCS computer system at Ginna Station provides historical and real time plant information via displays and hard copy devices that are located in the Ginna June 2016 GN 5-8 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Control Room, the Technical Support Center and the Emergency Operations Facility.

PPCS display and report information is accessed via an alpha-numeric keyboard or icons that support menu driven functions.

PPCS provides the logging and archival capability.

Both computer systems are designed to assist Control Room operators and emergency response personnel in the decision-making process during normal and abnormal plant conditions.

5.3.2 Process

Radiation Monitoring System: The process radiation monitoring system provides indications and alarms which permit assessment of in-plant conditions, as well as providing certain automatic actuations.

The general functions of these systems are as follows: a) To indicate primary system leakage and fuel rod failures.

b) To indicate radioactivity levels in selected process systems. c) To indicate radioactivity released through vents or drains. d) To provide visible and audible alarms in the Control Room when a significant increase in radiation occurs in systems or areas. e) To alarm in the Control Room on monitoring equipment failure. f) To shut down a purge or a release .if radioactivity reaches the alarm set points and thereby avoid exceeding the release limits. 5.3.3 Effluent Monitors:

Effluent monitors available at Ginna are listed in Tables 5.1 A and 5.1 B. Of these monitors, particular importance is placed upon the plant vent monitors and liquid release monitor; the former because, as described in Section 3.0, Classification of Emergencies, in combination with other. monitors, they indicate the need for site evacuation and protective actions for the public; the latter because it indicates the need for protective measures with regard to the use of lake water. Alarm set points are based upon the maximum allowable environmental radioactivity concentration and dose which might result from a release and set at a fraction of those values. Monitor calibration factors, correlating monitor readings and vent concentrations can be used to estimate the release rate. From vent concentrations, the offsite dose or concentration levels can be calculated.

Table 5.1 A summarizes these monitors and alarm functions.

Several approaches are available to supplement effluent monitor readings for the assessment of release rates and projected doses. High range monitors have been established for. the estimation of noble gas release from the plant ventilation exhaust point in the event that normal range effluent monitors are off scale or inoperable.

Periodic grab samples of effluent release paths would also be used to quantify and further refine . estimated releases from the plant. Table 5.1 B summarizes the SPING 4 high range monitoring system. June 2016 GN5-9 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear If no release data is available, a method for assessment of release rates is used in conjunction with the X/Q values and offsite concentrations.

The release rate of radioactive material from the plant can be calculated from the measured airborne concentration at a given downwind *sample location and the X/Q value for that location.

Field Team survey results can be used to back calculate doses at the site boundary and offsite. The Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (EPA 400-R-92-001

), NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants (October 1978) and Regulatory Guide 1.109 Rev. 1, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluation Compliance with 1 O CFR Part 50, I (October 1977) provide the methodology for relating radiological measurements in various environmental media or effluent monitor readings to offsite dose or dose rates. Meteorological conditions can be factored into these calculations.

A computer program operating on a personal computer is available in the Control Room, TSC and EOF. This system provides multiple methetts-of calculating downwind dose rates and airborne contamination levels. The-sophisticated computer program, which uses the methods for environmental dose calculations required by Federal regulations, is also available to assess doses during and after an emergency.

Additional information on the radiological consequences of a variety of accidents can be found in Chapter 15 of the Ginna Updated Final Safety Analysis Report. External dose. or dose rates from surface contamination or airborne radioactivity are determined by direct field measurements (dosimeter or survey meter). Internal dose commitments from key isotopes via water or airborne pathways would be evaluated using the uptake rates, dose conversion factors, and other pathway parameters given in EPA 400, NUREG-0133 and Regulatory Guide 1.109. Computer software is available that uses these dose calculation models to determine the radiological dose assessment In this manner, rapid determination of dose estimates from multiple pathways*

may be made for comparison with protective action guides. June 2016 GN 5-10 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear TABLE 5.1A EFFLUENT RADIATION MONITORS RADIATION LOCATION METER READOUT DETECTOR RANGE PURPOSE MONITORS R-10A Top Floor Cold Side Control Room and 1.0E+01 -1.0E+07 1.ndicates the concentration of radioiodine in Containment Iodine Intermediate Building . Plant Computer cpm the containment atmosphere or containment vent air. R-10B " " " Indicates the concentration of radioiodine in Plant Vent Iodine the plant vent air. R-11 " " " Normally measures short-lived particulate Containment daughters of noble gases in the containment Particulate atmosphere or containment vent air. R-12 " " " Measures the noble gas concentration in Containment Gas which xenon 133 is the major isotope present in the containment atmosphere or containment vent air. R-13. " " " . Plant vent particulate monitor normally Plant Vent Particulate measures short-lived particulate daughters of noble gas. R-14 " " " Plant vent noble gas monitor normally , Plant Vent Gas measures low concentrations of xenon 133 from reactor coolant leaks in the auxiliary building .. R-15 Turbine Building Top " " Measures condenser off gas and is usually Air Ejector Floor, NW the first sensor of primary to secondary leakage. R-16 Turbine Building " " Monitors the service water from the Containment Fan Basement Southwest containment fan coolers. Cooling Water Corner R-17 Top Floor Auxiliary " " Used to detect leakage of primary coolant into Component Cooling Building component cooling water. Water R-18 Auxiliary Building Top " " Monitors liquid released for unexpected Liquid Waste Floor West End activity levels. An alarm will isolate the Disposal release. June 2016 GN 5-11 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear TABLE 5.1A (continued)

EFFLUENT RADIATION MONITORS RADIATION LOCATION METER DETECTOR RANGE PURPOSE MONITORS READOUT R-19 Intermediate Bldg South Control Room & 1.0E+01 -1.0E+07 Monitors Steam Generator blowdown water SIG Slowdown Side Intermediate Floor Plant Computer cpm for primary to secondary leakage. High activity will isolate the SIG blowdowns.

R-20A Auxiliary Building " " Monitors for leakage from the spent fuel Spent Fuel Pool Intermediate Floor pool into the service water as the result of Heat Exchanger 1 A West End heat exchanger tube leaks Cooling Water R-208 Auxiliary Building " " Monitors for leakage from the spent fuel Spent Fuel Pool Top Floor pool into the service water as the result of Heat Exchanger 1 B heat exchanger tube leaks Cooling Water R-21 Service Bldg Basement " " Monitors retention tank water which is Retention Tank Recirculation Line collected from normally clean areas of the plant. An alarm will isolate the release R-22 AVT Room N/A 1.0E+01 -1.0E+06 Monitors condensate polisher regeneration High Conductivity cpm waste water activity.

An alarm will isolate Waste Tank the normal discharge R-47 Turbine Building Middle Plant Computer 1.0E+01 -1.0E+07 Measures condenser off gas and is usually Condenser Air Floor, Air Ejector Area cpm the first sensor of primary to secondary Ejector Normal leakage. Range R-48 Turbine Building Top Plant Computer -1.0E-03 -1.0E+OS Measures condenser off gas. Condenser Air Floor, NW µCi/cc Ejector Accident Range June 2016 GN 5-12 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear TABLE 5.18 SPING 4 RADIATION MONITORING SYSTEM Unit #01 Containment Vent Sampler, Unit #02 Plant Vent Sampler CHANNEL RANGE Particulate 2.48E-05 to 2.48E+01 µCi on the filter Iodine 1.38E-05 to 1.38E+01 µCi on the filter Noble Gas 1.0E-06 to 1.0E+OS µCi/cc equivalent Xe-133 Note: Units 1 and 2 can be read on the PPCS or locally on the 296 foot level of the north side of the intermediate building.

Unit #04 Steam Line Monitors NOTE: Unit #04 can be read on the PPCS, digital display in the control room or at the 296 foot level of the intermediate building north. CHANNEL RANGE #01 1.0E-02 to 1.0E+04 mR/hr "A" Steam Line Monitor #02 1.0E-02 to 1.0E+04 mR/hr "B" Steam Line Monitor June 2016 GN 5-13 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear TABLE 5.1C AREA MONITORS RADIATION LOCATION METER DETECTOR RANGE POSSIBLE MEANINGS OF ALARMS MONITORS READOUT OR UPWARD TRENDING OF l\U"\l\llTf"'IDC' R-1 Control Room Control Room and 1.0E-01 to 1.0E+07 mR/hr Possible radiation level in the Control Control Room PPCS

• Room. Possible Control Room Monitor inaccessibility R-2 By Personnel Hatch " " Rising radiation levels in containment Containment R-7 Intermediate Floor " " Indicates flux mapping in progress or I ncore Detector Containment possible rising radiation levels in Area containment R-9 Auxiliary Building, " " Increasing radiation levels in the reactor Letdown Line Basement Floor, NaOH coolant system Monitor Tank Room R-29 Containment, " 1.0E+OO to 1.0E+07 R/hr Primary coolant leak inside containment High Range Operating Floor, Containment Northwest Monitor R-30 Containment, " 1.0E+OO to 1.0E+07 R/hr Primary coolant leak.inside containment High Range Operating Floor, Containment Northeast Monitor June 2016 GN 5-14 1012 (Revision

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Ginna Annex Exelon Nuclear 5.3.4 Area Radiation Monitoring System: The plant area radiation monitoring system provides indications and alarms which assist in assessment of plant conditions.

Its general functions are as follows: a) To indicate the general radiation level in specified areas of the plant.

• b) To provide visible and audible alarms in both the Control Room and the remote meter location when a significant increase in radiation level occurs. c) To provide a visible alarm in the Control Room on meter or detector failure. As described in Section 3.0, Classification of Emergencies, this system is used to initiate local radiation emergency protective action and, in combination with other systems, to indicate the need for a site evacuation and possible offsite protective measures.

Table 5.1 C lists the location of area monitors of major interest.

Alarm set points can be found in Plant Procedures.

High Range Radiation Monitors are installed within containment with readout in the Control Room. A procedure is available by which readings can be converted to an interpretation of the extent of fuel damage and/or radioactivity released to the containment atmosphere.

5.3.5 Source

Range Nuclear Instrumentation:

The two source range channels are used at shutdown to provide an audible count rate signal and audible alarms in both the Control Room and containment

/ to call attention to unexpected increase in neutron flux. A high source range alarm in containment is the signal to evacuate the area. 5.3.6 Continuous Air Monitors:

Several mobile radiation monitors are available within the controlled areas particularly for use during work where local detection of excessive airborne contamination is advisable.

Various combinations . of noble gases, iodine and particulate monitors are available.

These are equipped with meter as well as audible and visible alarms. 5.3.7 Portable Monitors, Sampling Equipment and Other Special Eduipment:

• Portable monitors, sampling equipment and other special equipment for assessing the extent of the consequences of a radiation emergency are located

• in the Control Room, the Radiation Protection office, the Auxiliary Building and the Training Center, including individual survey equipment boxes for each offsite monitoring team. A summary of this equipment is given in Step 5.1.7. Additional sampling and monitoring equipment is also available in the TSC and the EOF. 5.3.8 Process and Containment Monitors:

Numerous process variables are indicated and recorded in the Control Room to ensure safe and orderly operation of all systems and processes over the full operating range of the plant, as well as for detection of off-normal or emergency conditions.

Of these monitors, particular importance is placed upon those which

• provide for detection of a loss of coolant accident and the immediate automatic actuation of equipment to mitigate its consequences.

These include 4 channels June 2016 GN 5-15 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear for Pressurizer pressure, 3 channels for Pressurizer level, 4 channels for Steam Generator level, 4 channels for Reactor Coolant average temperature, 2 channels for steam flow and feedwater flow for each Steam Generator.

Along with these are indications of containment conditions, which include 6 channels for containment pressure, sump level and pump actuation, safety injection recirculation sump level indicator, 4 channels for fan cooler condensate level, and 6 channels for dew point temperature.

Greater detail for the process and containment monitors is given in the UFSAR, Chapter 7. *Seismic and hydrologic emergencies are treated by Procedure ER-SC.4 and SC.2 respectively.

A seismic monitor (accelerograph) is located in the intermediate building sub-basement and a lake level indication is available from the plant computers or the Screen House.

• Information concerning seismic or hydrologic events can be obtained-from offsite agencies such as the NYS geologist at the State Education Department or at Cornell University Geology Department.

5.3.9 Plant

Laboratories:

The laboratory area of the plant is maintained for the purpose of monitoring the condition of a variety of fluid streams and stored fluids including:

the activity and isotopic content; for assessing the degree of contamination of plant areas, movable items and personnel; and for storing, calibrating and maintaining portable and laboratory radiation measuring instruments.

Separate laboratory servic.es are available at Exelon's Ft Smallwood Road Complex in Baltimore, MD for assessing the effect of the plant operation on the environs.

By the use of a Post-Accident Sampling System located in the controlled area of the Intermediate Building,.

samples can be drawn from reactor coolant, containment atmosphere, and containment sump. These samples are processed from a remote control board to open valves, collect the sample, and read out . results of the analysis.

Analyses for chlorides and radioactive isotopes can be completed on diluted, shielded grab samples in a laboratory facility within the times required by NUREG-0737, Clarification of TMI Actio6 Plan Requirements.

Samples can be taken and analyzed without exceeding personnel doses of 5 Rem. This system will also be used for normal Operations samples. In addition to laboratory facilities within the plant, some capability is provideq at the Training Center for use in assessing the offsite effects of an incident.

The chemistry laboratories of the nuclear plants at the Oswego, New York, site are also available to supplement the Ginna onsite laboratory.

5.3.1 O Meteorological Monitoring:

Data on meteorological conditions is available to the Control Room for use in assessing the consequences of an. airborne release of radioactive matter. All meteorological measuring devices, with the exception of the precipitation measuring system, are mounted on a 250 *feet weather tower located at the Ginna plant site. Wind speed, wind direction and temperature are measured at the 150, and 250 feet levels. The 33 foot wind speed and direction sensor June2016 GN 5-16 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear readings are recorded on the Radiation Monitoring Sy$tem Panel in the Ginna Control Room. Temperatures at three tower levels are also indicated in the Control Room by digital display. This information will be relayed to the NRC Operations Center and the New York State and County EOCs. Meteorological data is available continuously and is also programmed for printout at 15 minute averages, accessible from the TSC and EOF. Rainfall is measured by a tipping bucket rain gauge located at the base of the Ginna weather tower. Wind direction, wind speed, and temperature indications from the three tower elevations are also registered on the Ginna Plant Process Computer System. Instrumentation and calibration procedures associated with the Ginna meteorological program are in conformance with Regulatory Guide 1.23. The weather tower is equipped with redundant sensing devices for use as backup indicators of wind speed, direction, temperature and temperature difference.

All meteorological data will be collected and computer processed to provide estimates of radioactive materials transport and diffusion under routine and accident conditions.

Power for the meteorological measurements system and associated equipment is supplied by an electrical feed separate from the plant. Means for remote interrogation of the meteorological system by telephone link is available to the TSC and EOF via computer terminals at each location.

The Buffalo International Airport (National Weather Service) has meteorological instrumentation readings which can be accessed by private phone number on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> basis. A backup weather tower is located in close proximity south of the plant, and has a wind direction and speed recorder.

Means for remote interrogation of the backup meteorological system is available at the TSC and EOF via computer terminal.

An implementing procedure describes the method by which onsite meteorological information is used for the estimation of offsite radiation doses. Based upon wind conditions and determined atmospheric stability, estimates of downwind radioactivity concentrations and doses can be made by dose assessment staff using computerized calculation methods. 5.3.11 Environs Radiological Monitoring:

Sampling systems are established for normal environmental sampling in the immediate area surrounding the plant and also in locations whose distance from the plant roughly corresponds to 1/1 OOth of the onsite radioactivity concentrations estimated from annual average atmospheric dispersion.

These stations contain provisions for air sampling and for radiation dose measurement.

Certain stations include precipitation collectors.

They provide information about the extent of a general emergency and its effect on the environment, in accordance with appropriate implementing procedures.

In addition, an array of dosimeters is in place at the site boundary, at the offsite sampling stations (approximately 10 miles) and at the onsite sampling stations.

• Up to 18 additional have been placed at specified locations, which will add to the evaluation of doses throughout the Emergency Planning Zone. June 2016 GN 5-17 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear The placement of these dosimeters around Ginna Station for routine or accident radiation assessment is given in an implementing procedure.

Maps are included in that procedure so as to locate the TLDs for best coverage (Figure* 5.2). The radiological program provided meets the minimum requirements of the NRC Radiological Assessment Branch Technical Position for Environmental Radiological Environmental Monitoring.

Monitoring teams are quickly dispatched to follow designated routes for the field monitoring within the plume exposure zone. A Ginna Station procedure details the method used for the rapid field determination of airborne particulate and radioiodine concentrations following an accident in addition to radiation levels. The procedure consists of operating a portable air sampler which contains a silver zeolite cartridge and particulate filter, followed by direct filter measurement with a count rate meter probe. The minimum sensitivity for iodine by this method, based upon a 6 minute sampling time, is approximately 2.3 E-8 microcurie/cc.

It is recognized that under certain post-accident conditions, some unavoidable interference from noble gas or high background levels may affect the initial filter readings being taken in the field. The absorption of noble gases in the charcoal cartridge would lead to an overestimate of airborne radioiodine concentrations.

Therefore, silver -zeolite is used. If background levels are too high to determine a proper filter reading, filter measurements will be made at an alternate location out of the radiation plume. Air samples collected by Offsite Monitoring Teams from portable sampling devices and from fixed air monitoring systems may be evaluated using higher sensitivity methods with onsite or near-site analytical equipment (e.g., environmental laboratory).

June 2016 GN 5-18 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Figure 5.2 Dosimeter Locations . I * .s e -t1 -8 ::ii:: ' z .. -0 I I :s I I l I I I J I

• l 8 "' "° Jlt

• 0 I c:> \ ..,. CIC I g :J Iii: ... < 1'12 !:: V1 s ! ... .91 <JO -I June 2016 GN 5-19 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 5.3.12 Emergency Instruments and Equipment:

Emergency equipment for the various centers is described in step 5.1.7. This equipment is checked periodically according to the schedule in implementing procedures to ensure that it is available and operable.

Any instrument or equipment found to be in need of repair or calibration is immediately replaced from the Radiation Protection reserve supplies.

Instruments are calibrated along with plant instruments by the Radiation Protection section according to RP procedures which meet the manufacturers' recommendations.

Sufficient reserves of instruments and equipment are available to replace those that are removed from service for maintenance and/or calibration.

5.3.13 Public Alerting System: An alerting system to make the public aware of an incident at Ginna Station which may require protective action on their part has been developed and installed.

The Ginna prompt public alerting-system consists of 96 sirens. In addition, tone alert radios have been provided at schools, nursing homes and industrial establishments as an enhancement to the Public Alerting System. Tone alert radio locations are listed in EPG-1, Emergency Preparedness Guideline.

The special supplemental needs of transient populations at locations such as motels, parks and work camps will be addressed, as necessary, within the individ_ual county plans. Instructions for transient populations have been distributed to such locations.

The objectives of the Ginna prompt public alerting system are twofold: to alert the general public both indoors and outdoors of the existence of an emergency situation and to provide for the communication of preliminary emergency information.

The design objective for this system is to complete the initial alerting of the affected population within the Plume Exposure Pathway within 15 minutes after the notification of State and local governments by the Ginna. The system was designed to assure coverage of essentially 100% of the population within the 10 mile E_mergency Planning Zone. The control of the system rests with the county officials within their respective borders. In Monroe County, the County Executive has this authority and, in Wayne County, it is the Chairman of the Board of Supervisors.

Sirens are activated by the counties and maintained by Ginna. Tone alert radios are activated by a radio signal from the Emergency Alert System (EAS). The sirens activate for 3 to 5 minutes. 5.3.13.1 Siren Backup: June 2016 A backup activation point is available in each county for activating the alert system should the primary transmitter fail. The siren portion of the alert system is designed to produce a minimum 1 OdB(C) above ambient sound levels in all portions of the Emergency Planning Zone or a sound level of at least 60 dB for population areas with <2,000 persons/mile or 70dB for population areas with >2,000 persons/mile.

GN 5-20 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear The Technical Support Center has an activation point that can be used as a back-up for both Monroe and Wayne Counties.

Each county also has a method for back-up alerting.

In the Wayne County portion of the 10-mile EPZ, route alerting is activated by the Wayne County EOG and carried out using loudspeakers mounted on county-owned emergency response vehicles.

Monroe County's back-up alerting method is a mass-notification reverse-calling system that can send emergency alert messages to specific geographical areas. 5.3.13.2 Siren Testing: Siren reliability Will be tested periodically at 3 levels of operation: 1 . Bi-weekly silent tests to verify system electronic components are functioning.

2. Quarterly manually-activated growl tests 3. Annual full duration audible tests of the entire system. Periodic surveys will be taken by the Federal Emergency Management Agency to determine any difficulties which may require. corrective measures.

Alert system operations reliability is expected to be greater than 95%. Sirens are powered off the RG&E distribution system which has better than 99% availability.

It is fed from the New York State Power Pool grid; therefore, it is not dependent on the operation of Ginna. The Company has the responsibility for maintaining the siren alert system operable.

The location 'Of sirens is given in the Ginna Alert and Notification System (ANS) Design Report. A siren verification system is installed providing remote feedback capability to both counties and Ginna from all 96 siren units. The system is used to verify proper siren activation and to verify whether inadvertent siren activations have occurred.

When appropriate, growl testing of the sirens will be conducted following preventive or corrective maintenance.

Depending on the. scope of the maintenance, the work order will determine if growl testing is appropriate.

5.3.13.3 Emergency,Alert System: June 2016 If the sirens are activated, the Emergency Alert System (EAS) will notify the public of the actions they should take. During an emergency at Ginna, activation of the EAS will be the result of a cooperative decision between lead officials of Wayne and Monroe Counties and New York State. In extenuating circumstances, activation requests may be made unilaterally by one of those entities.

Sample messages to be given over the. EAS via radio and television are part of the county procedures.

A calendar that is distributed annually provides information regarding the system and appropriate actions to be taken. The Wayne County Public Information Officer (PIO) will notify the Local Primary (LP-1) station of an imminent EAS broadcast and will coordinate the broadcast time for the message. If Ginna's JIG has not been activated, or all GN 5-21 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear lead PIOs have not yet reported there when the decision is made by either county to request EAS activation, coordination of the message preparation may take place between the Wayne and Monroe County EOCs. If Wayne County cannot contact the LP-1 station, the Wayne County PIO will communicate the approved EAS message* to Monroe County. Monroe County will read the EAS message to the LP-1 station via a telephone at the Monroe County EOG that is hard-wired into the LP-1 station's newsroom.

5.3.14 Fire Protection Facilities:

The fire protection facilities are comprised of a number of automatic and automatic protection systems as well as assessment and alerting equipment.

Fire protection facilities have been installed in accordance with NRC Fire Protection Safety Evaluations.

Detection is provided in all areas of the plant that contain vital equipment.

The system initiates suppression systems and alarms in the Control Room. 5.4 Protective Facilities:

Aspects of the plant which serve a protective function to personnel onsite in the event of an emergency are described in this section. They include accident shielding, protective ventilation, emergency condition

• signaling equipment, assembly locations, containment control provisions, and other protective equipment and supplies.

First aid and medical facilities are treated separately in Section 5.5. 5.4.1 Accident Shield: The containment vessel consists of the 3.5 feet thick reinforced concrete cylinder capped by a hemispherical reinforced concrete dome of a 2.5 feet thickness.

The shielding includes supplemental shields in front of the containment personnel hatch and 20 inch walls, east and south sides and the roof of the Control Room. The equipment access hatch is shielded by a 3 feet thick concrete shadow* shield and a 1 foot concrete roof to reduce scattered dose levels. Concrete walls and ceiling of the Technical Support Center provide shielding.

5.4.2 Protective

Ventilation:

During normal operation a varying amount of fresh outside air is admitted to the Control Room via the normal Control Room ventilation system. If sensors detect high radiation levels, chlorine gas or ammonia gas in the Control Room outside air intake, the Control Room is automatically isolated, the normal Control Room ventilation system is secured, and two trains of the Control Room Emergency Air Treatment System *(GREATS) will automatically start. GREATS provides charcoal and high efficiency particulate air (HEPA) filtration for removal of radioactive particles and gaseous iodine from the Control Room atmosphere.

The Technical Support Center has filtered fresh air makeup, with charcoal filtration, to meet habitability requirements for occupancy.

June 2016 GN 5-22 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 5.4.3 Alerting Equipment:

Plant personnel are signaled to evacuate at once by a special tone, activated manually in the Control Room. In areas where audible signals may not be heard, special flashing lights have been installed.

For fire and medical emergencies, an explicit announcement is made over the PA system. 5.4.4 Assembly Locations:

Several assembly locations have been established, the selection of which will depend on the conditions of the emergency.

Non-essential personnel affected by a local radiation emergency are to report to the Decontamination Area. In the event of a site evacuation, all Control Room operators are to report to the Control Room, the protective features of which are described above. essential personnel are to reassemble at the Ginna Training Center or alternate assembly area as directed, except for those having a role in the Technical Support Center or Operations Support Center, described in Section 5.1. The Training Center has several classrooms and offices to accommodate essential personnel.

The classrooms and offices, roughly 600 feet from the reactor, seats more than 150 people; there is additional room in the classrooms and offices. A local radiation monitor is installed in the Training Center which houses the Offsite Monitoring Team equipment to aid in the evaluation of the necessity for emergency organization personnel to relocate.

5.4.5 Contamination

Control Provisions:

The plant site is divided into two categories, the "Clean Area" and

• the . . Radiologically Controlled Area. Entry to and exit from the Radiologically Controlled Area is normally through the designated Access Control Point. Any area in which radioactive materials and radiation are present shall be surveyed, classified, roped and conspicuously posted with the appropriate radiation caution sign. These then become Radiologically Controlled Areas and proper access is provided and controlled.

Plant procedures provide the radiation or contamination

• levels at which an area is declared a Radiologically Controlled Area or removed from radiation control status. The general arrangement of the service facilities is designed to provide adequate personnel decontamination and change areas. The clean locker room is used to store items of personal clothing not required or allowed in the Controlled Area. The Hot Shop is employed as a protective clothing change area. A supply of clean protective clothing for personnel is maintained in this area, and there is provision for collection of used protective clothing.

All personnel will survey themselves on leaving the Controlled Area using equipment provided at the Access Control Point. Personnel decontamination supplies with instructions posted for their use are available in the access control area. In the event of a site evacuation, provisions for decontamination are available at the onsite Training Center. June 2016 GN 5-23 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear A 1000-gallon holding tank is available to contain decontamination water from a sink and shower located at the Training Center. Decontamination water will be sampled prior to transfer, treatment or disposal.

5.4.6 Protective

Equipment and Supplies:

Personnel entering the Controlled Area may be required to wear protective clothing.

The nature of the work to be done governs the selection of protective clothing to be worn by individuals.

The protective apparel available is shoe covers, head covers, gloves and coveralls.

Additional items of specialized apparel such as plastic suits, face shields, and respirators are available for operations involving high levels of contamination.

In all cases, Radiation Protection personnel shall evaluate the radiological conditions and specify the required items of protective clothing to be worn. Respiratory protective devices are required wherever an airborne radiation area exists or is expected.

In such cases, Radiation Protection personnel monitor the . airborne concentrations and specify the necessary protective devices according to concentration and type of airborne contaminants present. Available respiratory devices include full face air purifying respirators (filter type both negative and pressured powered air purifying units). ,Air-line supplied respirators of pressure demand type are used as well as constant flow hoods. Self-Contained Breathing Apparatus devices, using full face masks and pressure demand regulators, are also available.

Site specific ERO Respirator qualification requirements contained in the ERO Training and Qualification procedure take precedence over requirements contained in the Exelon Standardized Radiological Emergency Plan for Ginna Station. For use in an emergency, equipment and supplies are located in the Control Room, Technical Support Center, and the Training Center. Equipment categories are given in 5.1.7.

• 5.4.7 Emergency Vehicles:

In the event it becomes necessary to make use of automotive equipment, a number of vehicles will be available.

These include a variety of company-owned vehicles assigned to the Station. Lastly, a large and diverse fleet of vehicles is available from the Company vehicle fleet. 5.5 First Aid and Medical Facilities:

First aid and medical provisions include both onsite and offsite facilities.

The latter are described in Section 2.8, Augmentation of the Emergency Organization.

A dispensary onsite contains sinks; a bed, a stretcher, and miscellaneous first aid equipment and supplies.

Decontamination . supplies can be obtained from the Radiation Protection group. Personnel decontamination kits and bioassay collection kits are available at Rochester General Hospital and Newark-Wayne Community Hospital.

Auxiliary Operators are trained in first aid procedures using Red Cross Media or an equivalent program. An administrative procedure establishes a First Aid Team and the actions to be followed in the event of illness or injury at Ginna Station. June 2016 GN 5-24 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Section 6: Maintaining Nuclear Emergency Preparedness Formalized training program(s) have been established to ensure that all personnel who actively participate in the Nuclear Emergency Plan maintain their familiarity with the plan and their required response.

A radiation emergency exercise shall be conducted at least annually, with emphasis placed upon orderly implementation of the emergency plan. It is the Company management's expectation that responders will respond immediately upon being notified and not wait for additional time. This expectation is reinforced as part of the responder training.

Personnel trained for onsite response to a radiation emergency are part of the regular plant staff and are trained to specific responsibilities within the emergency organization.

Training is documented by the Manager, Emergency Preparedness and the Emergency Preparedness Staff. Any emergency plan work by consultants will be under the control of, and reviewed by, the Manager, Emergency Preparedness.

' Exercises shall be evaluated by the Manager, Emergency Preparedness and reviewed by the Emergency Preparedness Station and Corporate Management, thereby assuring the effectiveness of the plan throughout the lifetime of the R. E. Ginna facility.

6.1 Training

and Drills: Training classes on the emergency plan shall* be conducted once per calendar year not to exceed 18 months between training sessions for all Ginna emergency response personnel who may actively participate in the radiation emergency plan;* Details of the training programs are established

'in Exelon ERO Training and Qualification procedure.

Training will include a demonstration of their ability to perform the functions to which they may be assigned by participating in a Drill or Exercise at least once every two years. During drills, on-the-spot corrections of erroneous performance may be made, followed by a critique or corrective . action. Provisions must be made to start a drill or exercise between 6:00 p.m. and 4:00 a.m. at least once in every eight-year cycle. Some drills or exercises should be unannounced.

• Specialized training will be provided for: 1. Technical Support Center assignees

2. Operations Support Center assignees

3. First Aid Teams 4. Offsite Monitoring Teams 5. Emergency Operations Facility personnel

6. Security personnel

7. Local Emergency Support Services personnel

8. Fire Brigade personnel

9.

• Dose Assessment personnel June 2016 GN 6-1 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear 10. Core Damage Assessment personnel

11. JIC personnel

12. On-Shift Radiation Protection technicians

13. Severe Accident Management Evaluators and Decision-Makers

6.1.1 Emergency

Director:

Training of Emergency Directors will be given annually to the personnel who fill the Corporate and Shift Emergency Director position.

This training will cover responsibilities, communications, emergency classifications, protective action recommendations, and review of all proQedures pertinent to their respective duties under the Emergency Plan. The necessary lesson plans and _training documents are* developed in accordance with Exelon procedures and processes.

6.1.2 . Offsite Monitoring Teams: Offsite Monitoring Team Training will be given to selected personnel.

Training material will cover Radiation Protection practices and techniques utilized during radiation monitoring, Offsite Monitoring Team equipment and its use, . radio communication techniques, monitoring and sampling procedures, survey routes and sample points, contamination and decontamination considerations, and review of implementing procedures used by Offsite Monitoring.

Teams. Field training will be given as needed. 6.1.3 Special Training for Participating Agencies:

Annual training will be provided to offsite support agencies, State and counties

• on EALs/PARs and other pertinent topics. Training shall also be provided at least annually for but not limited to the following groups: a) b) Ontario Volunteer Fire Company Ontario Volunteer Emergency Squad c) Rochester General Hospital d) Newark-Wayne Community Hospital Training for these groups consists of lectures concerning their required involvement during radiation emergencies, procedures for notification, and basic radiation protection.

6.1.4 Drills

and Exercises:

The ERO Training and .Qualification procedure establishes the training program which develops and maintains the proficiency of emergency response personnel.

This program meets the requirements of

• 1 OCFR50 Appendix E Section IV F regarding responding to emergencies.

Through the initial training program and annual drills, personnel will be familiarized with the intent of the plan and the content of implementing procedures.

Key personnel will be trained in the specific duties to which they may be assigned.

Lectures and field training will be used, as appropriate, to familiarize personnel with their duties. June 2016 GN 6-2 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Communications equipment and processes are checked periodically as established by an implementing procedure.

The New York State Radiological Emergency Communications System (RECS) and the NRC Emergency Notification System (ENS) are tested monthly. Fire drills are conducted in accordance with plant procedures.

A medical emergency drill which involves a simulated contaminated/injured individual and participation by the local support services will be conducted annually.

A plant environs radiological monitoring drill (onsite and offsite) will be conducted annually in conjunction with training for and during the annual exercise.

This shall include collection and review of analysis procedures for environmental samples. Radiation Protection drills shall be conducted semi-annually.

Analysis of in-plant liquid samples, including use of the post-accident sampling system, shall be included in Radiation Protection drills annually.

Periodic drills will check communication systems, response time, performance of participants, and interrelations of the various emergency centers. Training drills may be held prior to any exercises.

Exercises will be held in conjunction with Ginna Station, New York State and local governments as required by regulations. . All aspects of an exercise will be monitored by trained observers and a report made to the station and corporate management.

Any comments will be evaluated and actions taken if appropriate.

Emergency response facilities, procedures and equipment are evaluated by the ERO members and the controllers/evaluators during drills and exercises and deficiencies are noted during facility critiques.

Preparation of the scenarios for use in exercises and drills will be coordinated by the Manager, Emergency Preparedness.

The scenario preparation team is appointed by the Manager, Emergency Preparedness to develop the scenario package which shall include the scope, goals and objectives of the *exercise, a time *line of real and simulated events, a narrative summary, participating organizations, appropriate messages and data sheets, evaluation criteria, and information for official observers.

The Manager, Emergency Preparedness will review and approve the scope and objectives for the Annual Ginna Emergency Exercise.

The Manager, Emergency Preparedness will arrange for qualified controllers and coordinate activities of participating organizations.

The scenario should be varied from year to year to test all major elements of the plan within a 8 year period. The exercise shall simulate an emergency that results in offsite radiological releases which require response by offsite authorities.

Annually, a radiation emergency*

exercise will be held. This exercise will be coordinated with principal participating offsite agencies, testing at a minimum the communication links and one other element: Drills will be started at various times of the day and under various weather conditions.

Some exercises will be unannounced.

Hostile action based scenarios will periodically be used to practice and evaluate the integration of security functions with emergency plan implementation (at least one during a eight-year period). Scenarios will be developed which allow for free play in decision-making by those individuals in responsible positions

.. Structured_

responses will be used only to the extent necessary to keep the exercise moving so as to meet the objectives of the exercise.

June 2016 GN 6-3 EP"'.AA-1012 (Revision

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Ginna Annex Exelon Nuclear Written Drill/Exercise Reports shall be submitted by the Manager, Emergency Preparedness to the station and corporate management emphasizing areas of strength and weakness and outlining plans for remedial action, as necessary.

A critique at which controllers, observers and participants may make comments will be held as soon as practical after the exercise to evaluate the actions and interactions of response organizations.

Thes*e comments will be evaluated by the Manager, Emergency Preparedness to determine if they should be entered into the Ginna Corrective Action Program to assure that necessary corrections to the Plan are implemented.

6.1.5 Manager, Emergency Preparedness and Emergency Preparedness Coordinator:

The Manager, Emergency Preparedness

• is responsible for coordinating the Emergency Plan with other response organizations.

They will review the Plan and agreements to certify that they are current. The update will take into account changes identified by drills and exercises.

The Emergency Preparedness Coordinator reports to the Manager, Emergency Preparedness.

The Emergency Preparedness Coordinator provides assistance on emergency planning issues in the plant and will be designated duties by the Manager. The Manager and Coordinator will maintain their awareness of emergency response activities, facilities and procedures by participating in related committees and reviewing completed documentation.

The Ginna procedure change process requires multiple-independent reviews. A 1 OCFR50.54(q) screening is also required for all EP implementing procedure revisions. )he EP Coordinator conducts surveillance of the emergency response facilities through scheduled inspections and tests to ensure their readiness.

The Manager and EP Coordinator meet routinely with Ginna management and supervisors to discuss emergency concerns, training and changes relative to emergency planning.

These meetings include: EP Advisory Committee, PORC, POD, the . Exelon Nuclear Training Emergency Preparedness Oversight Commi:ttee (ENTEPOC), and special task forces. The Manager and EP Coordinator will attend appropriate training, seminars, workshops, and conferences sponsored by the Company, the nuclear industry, and Federal, State and local governments to current on emergency planning techniques and concepts.

The Plant Manager is the chairman of the Emergency Preparedness .Advisory Committee which tracks the progress of emergency planning activities and acts as a sounding board for all emergency planning issues. The EP Manager is a board member. 6.2 Annual Review and Revision of the Plan and Procedures:

The Ginna Emergency Plan will be reviewed and revised annually in accordance with EPIP-5-6.

Revisions to the Plan are subject to approval by PORC. Revisions to the Plan and Emergency Plan Implementing Procedures (EPIP) may be the result of drills, exercises, training or routine surveillance.

The Plan is June 2016 GN 6-4 EP-AA-1012 (Revision

3)

\ Ginna Annex Exelon Nuclear reviewed by the PORC. EPIPs are reviewed in accordance with site and fleet requirements.

Emergency procedure changes are controlled so that only current copies are available for use. Revised procedures are distributed to a list of controlled copy holders. Shift Operators and licensed staff are made aware of revisions during regularly scheduled training coordinated by the Training Department.

Emergency telephone numbers are kept up-to*-date through quarterly review and distribution of revisions.

The Emergency Plan is a Quality Record and shall be processed per Records Management procedures.

Copies shall be maintained in the Station Archives for the lifetime of the plant. 6.3 Emergency Equipment and Supplies:

The operational readiness of all items of emergency equipment and supplies will be assured through periodic inspections of emergency equipment in accordance with implementing procedures.

Communications test with state & local governments (RECS) is performed monthly. The EP procedures include inspecting and testing of equipment stored in the Control Room, OSC, JIC, EOF, Training Center, Technical Support Center and Warehouse.

Also included are tests of the operability of equipment.

Necessary transportation for offsite surveys will be through a company owned vehicle. *6.3.1 Siren Tests and operability:

The Ginna Emergency Sirens shall be activated at intervals not to exceed one year (plus or minus three calendar months). This test will be considered successful if no more thc;in 10% (1 O of 96) of the sirens fail to operate properly.

Any time it is found that siren failures result in the loss of capability to alert more than 25% of EPZ population for more than one hour, the NRC shall be notified.

6.4 Auditing

All Nuclear Emergency.

Response Plan elements are reviewed by persons who have no direct responsibility for the. implementation of the emergency preparedness program either: a. At intervals not to exceed 12 months; or b. As necessary, based on an assessment by the licensee against performance indicators, and as soon as reasonably practicable after a change occurs in personnel, procedures, equipment or facilities that potentially could adversely affect emergency preparedness, but no longer than 12 months after the change. In any case, all elements of the emergency preparedness program must be reviewed at least once every 24 months. The review must include an evaluation of the adequacy of interfaces with State and local governments and of licensee drills, exercises, capabilities and procedures.

The results of the review, along with recommendations for improvements, must be documented, reported to corporate and plant management, and retained for* a period of five years. The part of the review

• June 2016 GN 6-5 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear involving the evaluation of the adequacy the of interfaces with State and local governments must be available to the appropriate State and local governments.

Follow-up implementation tasks are assigned through the use of Condition Reports. The results of the review are reviewed by the Nuclear Safety Review Board (NSRB). June 2016 GN 6-6 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Section 7: Recovery After the initial _emergency response actions are concluded (i.e., the plant is in cold shutdown and under control), a decision to begin the recovery phase will be initiated.

A number of considerations will enter into the decision to begin the recovery phase and dismantle the Emergency Response Organization.

The decision to enter the recovery phase will be made by the Corporate Emergency Director in consultation with the support managers, the Plant Operation Review Committee, and the corporate officers and offsite personnel.

EP-CE-115, Termination and Recovery will be used by the organization to transition from a response organization to a recovery organization.

Federal, State and local authorities shall be advised of any decisions and resulting changes pertaining to the Emergency Organization status. 7.1 Recovery Actions: Re-entry of the plant, decontamination, repair, and return to operation will be controlled by a general implementing procedure which provides for development of a flexible plan of actions and specifies particular evaluation and pla*nning activities.

A recovery.

organization to provide long term augmentation of the emergency organization has been established.

A procedure to alert these people and put the EOF into operation is part of the station implementing procedures.

• EP-CE-115 details the establishment of a Recovery organization.

The Corporate Emergency Director will notify all response organizations that recovery operations are underway.

In the recovery phase, all actions will be carefully planned by station supervisory personnel in conjunction with the Recovery Team, the Technical Support Center personnel and the Ginna senior management.

Planning for recovery will include evaluation of survey data, review of exposures incurred, projection of manpower and equipment needs, and re-entry offsite monitoring team activities.

Actions prescribed upon re-entry include a comprehensive survey of the plant to define radiological problem areas. Based on survey results, high radiation areas and areas of contamination will be isolated and posted and, if possible, portable shielding will be used, as appropriate.

Upon evaluation of plant conditions, further activities for making necessary repairs, decontamination and restoration to normal operations will be outlined by Ginna senior management in accordance with standard Radiation Protection . practices.

Personnel radiation exposure during the recovery stage of the incident shall be Closely controlled and documented.

Individual exposures shall be in accordance with 1 OCFR20 limits. Corporate management and Emergency Response Organization personnel will augment the plant staff in long-term recovery operations.

a) Corporate groups such as Business Continuity may provide logistical support using corporate emergency plans, protocols and procedures.

b) Technical support may be provided by the Engineering Services Department and consultants under the direction of the Manager, Nuclear Services.

June 2016 GN 7-1 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear c) The Vice President, Ginna, will provide management level interface with government authorities.

He or she will be assisted by the Corporate Communications group. d) Communicating with the President of the United States and the Governor of New York State is the responsibility of Company senior management.

June 2016 GN 7-2 EP-AA-1012 (Revision

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Ginna Annex. Exelon Nuclear Section 8: Definitions

• Assembly Area . -A designated building in which all. non-essential personnel congregate following a site evacuation.

• Centers -Locations where communications, equipment and information are . available and personnel will assemble to evaluate conditions during and after an event. See Section 5.1 for details.

• Drill -A drill is a supervised instruction period aimed at developing, maintaining and testing skills needed for a particular operation.

A drill will be supervised by qualified instructors or controllers.

• Manager, . Emergency Preparedness

-The individual who has overall responsibility for maintaining the Ginna Station Nuqlear Emergency Response Plan and implementing procedures.

He/she will also coordinate these plans with New York State and county organizations having emergency responsibilities.

He/she will act as liaison with private organization$

in developing plans which augment the Company plans. *

• Emergency Classification Levels -Four Emergency Classification Levels have been established by the NRC and incorporated into the Emergency Plan Annex and State and county plans. Each Emergency Classification requires a different degree of response actions by the state, counties and the Company. The four emergency classification levels are:

• Unusual Event -Events are in progress or have occurred which indicate a potential degradation of the level of safety of* the* plant or a security threat to facility protection has been initiated.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. Alert -Events are ir:i progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life-threatening risk to site personnel or damage to site equipment because of hostile action. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. Site Area Emergency

-Events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or hostile action that results in intentional damage or malicious acts: (1) toward site personnel or equipment that could lead to the likely failure of equipment needed for the protection of the public; or (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protection Action Guideline exposure levels beyond the site boundary.

General Emergency

-Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or hostile action that results in an actual loss of physical June 2016 GN 8-1 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear control of the facility.

Any releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

• Emergency Director -An individual who has received appropriate training in the actions to be taken in the event of an incident at Ginna Station. He has full authority and responsibility for meeting the emergency.

• Emergency Plan Implementing Procedures (EPIPs), Procedures used to govern actions of the ERO to declare events and respond to a classified emergency.

The following types of procedures are considered EPIPs: Fleet Facility Operations Procedures

-Governing procedure for each Emergency Response Facility directing use of Position Specific Checklists.

Fleet Functional Procedure

-Standard_

procedures directing actions to complete a specific function (such as Classification or Emergency Exposure Controls)

Position Specific Checklist

-Checklist directing actions of an ERO position.

Station Specific Functional Procedure

-Procedures directing actions to complete a station specific function (such as Dose Assessment or Core Damage Assessment)

• Emergency Planning Zone (EPZ) -An area around Ginna Station divided into Emergency Response Planning Areas (ERPAs) for which preplanned actions to meet possible hazards have been developed.

Actions to meet site hazards are the responsibility of the Company. Protective actions in the Emergency Planning Zone (approximately 10 miles) are the responsibility of the county organizations.

New York State is responsible for actions to limit ingestion exposure in the zone out to approximately 50 miles.

• Emergency Operations Facility (EOF) -A facility located at 1255 Research Forest, Macedon, NY, from which additional Company personnel, consultants, NRC and other individuals can provide assistance to the plant in evaluating any emergency, gaining control of it and continuing the recovery operation.

Meteorology, field monitoring and plant data can be evaluated here by the dose assessment staff and recommendations made to the State and counties for protection of the public: The EOF is a coordinating center for gathering and initially evaluating information relative to possible offsite radiation and contamination.

• Emergency Preparedness (EP) Coordinator

'." The Emergency Coordinator provides assistance on emergency planning issues at the plant and will be designated duties and responsibilities by the Manager, Emergency Preparedness.

June 2016 GN 8-2 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear

• Emergency Response Organization (ERO) -Organization put in place to respond to declared events. The ERO replaces normal plant organization when activated and remains in control until the event is terminated.

The full ERO is made up of the following sub-groups:

o On-Shift Personnel

-minimum number of shift personnel filling positions identified in Shift Staffing Assessment.

o Minimum Staffing -The minimum nun:iber of ERO members that must be staffed within one hour whenever the Technical Support Center, Operations Support Center, Emergency Operations Facility and the Joint Information Center are required to activate.

These positions and number of individuals filling them are identified in Table 2.1.

• o Full Staffing:

Total members of the ERO including Shift Personnel, Minimum Staff personnel and augmented staffing.

Full Augmentation positions and

• number of individuals filling them are identified in Table 2.1.

• Hostile Action -An act toward a nuclear power plant or its personnel that includes the use of violent force to destroy equipment or take hostages, and/or that intimidates the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles or* other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.

Hostile action should not be construed to include acts of civil disobedience or felonious acts that are not part. of a concert_ed attack on the nuclear power plant. Non-terrorism-based Emergency Action Levels (EALs) should be used to address such activities (e.g., violent acts between individuals in the Owner Controlled Area).

• Joint Information Center -Located at 1255 Research Forest, Macedon, NY, it has

• facilities for press briefings, public inquiry and general information dissemination.

Information regarding the status of Ginna Station will come from the EOF.

• Local State of Emergency

-May be declared by a county executive in the event that public safety is imperiled by a disaster or public emergency.

Following such a declaration, the county executive may promulgate local emergency orders to protect life and property or to bring the emergency under control. Actions may include prohibition or control of vehicular traffic, closing of public facilities and suspension of local ordinances. (Further details provided in NYS Executive Law Article 2-8.)

• Operations Support Center (OSC) -Located in the Ginna Administration Building's Outage Control Center where personnel qualified to support the Operations needs of the plant will be assigned.

• Protective Action Recommendation (PAR) -Recommendation by the licensee to County and State officials to shelter or evacuate members of the general public based upon plant conditions or projected radiological doses. June 2016* GN 8-3 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear

• Radiological Emergency

-An incident that may result in the uncontrolled release of radioactive material leading to a hazard or potential hazard to the health and safety of the general public. As a result, the Ginna Emergency Organization, the Company recovery organization, and State and county emergency organizations may be activated, depending upon the level of response required.

• State Disaster Emergency

-May be declared by the Governor on his own initiative or pursuant to a request from one or more county executives.

Actions may include public notifications, protective actions, and requests for Federal assistance. (Further details provided in NYS Executive Law Article 2-8.)

• Technical Support Center (TSC) -An onsite facility which is used by the plant staff to assist the operating personnel in evaluating an emergency and bringing the plant under control. The TSC is a coordinating center for gathering and initially evaluating information relative to accident conditions.

June 2016 GN 8-4 EP-AA-1012 (Revision

3) -

Ginna Annex NUREG-0654 Reference A1 -Item a . A1.-ltem b A1 -Item c A1 -Item d A1 -Item e A2-ltem a A2-Item b A3 A4 B1 B2 B3 B4 B5 B6 B7 B7-Item a B7-Item b B7-Item c B7-ltem d B8 'B9 June 2016 Appendix 1 NUREG-0654 Evaluation Criteria Cross Reference Criteria Identification of Response Organizations Organization of Concept of Operations Organizational Inter-Relationships

-Block Diagrams Designation of Organization Director 24 Hour Response/Communication Organization Authority Legal Basis for Organization Authority Formal lntra-governmenVOrganization Agreements Designated Authority for Organization Resource Continuity Provisio.n for Onsite Shift Emergency Organization Designation of Onsite Emergency Director Line of Succession for the Emergency Director Functional Responsibilities of the Emergency Director Assignment of On-Site Emergency Personnel Onsite Emergency Organization Interface

_ Designation of Minimum Staffing Requirements for Plant Emergencies Logistics Support for Emergency Personnel Technical Support for Planning/Re-entry/Recovery Operations Management Level Interface with Governmental Authorities Information/Pres$

Releases Designation/Responsibility/Limitations of Local Agency Assistance Exelon Nuclear Plan Reference Section No. 2.8 1.1, 1.2 Fig. 2.7 1.1, 2.2 5.2 N/A (not required in Licensee Plans) N/A (not required in Licensee Plans) Appendix 2 2.2 2.1, 2.2 2.2 2.3 3.5, 2.2, 2.4, 4.5.1, 4.8 2.1 thru 2.6, 6.0 2.2 thru 2.6, 5.1, 7.1 Table 2.1 2.7 2.5 2.5 4.11 2.9, 2.10 2.8, 2.10, Appendix 2 A1-1

• EP-AA-1012 (Revision

3)

Ginna Annex C1 -Item a C1 -Item b C1 -Item c C2-Item a C2-Item b C3 C4 01 02 03 04 E1 E2 E3 E4 ES E6 E7 Appendix 1 NUREG-0654 Evaluation Criteria Cross Reference Authority to Request RAP/IRAP Resources Federal Resources Expected and Time of Arrival Specify Support Available to Federal Response Organization Representative at Near-Site Emergency Operations Facility Licensee Representative at Governmental EOG Radiological Laboratory Capabilities Nuclear Assistance Sources Facility Emergency Classification System Initiating Conditions State and Local Emergency Classification System State and Local Procedures Bases for NotificationNerification Personnel Notification/

Alert/Mobilization Procedures Contents of Initial Plant Emergency Messages Provisions for Content of Plant Follow-up Messages Dissemination of Information from Plant Operators Means for Population Notification Provision for Written Public Instruction Messages Exelon Nuclear 2.2, 4.5, 5.2.5 2.8.4 2.8.4 N/A (not required in Licensee Plans, see State & County Plans) 4.8 2.10.9 2.8, 2.9, 2.10 3.0 N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) 3.0 4.3 4.7 4.8 N/A (not required in Licensee Plans, see State & County Plans) 5.3.13 4.5 F1 -Item a, b, 24-Hour Notification/Activation of Emergency Response 5.2.5 c, d, f Network F1 -Item e F2 F3 G1 June 2016 Alerting Ginna Emergency Personnel

4.6 Communications

with Medical Support Facilities 2.10 Periodic Communications System Testing 5.2 Public Emergency Education/Information 4.11 A 1-2 EP-AA-1012 (Revision

3)

Ginna Annex G2 G3 G4-ltem a G4-ltem b G4-ltem c GS H1 H2 H3 H4. HS Appendix 1 NUREG-0654 Evaluation Criteria Cross Reference Public Emergency Education Program Public Information Control Point Designated Public Information Spokesperson Timely Exchange Among Spokespersons Arrangements for Rumor Control News Media Education Program NUREG-0696 Technical

& On-site Operations Support Centers Near-Site Emergency Operations Facilities State & Local Emergency Operations Center Provision fpr Activation/Staffing of Facilities Onsite Monitoring Systems Exelon Nuclear 4.11 S.1.S 4.11 2.S.c.2 Figure 2.6 4.11 S.1.2, S.1.3 S.1.4, S.1 .s N/A (not required in Licensee Plans, see State & County Plans) 4.3 S.3.1 -S.3.8, S.3.10, S.3.14 H6-ltem

• a Off site Geophysical.

Phenomena Monitors S.3.8 H6-Item b H6-Item c H7 H8 H9 *H10 H11 H12 11 12 13-ltem a June 2016 Off-site Monitors/Dosimetry Laboratory Facilities Off-site Radiological Monitoring Equipment Provision for Meteorological Instrumentation/Procedures Provision for On-site Operations Support Center Inspection/Inventory/Calibration of Emergency Equipment/Instruments Categories of Emergency Equipment Centralized Point for Receipt and Analysis of All Field Monitoring Data Identification of Plant Condition Parameters and Corresponding Emergency Classes NUREG-OS78 Post-Accident Sampling and Monitoring Capabilities Methods/Techniques for Source Term Determination S.3.7, S.3.11 S.3.9 S.3.10, S.3.11 S.3.10 S.1.3 S.3.12, 6.3 S.1.7 S.3.9 3.0, 4.0 S.3.2, S.3.3, S.3.6, S.3.8, S.3.9 S.3.2 A1-3 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 1 NUREG-0654 Evaluation Criteria Cross Reference 13-ltem b Methods!Techniques to Determine Release Magnitude 5.3.3 14 Onsite/Offsite Exposures and Contamination for Various 5.3.3 Meteorological Conditions 15 Acquisition of Meteorological Information 5.3.10 16 Determination of Release Rate/Projected Doses Given 5.3.3 Inoperable Instrumentation 17 Capabilities for Field Monitoring within the Plume 5.3.11 Exposure EPZ 18 *Capability for Assessment of Actual/Potential Magnitude 4.6, 4.7, 4.8 and Location of Radiological Hazards 19 Capability to Detect Airborne Radioiodine Concentrations 5.3.11 as Low as 1 E-07 microcurie/cc 110 Estimation of Integrated Doses; Comparison With 4.5.1 Protective Action Guides NIA (not required 111 Arrangements to Locate and Track the Plume in Licensee Plans, see State & County Plans) J1 Capability to Warn Personnel 4.9.2, 5.2.1 J2 Offsite Sheltering/Evacuation of Onsite Personnel 4.9.2 J3 Radiological Monitoring of Personnel Evacuated from Site 4.9.1 J4 Onsite Non-Essential Personnel 4.9.2, 4.9.5 Evacuation/Decontamination at Offsite Facility J5 Accountability for Onsite Personnel 4.9.2 J6 Onsite Personnel Protection 4.9.3, 5.1.3 J7 Prompt Notification of Offsite Authorities for Protective 3.5.5.5 Actions JS Onsite Plan Contains Plume Exposure EPZ Evacuation EP-AA-1012, Time Estimates Addendum 2 Protective Action Guides (Personnei Exposure/Food NIA (not required J9 in Licensee Stuffs) Plans, see State & County Plans) Figures 4.2 & J10-Item a Maps of Evacuation Routes/Sectors Relocation Centers 5.2, EP-AA-1012, Addendum 2 June 2016 A1-4 EP-AA-1012 (Revision

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Ginna Annex J10-Item b J10-Item c J10-Item d

• J10-Item e J10-Item f J10 g J10-Item h J10-Item i J10-Item j J10-Item k

• J10-Item I J10-ltem m June 2016 Appendix 1 NUREG-0654 Evaluation Criteria Cross Reference Population Distribution by Sector/Zone Means of Notification of Transient/Resident Population Protection of Impaired Persons Radioprotective Drug Distribution Radioprotective Drug Administration Means of Relocation Relocation Centers 5 to 10 miles Beyond the EPZ Evacuation Routes/Traffic Capabilities Evacuated Area Access Control Evacuation Route Impediments/Contingency Measures Evacuation Time Estimates for EPZ Basis for Protective Actions used in EPZ during* Emergency Conditions Exelon Nuclear EP-AA-1012, Addendum 2 5.3.13 N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans)* N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) N/A (not required

• in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) EP-AA-1012, Addendum 2 Table 4.1 A1-5 EP-AA-1012 (Revision

3)

Ginna Annex J11 J12 K1 -Item a K1 -Item b K1 -Item c K1 -Item d K1 -Item e K1 -Item f K1 -Item g K2 K3 K4 K5 K6 K7 L1 L2 L3 L4 M1 June 2016 Exelon Nuclear Appendix 1

• NUREG-0654 Evaluation Criteria Cross Reference Protective Measures for the Ingestion Pathway Registration

& Monitoring of Evacuees Exposure Guidelines for the Removal of Injured Persons Exposure Guidelines for the Undertaking of Corrective Actions Exposure Guidelines for Performing Assessment Actions Exposure Guidelines for Providing First Aid Exposure Guidelines for Providing Personnel Decontamination Exposure Guidelines for Providing Ambulance Service Exposure Guidelines.for Providing Medical Treatment Services Onsite Radiation Protection Program 24-Hour Dosimetry Service Authorization for Personnel Exposure in Excess of the Protective Action Guides Determination of Need for Decontamination Onsite Controls Capability for Decontamination of Relocated Onsite Personnel Ability of Medical/Health Services to Evaluate Radiation Exposure/Handle Contaminated Individuals Onsite First Aid Capability Identification of Medical Services Facilities Equipped/Trained to Treat Radiological Accident Victfms Transportation to Medical Facilities Plans for Recovery/De-escalation of Protective Measures N/A (not required in Licensee Plans, see State & County Plans) N/A (not required in Licensee Plans, see State & County Plans) 4.9.1 . 4.9.1 4.9.1 4.9.1 4.9.5 4.9.1 4.9.1 4.9.1 4.9.1 N/A (not required in Licensee Plans, see State . & County Plans) 4.9.5 5.4.5 4.9.5 2.10.2, 2.10.4-2.10. 7, 5.5 4.9.3 N/A (not required in Licensee Plans, see State & County Plans) 2.10.2 7.0, 7.1 A1-6 EP-AA-1012 (Revision

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Ginna Annex M2 M3 M4 N1 -Item a N1 -Item b N2-Item a N2-Item b N2-Item c N2-Item d N2-Item e N3 N4 NS 01 -Item a 01 -Item b 02 03 04 OS P1 P2 P3 P4 PS P6 P7 P8 June 2016 Appendix 1 NUREG-0654 Evaluation Criteria Cross Reference Designation of Facility Recovery Organization Notification of Recovery Operation Initiation Methodology for Periodic Exposure Estimate Drills to Simulate Offsite Releases Drills to Test All Elements, Time, & Weather Conditions Communication Drills Fire Drills Medical Emergency Drills Radiological Monitoring Drills Health Physics Drill Drill Scenarios Official Observers/Critique I mprovemertts/Corrective Actions Onsite Emergency Response Training for Offsite Emergency Organizations Offsite Emergency Response Organization Training Onsite Training/Corrective Actions Onsite First Aid Team Training Response Personnel Training Annual Retraining of Personnel Planning Personnel Training Designation of Planning Authority_

Designation of Emergency Planning Coordinator Annual Review and Update of Response Plan Provisions for Plan Distribution and Promulgation of Plan Revisions Listing of Supporting Plans Procedures for Plan Implementation Table of Contents Exelon Nuclear 7.1 7.1 S.3.3 6.1.4 6.1.4 6.1.4, 6.2 6.1.4 2.10.2, 2.10.4, 2.10.S 6.1.4 6.1.4 6.1.4 p.1.4 6.1.4 6.1.3 N/A (not required in Licensee Plans, see State & County Plans) 6.1 4.9.3 6.1 6.1 6.1.S 1.1 1.1 6.2 6.2 Appendix S Ap.pendix 3 Page 1 A1-7 EP-AA-1012 (Revision

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Ginna Annex pg' P10 June 2016 Exelon Nuclear Appendix 1 NUREG-0654 Evaluation Criteria Cross Reference Independent Audit of Emergency Preparedness Program

6.4 Updating

of Telephone Numbers 6.2 A1-8 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Appendix 2 Letters of Agreement The up-to-date Letters of Agreement are maintained in accordance with Ginna document control procedures and are considered to be incorporated as part of this document by reference.

• Agency/Company New York State Office of Emergency Management Ontario Volunteer Emergency Squad Rochester Regional Health System Ontario Fire Company DOE/REAC!TS Wayne County Board of Supervisors U.S. Department of Commerce, National Weather Service Agreement between James A. Fitzpatrick Nuclear Power Plant, Nine Mile Point Nuclear Power Station and the R. E. Ginna Station Wayne County Sheriff's Office New York State Police County of Monroe Institute of Nuclear Power Operations Letter of Agreement between Exelon (Ginna Station), Wayne County Emergency Management Office, Monroe County Office of Emergency Management, and New York Office of Emergency Management (re. Offsite Survey Teams) Memorandum of Understanding for Offsite Staging Area June 2016 A2-1 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Appendix 3 Emergency Plan Implementing Procedures Emergenc:l£ Plan E Plan Reference EPIP# Procedures lEPIPl A-7 Procedures for Handling 2.11, 5.5 Injuries/Medical Emergencies at Ginna Station EP-CE-113 Personnel Protective Actions 4.4, 4.5.1, 5.2.1, 5.3, 5.4 4.9.1, 4.9.3 EP-AA-112-500-F-54 GNP Offsite Monitoring Team 5.3.3, 5.3.11 Guidance EP-CE-111 Emergency Classification and 4.5.1 Protective Action Recommendations EP-CE-114-100 Emergency Notifications 1.3, 3.0, 3.2, 3.3, 4.2-4.5, 5.2.4, 5.2.5, Public Information Organization 2.1thru2.7, 4.11, . 5.1, 5.1.5, EP-AA-112-400 Em*ergency 012erations Facility 2.1 thru 2.7, 5.1, Activation and 012erations 5.1.4, 5.2.5 EP-AA-112-100 Control Room 012erations 2.1thru2.7, 5.1, 5.1.1, 5.2.5 EP-AA-112-200 TSC Activation and 012erations 2.1 thru 2.7, 5.1, 5.1.2, EP-AA-112-300 012erations Su1212ort Center 2.1 thru 2.7, Activation and 012erations 5.1, 5.1.3, EP-CE-115 Termination and Recove!Y 7.0 EP-AA-110-203 GNP Dose Assessment 4.6, 5.3.3, 5.3.11, June 2016 A3-1 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Appendix 3 Emergency Plan Implementing Procedures Plan E Plan Reference EPIP# Procedures CEPIP) EPIP-1-13 Local Radiation Emergency 3.1, 4.1, EPIP-1-16 Radioactive Liguid Release to Lake 4.7, 4.10, Ontario or Deer Creek EPIP-1-17 Planning for Adverse Weather 4.5.1, 5.3.10 EPIP-1-18 Discretionary Actions for Emergency

1.3 Conditions

EPIP-2-16 Core Damage Estimation 5.3 EPIP-4-11 Activation of the Ginna Sirens from 5.3.13 the County Activation Points ' EPIP-4-9 Activation of Ginna Emergency*

5.3.13.1 Sirens from the Technical Suggort Center SY-AA-101-121 Security Resgonse to the Station 1.3, 3.3, 4.3 Emergency Plan ER-SEC.1 Resgonse to Change in Security 1 .3, 3.3, 4.3 Threat Level ER-SEC.2 Resgonse to Intrusion by Adversary 1.3, 3.3, 4.3 ER-SEC.3 Resgonse to Airborne Threat 1.3, 3.3, 4.3 June 2016 A3-2 EP-AA-1012 (Revision

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Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities Note: The positions and responsibilities described in this Appendix apply to Ginna station and supersede the list of ERO positions and respective ERO responsibilities identified in the Exelon Standard Plan. 1.0 On-Shift Staff Positional Responsibilities The emergency plan responsibilities for shift personnel are: 1 .1 Shift Emergency Director I Shift Manager: NOTE:

• Indicates Non-Delegable responsibilities when performing Emergency Director duties.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Perform or direct emergency PA announcements.

• Ensure flow of information within and between the emergency response facilities.

• Integrate ERO activities with the Incident Command Post (ICP) response activities.

• Assume overall command and control of emergency response.

• Classify and declare emergencies.*

• Direct notification and activation of the ERO.

• Direct and approve offsite emergency notifications to state and local authorities*.

• Direct ENS communications with the NRG.

• Oversee the performance and evaluate the results of dose projection activities.

• Ensure appropriate accountability and search and rescue actions for plant personnel.

• Ensure appropriate evacuation actions for plant personnel*.

• Approve the issuance of Kl.

• Make Protective Action Recommendations to offsite authorities*.

• Approve emergency exposures.*

• Terminate the emergency event. 1 .2 Shift Manager (After Transfer of Command and Control)

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Perform or direct emergency PA announcements.

• Ensure flow of information within and between the emergency response facilities.

June 2016 A4-1 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• Participate in Inter-Facility Briefings to communicate and obtain event and response information.

• Authorize and prioritize requests for external assistance (police, fire, medical) as necessary.

• Assist with Emergency Classification.

1.3 Shift

Technical Advisor (STA), SROs and ROs

• Assist with emergency classification.

1.4 Designated

Shift Communicator

• Notify the ERO.

• Perform offsite emergency notifications to state and local authorities.

• *Provide plant data and plant information to the NRC via the* ENS. 1 .5 Designated Shift Dose Assessor

• Perform dose assessments.

1.6 Shift

Radiation Protection Technician(s)

• Provide radiation protection for shift personnel

• Conduct surveys and radiological monitoring to assist with emergency assessment activities.

1.7 *Shift Chemistry Technician

• Perform dose assessment

• Conduct sampling to assist with emergency assessment activities.

1.8

• Security Shift Supervisor

• Supervise security 'force activities.

• Notify the ERO.

• Perform offsite emergency notifications to state and local authorities.

• Establish and maintain Protected Area accountability.

• Direct security actions for offsite assembly.

• Establish and supervise plant access controls.

• Supervise security actions for site evacuation.

• Coordinate administration of Kl to the security officers.

1.9 Other

Shift Personnel (Non-licensed Operators, Security Force, Maintenance Personnel)

• Support emergency response as directed.

June 2016 A4-2 EP-:-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• 2.0 Technical Support Center CTSC): 2.1 Station Emergency Director

• Manage all onsite emergency activities in support of plant operations.

• Establish plant/station response priorities.

• Integrate ERO activities with the Incident Command Post (ICP) response activities.

-* Authorize and prioritize requests for external assistance (onsite technical support, manpower) as necessary.

• Assist with emergency classification.

• Provide informational updates and recommendations to the ED, regarding plant status and activities'.

• Direct ENS communications with the NRC.

• Authorize emergency response facility relocations.

• Evaluate event assessments and mitigative strategies to determine Operations and response actions. * . Authorize anq direct extreme measures (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Ensure appropriate accountability and search and rescue actions for plant personnel.

• Ensure accountability, once established, is maintained in all occupied areas of the station.

• Ensure appropriate evacuation actions for plant personnel.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility briefing to communicat,e and obtain event and response information.

• Coordinate integration of the NRC Site Team

• Assist in the development of recovery plans. 2.2 TSC Director

• Activate the Facility . .

• Establish and maintain facility accountability.

• Manage the operation of the facility.

• Review and ensure facility displays are maintained current.

• Coordinate ERO shift relief rosters for the onsite facilities.

• Develop ERO shift relief rosters for the facility.

• Perform or direct emergency PA announcements.

• Coordinate integration of the NRC Site June 2016

• A4-3 EP-AA-1012 (Revision 3).

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• Arrange for logistics support.

• Ensure flow of information within and between the emergency response facilities.

• Provide input for facility briefs and updates.

• Coordinate TSC relocation.

2.3 Technical

Manager

• Manage the activities of the TSC engineering I technical staff.

• Ensure additional personnel and/or equipment is arranged for, as necessary.

• Provide engineering support for accident detection and assessment.

• Develop mitigative strategies based on assessment of the event.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Provide input for facility briefs and updates. 2.4 Electrical Engineer

• Provide engineering support for accident detection and assessment.

• Provide input into mitigative strategies.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

2.5 Mechanical

Engineer

• Provide engineering support for accident detection and assessment.

• Provide input into mitigative strategies.

• Analyze and develop measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

2.6 Core I Thermal Hydraulic Engineer

• Provide engineering support for accident detection and assessment.

• Provide input into mitigative strategies.

• Perform core damage estimations.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

2. 7 TSC/OSC Computer Specialist

• Support the setup of systems and equipment within the facility.

• Monitor facility equipment (computer related and communications) to ensure adequate operation.

• Resolve any IT related malfunctions.

2.8 Operations

Manager

• Manage the activities of the TSC Operations staff.

• Assist with emergency classification.

• Provide technical assistance communication path to the Shift Manager. June 2016 A4-4 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• Support the establishment of plant/station response priorities.

• Provide operations support for accident detection and assessment.

• Recommend operations actions to the Shift Emergency Director in support of restoration and accident mitigation.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Coordinate operations activities outside of the Control Room between the Shift Emergency Director and OSC.

• Provide input for facility briefs and* updates. 2.9 ENS Communicator

• Provide event data and plant information to the NRC via the ENS.

• Verify EROS operation.

• Monitor assigned communication line and provide key information to facility staff.

• Monitor event information on the facility display systems. 2.10 Ops Communicator (TSC)

• Communicate key information between the facilities over the Technical Information Line.

• Monitor assigned communication line and provide key information to facility staff.

• Display, monitor and trend plant data and event information on the facility display systems. 2.11 Ops Communicator (CR)

• Communicate key information between the facilities over the Technical Information Line.

• Monitor assigned communication line and. provide key information to facility *staff. 2.12 Maintenance Manager

• Provide input into mitigative strategies.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Coordinate repair and OSC team task information between the TSC and OSC.

• Provide input for facility briefs and updates. 2.13 TSC Radiation Protection Manager

• Manage and direct the radiological activities of the RP personnel.

• Ensure additional personnel and/or equipment is arranged for, as necessary.

• Provide radiological support for accident detection and assessment.

June 2016 A4-5 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• Monitor, evaluate and communicate conditions involving any release of radioactivity.

• Provide support and logistics for site evacuation activities.

• Evaluate the need for and ensure proper use of Kl.

• Ensure habitability is established and maintained for occupied orisite areas.

• Ensure proper emergency exposure controls are taken for personnel.

• Provide radiological assistance for planning rescue operations and repair team monitoring.

• Direct personnel decontamination activities.

• Provide radiological assistance for the transfer of injured and/or contaminated personnel.

• Provide input for facility briefs and updates. 2.14 Security Coordinator

• Integrate ERO activities with the ICP response activities.

• Manage the activities of the site security force.

• Request and coordinate emergency activities . with Local Law Enforcement Agencies (LLEAs).

• Provide security related cpmmunications with the NRC.

• Direct accountability and search & rescue activities.

• Direct site evacuation activities.

• Direct site access controls activities.

• Coordinate security activities between the SSS and OSC.

• Determine radiation protection measures for security force personnel and law enforcement agency personnel on site.

• Provide input for facility briefs and updates. 2.15 TSC Administrative Staff

• Perform administrative and logistic support functions for facility personnel.

• Establish and maintain facility accountability.

3.0 Operations

Support Center (OSC): 3.1 OSC Director

• Activate the Facility.

• Manage the operation of the facility.

• Develop ERO shift relief rosters for the facility.

• Ensure flow of information Within and between the emergency response facilities.

• Support the establishment of plant I station response priorities.

June 2016 A4-6 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• Direct accountability and search & rescue activities.

• Establish and maintain facility accountability.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Coordinate OSC team dispatch and control.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility Briefing to communicate and obtain event and response information.

3.2 Assistant

OSC Director

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Participate with OSC team dispatch and control.

• Assemble and dispatch OSC and offsite monitoring teams.

• Provide input for facility briefs and updates. 3.3 OSC Craft, Chemistry and Operations Group Leads

• Manage OSC manpower needs.

• Assist with formation of OSC teams.

• Participate with OSC team dispatch and control.

• Provide technical support to dispatched OSC teams. 3.4 OSC Craft, Chemistry and Operations Personnel

• Perform job duties as an OSC team member. 3.5 OSC Radiation Protection (RP) Group Lead

• Manage OSC manpower needs.

• Monitor in-plant radiological conditions.

• Ensure habitability is established and maintained for occupied onsite areas.

• Participate with OSC team dispatch and control.

• Coordinate RP support for OSC teams.

• Track OSC Team emergency exposure.

• Implement appropriate protective measures for OSC personnel.

• Establish OSC and plant access radiological controls.

• Provide input for facility briefs and updates. 3.6 OSC Radiation Protection Technicians(s)

• Perform habitability monitoring in occupied areas.

• Perform job duties as an OSC team member. June 2016 A4-7 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities 3.7 OSC Team Tracker

• Maintain Team Tracking Status display.

• Participate with OSC team dispatch, control and tracking.

• Track and maintain communications with o*sc teams. 3.8 Operations Communicator

-OSC

• Communicate key information between the facilities over the Technical Information Line.

• Monitor the Technical Information Line and announce key information to facility staff.

• Display, monitor and trend plant data and event information on the facility

• display systems. 3.9 OSC Administrative Staff

• Perform administrative and logistic support functions for facility 4.0 Offsite ERO: Emergency Operations Facility 4.1 Corporate Emergency Director *

• Assume overall command arid control of emergency response.

• Ensure all Exelon emergency response facilities are properly staffed and activated.

• Classify emergencies.

• Direct and approve offsite emergency notifications to state and local authorities.

• Make Protective Action Recommendations to offsite authorities.

• Direct ENS communications with the NRG.

• Ensure appropriate evacuation actions for plant personnel.

• Approve the issuance of Kl.

• Approve emergency exposures.

• Integrate ERO activities with the ICP response activities.

• Authorize and prioritize requests for external assistance (governmental) as necessary.

• Authorize and prioritize requests for external assistance (offsite technical .support, manpower) as necessary.

• Ensure other organization's management/decision makers (NRG, State, Exelon, etc.) are kept informed of the emergency situation.

June 2016 A4-8 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix4 Emergency

Response Organization Responsibilities

• Ensure flow of information within and between the emergency response facilities.

• Approve technical content of media statements.

• Coordinate integration of the NRC site team.

• Authorize and direct extreme measures (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Terminate the emergency event.

• Establish a recovery plan and organization.

• Conduct facility briefs and updates.

• Conduct an Inter-Facility briefing to communicate and obtain* event and response information.

4.2 EOF Director

• Activate the Facility.

• Manage the operation of the facility.

• Assist offsite agency personnel responding to the facility.

• Coordinate integration of the NRC site team. *

• Assist with emergency classification.

• Support the completion of timely offsite event notifications to State and local authorities.

• . Evaluate conditions and determine recommendations for PARs.

• Assist in the development of recovery plans.

• Participate in the Inter-Facility briefing to communicate and obtain event and response information.

• Provide input for facility briefs and updates. 4.3 EOF Technical Advisor

• Assist with emergency classification.

• Monitor plant status and Control Room activities.

• Provide input for facility briefs and updates. 4.4 Ops Communicator

-EOF

• Communicate key information between the facilities over the Technical Information Line.

• Monitor assigned communication line and provide key information to facility staff. June 2016 A4-9 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• Display, monitor and trend plant data and event information on the facility display systems. 4.5 EOF Logistics Manager

• Ensure ERO personnel have been properly notified and are responding to the facilities.

• Oversee staffing of EOF and assist with staffing for other facilities.

• Develop ERO shift relief rosters for the facility.

• Coordinate ERO shift relief rosters for all facilities and the notification of personnel.

• Manage the administrative support staff.

• Review and ensure facility displays are maintained current.

• Manage the procurement and logistical support activities for the onsite and offsite emergency response personnel and facilities.

• Monitor and maintain access controls for the facility.

• Communicate with and coordinate support for ERO responders or plant personnel sent offsite to relocation areas.

• Provide input for facility briefs and updates 4.6 EOF/JIC Computer Specialist

• Support the setup of systems and equipment within the facility.

• Monitor facility equipment (computer related and communications) to ensure adequate operation.

• Resolve any IT related malfunctions.

• Assist in operation of JIC audio visual equipment.

4.7 EOF Administrative Staff

• Callout ERO relief shift.

• Set up EOF equipment in preparation for facility activation.

• Perform administrative and logistic support functions for facility personnel.

4.8 EOC Communicator

• Monitor plant conditions and event response activities.

• Provide information updates to and address questions and support requests from the offsite liaisons.

• Notify and brief external agencies and groups (INPO, ANI) of the emergency event.

• Provide input for facility briefs and updates. June 2016 A4-10 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

4.9 State

Liaison

• Communicate EOC I ICP actions and decisions to the EOF.

• Provide technical support and information to the EOC I ICP. 4.10 County Liaison(s)

• Communicate EOC I ICP actions and decisions to the EOF.

• Provide technical support and information to the EOC I ICP. 4.11 EOF Radiation Protection Manager

• Manage and direct the radiological activities of the RP personnel.

• Coordinate activities with the external agency field monitoring teams.

• Coordinate the comparison and exchange of dose assessment results with offsite agency personnel.

• Assist with emergency classification.

• Monitor, evaluate and communicate conditions involving any release of radioactivity.

• Oversee the performance and evaluate the results of dose projection activities.

• Perform dose assessment.

• Oversee the performance and evaluate the results of OMT activities.

• Provide support and logistics for site evacuation activities.

• Evaluate the need for and ensure proper use of Kl.

• Evaluate conditions and determine recommendations for PARs.

• Ensure proper emergency exposure controls are taken for personnel.

• Provide assistance to state and federal agencies for ingestion pathway radiological activities.

• Provide input for facility briefs and updates. 4.12 HPN Communicator

• Provide event data and plant information to the NRC via the HPN.

• Monitor assigned communication line and provide key information to facility staff. June 2016 A4-11 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities 4.13 Dose Assessor

• Monitor, evaluate and communicate conditions involving any release of radioactivity.

• Perform dose assessment.

• Evaluate conditions and determine recommendations for PARs. 4.14 Environmental Coordinator

• Direct and track Offsite Monitoring Team activities.

• Coordinate activities with the external agency field monitoring teams.

• Establish and maintain OMT communications.

• Maintain and update the radiological status displays.

-* Coordinate the receipt, analysis, storage and transfer of field monitoring samples.

• Record and report field monitoring survey, sample and exposure information.

4.15 Offsite Monitoring Teams

• Establish and maintain OMT communications.

• Perform equipment checks and inventories in preparation of deployment.

• Track radiological plumes.

• Perform and report results of radiation surveys and environmental sampling.

• Coordinate the receipt, analysis, storage and transfer of field monitoring samples.

• Communicate exposure status to the Environmental Coordinator.

4.16 State/Local Communicator

• Perform offsite emergency notifications to state and local authorities.

5.0 Public

Information ERO (JIC Staff) 5.1 JIC Manager

• Activate the Facility.

• Manage the operation of the facility.

• Assist offsite agency personnel responding to the facility.

• Coordinate integration of the NRC Site Team.

• Provide liaison to the NRC Site Team.

• Arrange for support for Emergency Alert System (EAS) information.

June 2016 A4-12 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• Ensure flow of information within and between the emergency response facilities.

• Interface with offsite agency Public Information Officers (PIOs) to coordinate overall information flow to the media and public.

• Coordinate facilitation of the media briefing schedule.

• Ensure news media briefings are held regularly during the course of the emergency.

• Oversee conduct of media briefings.

-* Integrate ERO activities with the Incident Command Post (ICP) response activities

• Assist in the development of recovery plans.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility Briefing to communicate and o_btain event and response information.

5.2 Company

Spokesperson

• Establish periodic contact with the communications personnel in the corporate office.

• Interface with offsite agency PIOs to coordinate overall information flow to the media and public.

• Provide interviews to the media.

• Serve as Company Spokesperson during press conferences at the JIC.

• Participate in the Inter-Facility Briefing to communicate and obtain event and response information.

• Provide input for facility briefs and updates. 5.3 JIC Logistics Manager

• Manage the administrative support staff.

• Develop ERO shift relief rosters for the facility.

• Arrange for logistics support.

• O_versee set .. up and testing of _JIG equipment.

• Maintain access control to the JIC. -* Provide input for facility briefs and updates.

• Oversee collection of technical data and station activities for drafting Media Statements and answering JIC questions.

• Coordinate preparation, review and distribution of Media Statements.

June 2016 A4-13 EP-AA-1012 (Revision

.3)

Ginna Annex Exelon Nuclear Appendix 4 Emergency Response Organization Responsibilities

• Obtain ED approval for the technical content of Media Statements.

• Keep JIC staff informed of plant status and Exelon emergency response activities.

5.4 News Writer

• Prepare draft Media Statements.

• Develop public information materials (bulletins, backgrounders and chronologies).

5.5 JIC Technical Advisor

• Provide technical expertise to the JIC staff.

• Assist the News Writer with development of technically accurate media statements.

• Provide answers to technical questions from the news media regarding the emergency situation.

• Periodically monitor EOF/TSC briefings and Technical Information Line to obtain information.

• Provide technical information support to the Company Spokesperson.

• Monitor event information on the facility display systems.

• Provide input for facility briefs and updates. 5.6 Media Liaison

• Ensures media is informed of protocol and schedules established for media briefings.

• Coordinate preparations for media briefings.

• Distribute media statements to the media in the media briefing area.

• Coordinate media relations in JIC and update media between press conferences.

• Coordinate special interviews and facility tours for the media.

• Coordinate JIC briefing area preparation and establish briefing protocol.

5.7 JIC Administrative Staff

• Assist in badging and direction of members of the media to proper work locations.

• Perform administrative and logistic support functions for facility personnel.

• Distribute media materials to the press. June 2016 A4-14 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix4 Emergency Response Organization Responsibilities

5.8 Media

Monitoring I Rumor Control Coordinator

• Supervise media monitoring and Inquiry Phone Team personnel.

• Review Media Monitoring team information for trends, misinformation and rumors.

• Review Phone Team information tor trends, misinformation and rumors.

• Ensure adequate staff is available to perform media monitoring and phone team functions.

• Provide input tor facility briefs and updates. 5.9 Inquiry Phone Team

• Respond to and log phone inquiries from the media and the public.

• Monitor telephone lines tor trends, misinformation and rumors. 5.1 O Media Monitoring Team

• Monitor media coverage of the event tor trends 5.11 JIC Security

• Provide badging and access: controls tor the facility.

6.0 In addition to the position specific responsibilities listed above all ERO members have the following general responsibilities:

• Perform position turnover tor protracted events

• Respond as directed when notified of a declared event

• Maintain personal event logs and records in support of the after action report

• Restore area and materials upon event termination

• Apply fundamental ERO knowledge in the performance of your ERO duties

• Properly use ERO procedures and checklists in the performance of your ERO duties

• Acquire & maintain qualification in your assigned ERO position

• Apply human performance error reduction techniques in the performance of your ERO duties. June 2016 A4-15 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 5 SUMMARIES OF INTERFACING EMERGENCY PLANS 1. New York State Radiological Emergency Preparedness Plan: The purpose of the NYS Plan is to minimize the risk to the health of the inhabitants of the State in the event of a radiological emergency.

This will be accomplished by identifying measures to prevent and mitigate such an emergency; by developing mechanisms to coordinate Federal, State, local and private sector resources, during and after such an emergency; and by providing for recovery following a radiological emergency.

The New York State Department of Health is the state agency having primary responsibility in this area. The New York State Public Health Law gives the Commissioner of Health broad authority for protecting the health and life of the people of New York State, including protection against ionizing radiation.

The State Sanitary Code, Part 16, which implements the Public Health Law, includes requirements relating to accidents, emergencies; or incidents.

Article 2-B of the New York State Executive Law (State and Local Natural and Manmade Disaster Preparedness) created a State Disaster Preparedness Commission.

This Commission is charged with a wide variety of power and responsibilities, designed to provide a comprehensive emergency system to prevent or react to emergencies or disasters within the State. Among these responsibilities are: (1) to develop and maintain a State plan and to assist local government in developing such plans; (2) to direct State disaster operations and

• coordinate State operations with local disaster operations; (3) to coordinate recovery operations and recovery as*sistance; and (4) to provide training to assure th.at responsible personnel are familiar with plans and procedures.

Where, by tradition, emergency plans have been primarily concerned with response activities, New York State has adopted an overall emergency.

preparedness system which includes two interrelated critical phases. (1) Preventive/Mitigation:

This is the initial phase of activities that is aimed at eliminating or reducing the probability of the occurrence of a radiological emergency, and at minimizing the impact of a radiological

• emergency on public healt.h and property.

These activities include the development of new legislation and the development of preparedness plans and training programs.

Prevention/mitigation activities form a basis for enhancing the quality of response operations.

(2) Response:

June 2016 The response phase follows the identification or notification of an emergency.

Generally, response activities are planned to minimize the adverse impact on public health and to protect property, to the extent possible, through emergency assistance.

These activities include accident A5-1 EP-AA-1012 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 5 SUMMARIES OF INTERFACING EMERGENCY PLANS assessment and evaluation and radiological exposure control. They also reduce the probability of secondary damage and speed recovery operations.

2. Wayne County Radiological Emergency Response Plan (CRERP): When considering radiological emergencies, preparedness, response, and recovery are general responsibilities which are shared by all levels of government and the nuclear facility operators.

These emergencies will be dealt with at the local or county level until such time that the county's resources have been exhausted.

At this point, in addition to technical guidance and evaluation, the county will request state assistance through the New York State Emergency Management Office (SEMO). The mission of the County Emergency Response Organization and the County Radiological Emergency Response Plan (CRERP) is to protect the health and safety of the general public of Wayne County in the unlikely event of a

• radio.logical release incident at the Ginna Nuclear Power Plant. , In order to successfully execute this mission it will be necessary to perform the following operations: 1 . Monitor and assess the scope and magnitude of the incident;

2. Evaluate and decide which protective action response options should be initiated;

3. Implement the appropriate protective action response option (or combination of options, if necessary.)

The successful implementation of-the CRERP will depend on the efficient and effective coordination with

• other emergency response organizations.

Specifically, the CRERP will be closely coordinated with the RERP of Monroe County; the New York State Radiological Emergency Plan; and the Ginna Station Nuclear Emergency Response Plan.

• 3. Monroe County Radiological Emergency Preparedness Response Plan (CRERP): When considering.

radiological emergencies, preparedness, response, and recovery are general responsibilities which are shared by all levels of government and the nuclear facility operators.

These emergencies will be dealt with at the local or county level until such time that the county's resources have been exhausted.

At this point, in addition to technical guidance and evaluation, *the county will request state assistance through the New York State Emergency Management Office (SEMO). The mission of the County Emergency Response Organization and the County Radiological Emergency Plan is to protect the health and safety of the general public of Monroe County in the unlikely event of a radiological release incident at

• the Ginna Nuclear Power Plant. June 2016 AS-2 (Revision

3)

Ginna Annex Exelon Nuclear Appendix 5 SUMMARIES OF INTERFACING EMERGENCY PLANS In order to successfully execute this mission it will be necessary to perform the following operations:

1. Monitor and assess the scope and magnitude of the incident;

2. Evaluate and decide which protective action response options should be initiated;

3. Implement the appropriate protective action response option (or combination of options, if necessary.)

In addition to these operations, the successful implementation of the CRERP will depend on the efficient and effective coordination with other emergency response organizations.

Specifically, the CRERP will be closely coordinated with the RERP of Wayne County; the New York State Radiological Emergency Plan; and the Ginna Station Nuclear Emergency Response Plan. 4. Management of Radiologically Contaminated Patient at Rochester General Hospital The purpose of this plan is to describe the response of Rochester General Hospital (RGH) to an injured and radioactively contaminated patient. The procedure will describe the responsibilities of the hospital staff, the set-up of the

• Radiation Decontamination Center (RDC), notification protocols, equipment and supplies, decontamination and contamination control techniques.

RGH is a support hospital for the Ginna plant a*nd has agreed to provide medical care to patient(s) who injuries and who may be contaminated and/or overexposed to ionizing radiation.

5. Management of Radiologically Contaminated Patient at Newark-Wayne Community Hospital The. purpose of this plan is to describe the response of" Newark-Wayne Community Hospital (NWCH) to an injured and radioactively contaminated patient. The procedure will describe the responsibilities of the hospital the set-up of the Radiation Emergency Area, notification protocols, equipment and supplies, decontamination and contamination control tec.hniques.

NWCH is a support hospital for the Ginna plant and has agreed to provide medical care to patient(s).who sustained injuries and who may be contaminated and/or overexposed to ionizing radiation.

June 2016 A5-3 EP-AA-1012 (Revision

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ATTACHMENT 4 EP-AA-1013, Revision 2, "Exelon Nuclear Radiological Emergency Plan Annex for Nine Mile Point Station" Emergency Plan Annex Revision

<<'i ad ;t?

EXELON NUCLEAR EP-AA-1013 Revision 2 RADIOLOGICAL EMERGENCY PLAN ANNEX FOR NINE MILE POINT STATION Nine Mile Point Annex Exelon Nuclear TABLE OF CONTENTS Section Section 1: lntroduction

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

1-1 1.1 Purpose ................................................................................................

1-1 1.2 Emergency Organization

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

1-1 Section 2: Organizational Control of Emergencies

................................................... , .. 2-1

• 2.1 Typical Nuclear Division I Station Organization

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

2-1 2.2 On-Shift Emergency Response Organization Assignments

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

2-2 2.3 Authority Over the Emergency Response Organization

.. : ....................

2-4 2.4 Criteria for Assuming Command and Control (Succession)

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

2-4 2.5 Non-Delegable Responsibilities

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

2-4 2.6 Emergency Hesponse Organization Positional Responsibilities

..........

2-5 2. 7 Emergency Response Organization Block Diagram ..........................

2-18 2.8 Corporate Emergency Response Organization

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

2-18 2.9 Industry/Private Support Organizations

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

2-18 2.10 Supplemental Emergency Assistance to the ERO .............................

2-20 2.11 Coordination with Participating Government Agencies .................*....

2-20 Figure 2.1 Minimum Staffing Requirements for the ERO ............................

2-23 Figure 2.2 ERO Management Structure

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

2-27 Figure 2.3 TSC Staffing ...............................................................................

2-28 Figure 2.4 OSC Staffing ...............................................................................

2-29 Figure 2.5 EOF Staffing .............................................................................

2-31 Figure 2.6 JIC Staffing ..............................................................................

2-31 . Section 3: Emergency Conditions

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3-1 3.1 Classification System ........................................................................... 1 3.2 Spectrum of Postulated Accidents

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

3-3 Figure 3.1 Required Actions and Participation by Response Organizations for Various Emergency Classes ...................................................

3-4 Section 4: Emergency Measures ...... .........................................................................

4-1 4.1

• Initiation of Emergency Actions ............................................................

4-1 4.2 4.3 4.4 June 2016 Activation of Emergency Organization

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

4-2 Assessment Actions .............................................................................

4-4 Assessment Capabilities

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

4-7 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 4.5 Dose Assessment Methods and Techniques

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

4-8 4.6 Corrective Actions ..............................................................................

4-11 4.7 Protective Actions ..............................................................................

4-11 4.8 Aid to Affected Personnel

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

4-18 4.9 Emergency Public Information and Rumor Control ............................

4-19 Figure 4.1 Activation of Emergency Organization-Summary of Notification and Response .........................................................

4-20 Figure 4.2 Emergency Organization Interfaces (Initial Notification)

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

4-24 Figure 4.3 Emergency Organization Interfaces (After ER F's Staffed) .........

4-25 Section 5: Emergency Facilities and Equipment

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

5-1 5.1 Emergency Response .Facilities

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

5-1 5.2 Communications Systems ....................................................................

5-4 5.3 Assessment Facilities and Systems .....................................................

5-6 5.4 Protective Facilities

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

5-11 5.5 On-Site First Aid and Medical Facilities

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

5-13 5.6 Decontamination Facilities for Emergency Personnel

... _ .....................

5-13 5.7 Damage Control Equipment

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

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

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

5-14 5.8 Emergency Vehicles ............................................................. .... -........ 5-14 Section 6: Maintaining Emergency Preparedness

... : ................

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

6-1 6.1 Organizational Preparedness

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

6*1 6.2 Reviewing and Updating of Plans and Procedures

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

6-6 6.3 Maintenance and Inventory of Emergency Equipment and Supplies ... 6-7 6.4 Public Education and Information

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

6-8 Figure 6.1 Emergency Preparedness Department

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

6-9 Figure 6.2 Initial Training and Periodic Retraining

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

6-1 O Section 7: Recovery ................................................................................................

_ .... 7-1 7.1 Progression from Emergency Response to Recovery ..........................

7-1 7.2 Recovery Operations

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

7-2 7 .3 Emergency Organization Transformations

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

7-3 7.4 Recovery Organization

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7-3 Figure 7.1 Emergency Response/Recovery Organization

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7-7 June 2016 ii EP-AA-1013 (Revision

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Nine Mile Point Annex . Exelon Nuclear Section 8: Acronyms and Definitions

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

8-1 8.1 Acronyms .............................................................................................

8-1 8.2 Definitions

............................................................................. , ..............

8-3 APPENDICES

-,. 1. 2. 3. 4. 5. 6. 7. 8. NUREG-0654/FEMA-REP-1 Cross Reference index Letters of Agreement Emergency Plan Implementing Procedures Emergency Response Organization Responsibilities Oswego County Radiological Emergency Response Plan and New York State Radiological Emergency Response Plan Typical Additional Support Resources Resource Material Emergency Plan Commitments ADDENDUMS Addendum 1, Nine Mile Point Station On-Shift Staffing Analysis Report Addendum 2, Evacuation Time Estimates for the James A. Fitzpatrick/Nine Mile Point. Emergency Planning Zone Addendum 3, Unit 1 Emergency Action Levels for Nine Mile Point Station Addendum 4, Unit 2 Emergency Action Levels for Nine Mile Point Station June 2016 iii EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear REVISION HISTORY Revision O; February 2015 Revision 1; February 2016 Revision 2; June 2016 June 2016 iv EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear Section 1 : Introduction As required in the conditions set forth by the Nuclear Regulatory Commission (NRC) for the operating licenses for the Exelon Nuclear Stations, the management*

of Exelon recognizes its responsibility and authority to operate and maintain the nuclear power stations in such a manner as to provide for the safety of the general public. The Exelon Emergency Preparedness Program consists of the Exelon Nuclear Standardized Emergency Plan (E-Plan), Station Annexes, emergency plan implementing procedures, and associated program administrative documents.

The Exelon E-Plan outlines the basis for response actions that would be implemented in an emergency.

Planning efforts common to all Exelon Nuclear stations are encompassed within the E-Plan. ' This document serves as the Nine Mile Point Nuclear Station (NMPNS) Emergency Plan Annex and contains information and guidance that is unique to the station. This includes facility geography location for a full understanding and representation of the station's emergency response capabilities.

The Station Annex is subject to the same review and audit requirements as the Exelon Nuclear Standardized Emergency Plan. 1.1 Purpose This Station Annex describes the total preparedness program established, implemented and coordinated by NMPNS to assure the capability and readiness of coping with and mitigating both onsite and offsite consequences of radiological emergencies.

The Station Annex covers the spectrum of emergencies from minor localized incidents to major emergencies involving protective measures by offsite response organizations.

Included are guidelines for immediate response, assessment of emergency situations, defined action criteria and delineation of support functions.

Emergency Plan Implementing Procedures provide detailed information for individuals who may be involved with specific emergency response functions.

• *This Station Annex provides for a graded scale of response to distinct classifications for emergency conditions, action within those classifications, and criteria for escalation to a more severe classification.

This *Classification system is compatible with that used by the State of New York and the Oswego County Emergency Management Office. The plans have four emergency categories:

Unusual Event, Alert, Site Area Emergency, and General Emergency.

In addition to notifying the offsite agencies of the existing emergency classification, provisions are made in the implementing procedures for the Station to advise the State and County of appropriate protective actions. 1.2 Emergency Organization The organization for control of emergencies begins with the shift organization of the affected unit(s) and contains provisions for augmentation and extension to include

• other Division personnel, and outside emergency response organizations.

As an incident increases in severity or . potential severity, the emergency response and corresponding response organization must necessarily increase in size. Staffing levels have been established to provide appropriate response and are discussed in detail in Section 2.0 of this Station Annex. June 2016 NM 1-1 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 1.3 Interrelationship Between Emergency Plan and Other Procedures Interrelationship of this Station Annex with other procedures, plans and emergency arrangements is necessary to ensure an effective response organization.

These interrelated documents include: a. Nine Mile Point Nuclear Station Emergency Plan Implementing Procedures are designed to detail specific actions required by Station personnel in response to radiological and non-radiological emergency conditions.

A listing of these procedures is contained in Appendix C. b. Operating Procedures (OP), Emergency Operating Procedures (EOP) Special Operating Procedures (SOP), and Severe Accident Procedures (SAP) detail immediate and subsequent operator actions in response to various system transients.

These operating procedures are coordinated with the Station Annex and its implementing procedures to ensure appropriate actions are taken on a timely basis. c. Station Chemistry Department and Radiation Protection Department Procedures define health physics requirements for the control and handling of radioactive materials, personnel decontamination, and respiratory protection, sampling techniques, radiation survey techniques and radiation exposure guidelines.

Selected procedures, which are applicable to both normal and emergency conditions, are used in conjunction with the Station Annex and its implementing procedures.

d. Station Physical Security arid Fire Protection Plans and their implementing procedures, provide overall guidance and specific instructions to Nuclear Security and Station personnel for emergencies involving security or fire. These plans and procedures are coordinated with the Station Annex and its implementing procedures to ensure compatibility, and with Offsite Plans to ensure prompt access for Offsite Response Organization Responders when necessary.

e. The Oswego County Radiological Emergency Preparedness Plan and the New York State Radiological Emergency Preparedness Plan, in conjunction with this Station Annex and its implementing procedures, provide for early and redundant notification schemes, continued assessment and update of radiological conditions, and the coordination of onsite and offsite protective actions. The concept of operations, and its relationship to the Federal, State, local and private organizations that are part of the overall emergency response organizations, is described in Section 2.0 and 4.0. A block diagram, which illustrates these interrelationships, is included in Station Annex, Figures 4.1-4.3, Emergency Organizations Interfaces.

Illustrations of how the interfaces between various segments of response organizations change during various phases of emergency and recovery operations are shown in Station Annex, Section 4. June 2016 NM 1-2 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Section 2: Organizational Control of Emergencies This section describes the Exelon Emergency Response Organization (ERO) at Nine Mile Point, its key positions and associated responsibilities.

It outlines the staffing requirements which provide initial emergency response actions and provisions for timely augmentation of on-shift personnel when required.

It also describes interfaces among emergency response personnel and specifies the offsite support available to respond to the nuclear generating stations.

2.1 Typical

Nuclear Division/Station Organization The typical Nuclear Division organization for normal operation is shown in GAP-POL-01, Composition and Responsibility of the Nine Mile Point Nuclear Station LLC Organization.

Personnel in certain categories, principally Operations, Chemistry and Radiation Protection work in shifts so that coverage is provided 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. For certain station conditions, such as outages, testing, etc., personnel who do not normally work on shift may work other than normal hours to provide extended coverage.

The minimum staffing at each Unit during normal operation is contained in the NMP On-Shift Staffing Analysis Report, EP-AA-1013, Addendum 1. A detailed analysis of initial on-shift responsibilities and response to an emergency

• condition is contained in the NMP On-Shift Staffing Analysis Report, EP-AA-1013, Addendum 1. 2.1.1 Station Responsibility During Normal Working Hours During normal working hours, the Vice President Nine Mile Point has overall responsibility for the. site. The Plant Manager has overall responsibility for Unit 1 and Unit 2 operations.

The Shift Manager (SM) on duty has responsibility for ensuring that the Unit is operated safely and within the respective license and Technical Specification requirements

.. The SM has the authority and responsibility to order shutdown of the reactor and/or declare an emergency if* required.

Also, any licensed reactor operator on duty in a Control Room can shutdown (scram) the reactor if it is in an unsafe condition.

2.1.2 Station

Responsibility During Off-Normal Working Hours June 2016 During off-normal working hours, the SM's have overall responsibility for the site and safe operation of their respective units. Selected management personnel are on call and may be reached through the use of an approved notification system if a SM needs to notify them of an event that requires technical consultation or requires additional personnel.

However, it is the on-duty SM who has the responsibility and authority to declare an emergency.

Upon declaring an emergency, the SM immediately becomes the Shift Emergency Director.

In the event of an emergency declaration due to an initiating condition affecting both Unit 1 and Unit 2, both Units' SMs will confer and determine:

NM 2-1 EP-AA-1013 (Revision

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• Nine Mile Point Annex Exelon Nuclear

• The Shift Manager of the Unit with the higher emergency classification will become the Shift Emergency Director.

• If emergency classification levels are equal, the SM first notified will become the Shift Emergency Director.

• If there is any question as to who should initiate the Station Annex, the Unit 1 SM shall assume the Shift Emergency Director duties. 2.2 On-Shift Emergency Response Organization Assignments The initial phases of an emergency situation at a nuclear station will most likely involve a *relatively small number of individuals.

These individuals must be capable of (1) determining that an emergency exists; (2) providing initial classification and assessment; and (3) promptly notifying other groups and individuals in the emergency organization.

The subsequent phases of the emergency situation may require an increasing augmentation of the emergency organization.

All emergency facilities will have minimum staffing within 60 minutes. Minimum staff positions are defined in Table 2.1. All Exelon Nuclear stations have the capability at all times to perform detection, mitigation, classification, and notification functions required in the early phases of an emergency.

2.3 Authority

Over The Emergency Response Organization The Emergency Director in Command and Control is the designated Exelon individual who has overall authority and responsibility, management ability, and technical knowledge for coordinating all emergency activities at the nuclear power station. The Emergency Director will immediately and unilaterally initiate any emergency actions, including providing protective action recommendations to authorit.ies responsible for implementing offsite emergency measures.

The Shift Manager is available at all times to assume the responsibilities of Emergency Director.

A qualified individual is on-call to respond to the EOF and relieve the Shift Manager of Emergency Director duties. 2.4 Criteria for Assuminci Command and Control (Succession)

The responsibility for initial assessment of and response to an emergency rests with the Shift Manager. Emergency.

personnel assume responsibility for their positions upon receiving notification to activate when an event has been declared.

June 2016 NM2-2 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear The Emergency Director responsibilities are initially assumed by the Shift Manager. If the event is classified at an Alert or Higher level, or the Shift Manager deems it appropriate, the Shift ERO will be augmented by the on-call ERO. The on-call Corporate Emergency Director will report to the EOF and assume Command and Control. In accordance with the Nine Mile Point Emergency Plan, the TSC Emergency Director does not take Command and Control responsibilities.

• The Shift Manager is relieved of Command and Control as soon as possible after the declaration of an Alert or higher classification.

Command and Control does not transfer until the following criteria have been met:

• Adequate EOF staff levels are present in support of the non-delegable responsibilities.

• The staff has been fully briefed as to the status of the event and the currently proposed plan of action.

• A formal turnover between the Emergency Director relinquishing Command and Control and the Emergency Director assuming Command and Control has been made. 2.5 Non-Delegable Responsibilities

' . Functional responsibilities of the Emergency Director that may not be delegated are: * . Classify and declare emergencies.

• Direct and approve offsite emergency notifications to state and local authorities.

• Make Protective Action Recommendations to offsite authorities.

• Ensure appropriate evacuation actions for plant personnel.

• Approve emergency exposures and/or the issuance of Kl.

• 2.6 Emergency Response Organization Positional Responsibilities Table 2.1 outlines ERO positions required to meet minimum staffing and full augmentation of the on-shift complement at an Alert or higher classification, and* the major tasks assigned to each position.

The full augmentation staffing levels are used as a planning basis to cover a wide range of possible events. For extended events (one which lasts for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), actual staffing will be established by the Emergency Director based on the event and personnel availability.

However, additional staffing or reduced staffing will only occur after discussion concerning the impact on plant operations and emergency response.

The station's ERO consist of three major sub groups reporting to the Emergency Director:

June 2016 NM 2-3 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear

• Onsite ERO, consisting of Control Room, TSC, OSC and Security staffs. The primary functions of the Onsite ERO is perform mitigative actions and ensure appropriate onsite protective actions are taken.

• Offsite ERO, consisting of EOF staff. The primary functions of the Offsite ERO are to interface with offsite authorities and perform offsite radiological assessment.

• Public Information ERO, consisting of JIG staff. The primary function of the Public information ERO is to provide accurate information to the public through News Media. 2.7 Emergency Response Organization Block Diagram Figures 2.2 through 2.6 show the reporting chains and interfaces of the ERO. 2.8 Corporate Emergency Response Organization In the event of a declared emergency at one of Exelon's Nuclear Stations, a Corporate Duty Officer is notified.

The Duty Officer will notify senior company management personnel of the event. The Emergency Director will keep senior management informed of events and any need for assistance.

Specific departments of the company may be called on to assist as necessary to provide support for logistics, public information, finance, technical issues, etc .. Senior management may assist with interfacing government authorities and other outside organizations.

2.9 Industry/Private Support Organizations Exelon retains contractors to provide supporting services to the company's nuclear generating stations.

For station specific support, copies of current contracts and letters of agreement with these groups are maintained by the Emergency Preparedness Department.

Current contracts and letters of agreement are maintained in the Emergency Preparedness Department's files. a. Support from Other Nuclear Power Plants: The Nine Mile Point Nuclear Station is a co-signator to a Letter of Agreement (see Appendix 2) between the James A. Fitzpatrick Nuclear Power Plant, R. E. Ginna Power Station and the NMPNS. In the event of a radiological emergency or other situations resulting in the need for additional equipment and/or personnel assistance, these plants have agreed to provide assistance as requested.

June 2016 NM 2-4 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 2.10 Coordination with Participating Government Agencies 2.10.1 Federal Agencies The principal Federal government agencies having emergency responsibilities relative to the NMPNS, and a summary of those responsibilities, are: a. U.S. Department of Energy (DOE) The DOE, Brookhaven Area Office, will respond to requests from NMPNS for assistance.

This assistance is limited to advice and emergency action(s) essential for the control of the immediate hazards to public health and safety. The primary method of notification to DOE is by commercial telephone.

Notification may also be made through NRC. Assistance can be requested by the NMPNS ED/RM, the Oswego County Emergency Management Director or the Commissioner of the New York State Department of Health. Medical Assistance provided by DOE could also include medical assistance by the Radiation Emergency Assistance Center/Training Site (REAC/TS)

Support from Oak Ridge. When notified of an emergency the Federal Radiological Monitoring and Assessment Plan (FRMAP) team would request a Coast Guard helicopter pick up a six person team at Brookhaven and fly them to the Nine Mile Point area with their equipment.

Approximate arrival time of five (5) hours from notification is expected.

This team would provide initial radiation surveys, obtain airborne samples and analyze these samples with the equipment available.

The team would also act as an advance party to establish an initial base of operations for follow-on personnel.

A possible location for the FRMAP team to set up operations is the Oswego County Airport, which is about ten (10) miles from the NMPNS and in close proximity to the Emergency Response Facilities yet still outside of the 10 mile EPZ. Use of this airport facility would also allow for equipment to be flown in on fixed wing aircraft close to the facilities that would be used for staging and dispatch.

b. Federal Energy Regulatory Commission (FERC) June 2016 Two (2) licensed hydroelectric developments are situated within a ten (10) mile radius of the Nine Mile Point Nuclear Station and the James A. Fitzpatrick Nuclear Power Plant. The Minetto and Varick Hydroelectric Stations are part of Project Number 2474 licensed with the Federal Energy Regulatory Commission.

A plan has been developed to implement a response plan to safely shutdown and evacuate these hydroelectric facilities.

This would be done in the event of a radiological emergency at either nuclear station. In addition, this plan addresses the means to minimize the impact to the public as a result of this emergency shutdown of the hydroelectric stations.

NM 2-5 EP-AA-1013 (Revision

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/ Nine Mile Point Annex Exelon Nuclear 2.10.2 State and Local Agencies This section identifies the principal State and local government agencies having action responsibilities in the event of a radiological emergency, including a Hostile Action Based event, in the vicinity of the NMPNS. The radiological emergency response plans of these agencies:

describe their respective

• responsibilities, authorities, capabilities and emergency functions; contain provisions for preparedness and response to radiological emergencies by each organization; and contain the primary and alternate methods of emergency notifications.

a. Oswego County Emergency Management Office (OCEMO) June 2016 The OCEMO is the lead government agency for coordination and response at the local level. The Oswego County Radiological Emergency Preparedness Plan contains provisions for:

• Planning and coordination with local, State and Federal authorities

• Initial response to notification by NMPNS

• Alert and warning of local political subdivision

• Notification of other emergency response personnel

• Public information concerning the incident

• Evacuation and other protective measures for local populations Normally the OCEMO is notified by NMPNS via the County Warning Point. It may, however, be notified by the New York State Office of Emergency Management (NYSOEM).

A secondary method of notification is via radio from the NMPNS to the County EOG or County Warning Point. NM 2-6 EP-AA-1013 (Revision

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Nine Mile Point Annex Figure 2.1: Minimum Staffing Requirements for the ERO ';,', ; "* ,,,:;' . Functional Area 1. Plant Ops and Assessment Major

• . Control Room Staff 2. Emergency Command and Control Direction and Control : ', ;:: '" Emergency Positions , Shift Manager (Shift) Senior Reactor Operator (SRO) (Shift) Reactor Operator (RO) (Shift) Equipment Operator (EO) (Shift) RP Technician (Shift) Chemistry Technician (Shift) Shift Manager (Shift) Corporate Emergency Director (EOF) Station Emergency Director (TSC) Minimu 1 m' (1) 1* 1* 2* 2* 1* 1* See above 1 1 Exelon Nuclear Full Augipentation

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

-...................................................................................................................................... , ... _.__ ...........................................................

,.,_ ...................................................................................................................... . Facility Control 3. Notification

& Emergency Comm. Communications June 2016 Plant Status & Technical Activities In-Plant Team Control Governmental TSC Director (TSC) EOF Director (EOF) Shift Communicator (Shift) State/Local Communic_ator (EOF) ENS Communicator (TSC) , HPN Communicator (EOF) All ERFs: Operations Communicators (one for TSC, EOF, OSC and ea:ch CR) EIS Operators (all facilities)

Team (OSC) EOC Communicator (EOF) State Liaison (EOF) County Liaison (EOF) Incident Command Post Liaison NM 2-7 1 1* 1 1 5 4 (Note 2) 1 (Note 8) EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear . , . "* '_;* '. Minimum . ,. < "'.!

.::'. . :full

4. Radiological Offsite Dose Assessment Dose Assessor (EOF) Environmental Coordinator (EOF) Offsite Monitoring Team (EOF) 2 Assessment Offsite Surveys 1 5. Plant System Engineering, Repair, and Corrective Actions 6. In-Plant Protective Actions 7. Fire Fighting June 2016 4 Onsite Surveys RP Technician (OSC) 2 ..................

• -**-****--*""'""******-....................

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

,_ .. ,, ..............................

.. In-plant Surveys RP Technician (OSC) 2 __ ,, .............

_,,,,, ...... -.............

,_,,, .. _,_, __ .. ___ ,,,_ .. ,, ....... __ . **-*--****-******-

.. --...... ,,, ____________________

,, ____ .............

__________

.. ,_ .....................

____ ,,, .. ,,,,_,_ ...... _,__ ...........

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

_ .............................

• • • • • • • -****--*--*-***-*********" Chemistry . Chemistry Technician (OSC) RP Supervisory Technical Support I Accident Analysis . Repair and Corrective Actions Radiation Protection TSC Radiation Protection Manager (TSC) EOF Radiation Protection Manager (EOF) Shift Technical Advisor (Shift) Technical Manager (TSC). Electrical Engineer (TSC) Mechanical Engineer (TSC) Core Thermai Hydraulic Engineer (TSC) Operations Manager (TSC) Technical Advisor (EOF) TSC Technical Staff Maintenance Manager (TSC) OSC Director (OSC) Assistant OSC Director (OSC) Electrical Technicians (OSC) Mechanical Technicians (OSC) l&C Technicians (OSC) Operations Personnel (OSC) Leads (Ops, Elec, Main, l&C, & RP) RP Technician (OSC) Fire Brigade (Shift) NM 2-8 1 1 Note 5 EP-AA-1013 (Revision

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Nine Mile Point Annex Functional Area 8. First Aid I Rescue 9. Site Access Control 10. Resource Allocation and Admin Support 11. Public Information June 2016 Major Tasks Emergency Positions First Aid provided by trained Shift Personnel Rescue support provided by shift personnel or OSC personnel.

Security & Accountability Logistics Security Shift Supervisor (Shift) Security Personnel Security Coordinator (TSC) EOF Logistics Manager (EOF) JIC Logistics Manager (JIC) Administration Administrative Staff (TSC) Administrative Staff (OSC) Administrative Staff (EOF) Administrative Staff (JIC) ................................................................

_ ***-********----***-

.. ,,_., ____ .............................................

--*--*-**-*******

• • • • • • • • • • • • • • • • • • • • • • -

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • -

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • --****-***--****-

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

• • • --****-

Facility Operations Computer Specialist (TSC I OSC) Media Interface Computer Specialist (EOF I JIC} Company Spokesperson (JIC) Media Liaison (JIC) .................................................

___ ******************-*****---***-

-* ***********---*****************--*********************-**

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

---

**-****-****-*

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

• • -Information Development Media Monitoring and Rumor Control News Writer (JIC) Technical Advisor (JIC) .....................................................................................................

-................ . MM/RC Coordinator (JIC) Inquiry Phone Team (JIC) Media Monitoring Team (JIC} -------------

-*--************--********-*******-*--*-------**-*-****-*-*****-

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • -*****-*******------

Facility Operation and JIC Manager (JIC} Control JIC Security (JIC} TOTALS: NM 2-9 Minimum Staff (1) Note 6 Exelon Nuclear Full Augmentation 2 1 2 (Note 7) 2 (Note 7) ***************************

• • • • • • • • • • • ---

• • • • • • • • • • • • • ---****************-

Shift staff: 1 O Augmented Min Staff: 40 2 (Note 3) 2 (Note 3) 513 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Notes: (1) (2) (3) (4) (5) (6) (7) (8) June 2016 P r ovided by On-Shift personnel , denoted by an asterisk. Computer Specialist may perform EIS Operator duties. Pe r sonnel numbers depend on the type and extent of the emergency.

Craft Lead positions can be f i lled by senior technicians or craft supervisors. Fir e Brigade per FSAR!Techn i cal Specifications , as appl i cable. May be a collateral duty. Per Station Security Plan. EOF/JIC or TSC/OSC may share Administrative Staffs Up to 3 Incident Command Post (ICP) Liaisons may be called based on event when a near site ICP is established.

NM 2-10 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Figure 2.2: ERO Management Structure June 2016 I I EOF Director' Offsite ERO Interface with Offsite Response Organizations (Federal , State and Local) to coordinate Protective Actions for the public I Corporate Emergency Director I Station Emergency Director Onsite ERO Onsite (OCA) Protective Response and Mitigative Actions. NM 2-11 l I I i I I I JIC Manager Public Information ERO Provides information to the Public through the News Media, addresses phone inquiries , conducts Rumor Control operations. EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear Figure 2.3:TSC Staffing Stat i on Di r ector TSC Director TSC .. Adm i n Staff *-E I S Ope r ator I I --I I Technica l I TSC Rad Protect i on Secur i ty Operat i ons Ma n ager Ma in tenance Manager Manager u Manage r Coord i nator I I I I I (CAS) ;I (Co n tro l Room) (OSC) (OSC) -Elec t r i ca l Eng i neer -I. I. Secur i ty Sh i ft Shift Manager OSC Director i! RP Lead Superviso r Mechan i ca l -ENS Commun i cato r --Secur i ty For i Enginee r i ce i Core Therma l I i -J I. Hydrau li c -TSCOps I Commun i cator Eng i nee r I I I TSC/OSC Comp u ter I ' -Specia li st -CR Ops Communicator .ii T i I ec hn ca Sta ff June 2016 NM 2-12 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Figure 2.4: OSC Staffing osc Director OSCAdmin I EIS Staff r -Operator J I I I Assistant OSC Team OSC OPs I I OSC Director Tracker Communicator I I I I I I I Electrical l&C Mechanical i RP Chem Ops I I Lead Lead Lead :I Lead Lead J Lead Electrical I l&C Mechanical RP Chem ! -Techs Techs -Techs -Techs -Techs j-Operators ,I ! j! I June 2016 NM 2-13 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Figure 2.5 EOF Staffing EOF Director State/Local

-Communicator I I I ' EOF ; EOF Logistics EOF Technical Advisor I EOC Communicator Rad Protection Manager J Manager J j I i -EOF Ops Communicator I HPN .I EOF/J IC Computer State --Communicator Specialist

-Liaison I I Dose Assessor Environmental

-EOF Ad min Staff -County Liaison(s)

Coordinator

-EIS Ope r ator Offsite I -Mon. Team Members j June 2016 NM 2-14 EP-AA-1013 (Revision

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Nine Mile Point A nnex Exelon Nuclear Figure 2.6 JIC Staffing I JIC I Manager Company Spokesperson MM/RC JIC Logistics Coordinator i Manager Inquiry Phone -Team JIC News Admin Staff Writer J Media ' -Monitoring Team l ------*-----------.

Media ! JIC Tec h nical i i Liaison Advisor I JIC ! ; ! EIS Operator I Security I i Ju ne 2016 NM 2-15 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Section 3: Emergency Conditions

3.1 Classification

System The spectrum of probable and postulated emergency conditions have been categorized into four emergency classes. Emergency Action Level (EAL) criteria have been specified for recognizing, categorizing and declaring emergency classes based, to the extent feasible, on readily available information such as Control Room instrumentation.

In many cases the emergency classification is immediately apparent from in-plant instrumentation and is consistent with requirements of USN RC Regulatory Guide 1.101. In other cases more extensive assessment is necessary to determine the applicable emergency classification.

In any case, continuing assessment ensures that the emergency classification is commensurate with the severity of the emergency condition.

The information is presented by recognition Category with the associated Unit system/ equipment or instrument parameters clearly defined:

• Reactor Fuel

• Electrical Failures

• RPV

• Equipment Failures

• Primary Containment

• Hazards

• Secondary Containment

• Other

• Radioactivity Release Each EAL Initiating Condition is structured in the following way:

• Recognition Category-as described above

• Emergency Class-Unusual Event, Alert, Site Area Emergency and General Emergency

• Initiating Condition-Symptom-or Event-Based, Identification and Title

• Operating Mode applicability-Power Operation, Hot Standby,

• Hot Shutdown, Cold Shutdown, Refueling, Defueled or All. NMPNS maintains the capability to assess, classify and declare an emergency condition within 15 minutes after the availability of indications to plant operators that an Emergency Action Level (EAL) has been exceeded.

The 15 minute criterion does not prevent implementation of response actions to protect the public health and safety provided that any delay in declaration does not deny the State and Local authorities the opportunity to implement emergency response actions. The 15 minute criterion commences when plant instrumentation, plant alarms, computer displays or incoming verbal reports that correspond to an EAL first June 2016 NM 3-1 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear become available to any plant operator and encompasses all assessment, classification, verification and declaration actions. As used here, "plant operator

means any member of the plant staff who, by virtue of training and experience, is qualified to assess the indications or reports for validity and to compare the same to the EALs. A "plant operator

does not encompass plant personnel such as chemists, radiation protection technicians, craft personnel, security personnel, and others whose positions require they report, rather than assess, abnormal conditions to the control room. In the case where EALs are related to an analysis, e.g. dose assessment or sampling, the 15 minute declaration period starts with the availability .of analysis results, to any plant operator, that show the conditions of the EAL to be exceeded.

Procedures EP-CE-111, Emergency Classification and Protective Action Recommendations, provide specific implementation guidance on this classification system. Figure 3.1 provides action and participation by response organizations for the various emergency classifications.

EP-AA-1013, Addendums 3 and 4 provide the basis by which each of the emergency action levels was determined.

3.1.1 Unusual

Event Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection.

No releases of radioactive material requ'iring offsite response or monitoring are expected unless further degradation of safety systems occurs. Although the emergency situation can be corrected and/or controlled, notification of NMPNS Management may be performed.

In addition, appropriate offsite agencies are notified of the nature and extent of the incident, even though no action may be required of them. 3.1.2 Alert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of intentional malicious dedicated efforts of a hostile act. Any releases are expected to be limited to small fractions of the EPA Protedive Action Guideline exposure levels. 3.1.3 Site Area Emergency Events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or security events that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the public. Any *releases are not June 2016 NM3-2 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.

3.1.4 General

Emergency Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or security events that result in an actual loss of physical control of the facility.

Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. 3.*2 Spectrum of Postulated Accidents Postulated accidents are described in Chapter XV of the Unit 1 FSAR and Chapter 15 of the. Unit 2 USAR. Postulated accidents for dry fuel storage (ISFSI related) are described in the Transnuclear Inc. Updated Final Safety Analysis Report (NUHOMS UFSAR) for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel. Postulated accidents utilizing the Standardized NU HOMS -61 BT dry shielded canisters are described in Section K.11.2 of the NUHOMS UFSAR and Section T. 11.2 of the UFSAR describes the postulated accident utilizing the Standardized NU HOMS -61 BTH dry shielded canisters, June 2016 NM 3-3 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear FIGURE 3.1 REQUIRED ACTIONS AND PARTICIPATION BY RESPONSE ORGANIZATIONS FOR VARIOUS EMERGENCY CLASSES Participation By Participation NMPNS By Off-Site Agencies Emergency Necessity for Necessity for Plant Class Protective Action Corrective Staff On-Site Off-Site Action Unusual Event Possible Not Possible 1> Action No Action Alert Site Area Emergency General Emergency

1) 2) 3) Required Required Required Possible Not Possible 2> Action EOC's Required Required On Alert Probable Not Probable 3> Action EOC Required Required Action Required Probable Required Probable 3> Action EOC Required Action Required May involve normal organizational response such as ambulance, rescue personnel and use of medical facilities as would occur for any industrial accident.

May require police, firemen, ambulance, and/or medical facilities to be on alert or to respond. May involve police and Coast Guard, firefighters, ambulance and/or use of medical facilities.

May involve radiological monitoring teams from NMPNS, local, State and Federal agencies.

• , June 2016 NM 3-4 EP-AA-1013 (Revision 2)_

Nine Mile Point Annex Exelon Nuclear 4.0 Emergency Measures Emergency Measures are actions taken to ensure that an emergency situation is assessed and that proper corrective and/or protective actions are taken. These actions include activation .of the appropriate components of the emergency organizations, both on-site and off-site; assessment of plant systems status and radiological conditions; mitigative actions to mitigate or terminate an emergency situation; protective actions to minimize the consequences of the emergency to Station personnel and to the general public in the Station environs; decontamination and medical treatment for Station personnel; and other supporting actions such as timely and accurate emergency news releases.

to the public media. This section describes the emergency measures which may be performed and applicable criteria, guidelines and methodology for performing those measures.

4.1 Initiation

of Emergency Actions Emergency a.ctions are initiated primarily in response to alarmed instrumentation, but may be initiated through notification to the Control Rooms by individual(s) at the Nine Mile Point Nuclear Station who become aware of an apparent emergency situation or by persons outside of the plant in the case of severe weather warnings or hostile actions. The affected unit Control Room Operator (CRO) performs the necessary immediate actions to contend with the off-normal situation in-accordance with instrument alarm response procedures (which_ are contained in the Operating Procedures), Special Operating Procedures, _ Emergency Operating Procedures and/or other appropriate procedures.

The CRO promptly notifies the affected unit SM of the potential emergency situation.

This SM assesses the situation and, if declares the emergency.

As delineated in Section 4.1 of -this Emergency Plan, NMPNS maintains the capability to assess, classify and declare an emergency within 15 minutes after the availability of indications to plant operators that an Emergency Action Level (EAL) has been exceeded.

The affected unit SM assumes the role of NMPNS Shift Emergency Director until responsibilities are relieved by the Corporate Emergency Director in the EOF. In the event of an emergency declaration due*to an initiating condition affecting both Unit 1 and Unit 2, both Units' SMs will confer and determine:

• The Unit with the higher emergency classification will become the Shift Emergency Director.

• If emergency classification levels are equal, the SM first notified will become the Shift Emergency Director.

• If there is any question as to who should initiate the Station Annex, the Unit 1 SM shall assume the Shift Emergency Director duties. June 2016 NM 4-1 (Revision

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Nine Mile Point Annex Exelon Nuclear 4.2 The Shift Emergency Director continues to assess and classify the condition and initiates the appropriate corrective and protective actions and ensures activation . of the necessary segments of the total emergency organization.

The Operating Procedures contain appropriate action statements which refer the operator to the Emergency Plan Implementing Procedures when specified plant

• parameter values are exceeded or equipment status warrants such response.

Severe Accident Procedure (SAP) entry conditions are defined in the station Emergency Operating Procedures.

The Shift Emergency Director, in consultation with the Station Emergency Director, determines when SAP entry is required.

Activation of Emergency Organization This section describes the provisions for notifying and/or activating groups and organizations within the emergency organization in response to potential or actual emergency events at the station. Procedures for notifying, alerting and mobilizing emergency response organizations, including message authentication, are contained in procedure EP-CE-114-100, Emergency Notifications (CNG). Figure 4.1 summarizes the notification/activation of both the onsite and the offsite emergency organization and designates potential action requirements for each emergency classification.

A diagram identifying the major emergency and their interfaces during various stages is shown in Figures 4.2 and 4.3. 4.2.1 Offsite Notification and Follow-up Messages The contents of initial emergency notification messages which would be sent from the affected unit to New York State and Oswego County is contained in CE-114-100.

Notification Fact Sheets were developed in conjunction with New York State and Oswego County, and serve as the means of initial emergency notification.

The contents of the Notification Fact Sheets are consistent with the . guidance outlined in Section 11.E of NUREG-0654.

As a minimum, the following information is provided:

o Facility name, communicator name and call back telephone number o Date/time of incident o Class of emergency o Brief description of event o . Radioactive material release information o Protective action recommendations o Event prognosis o Meteorological information June 2016 NM 4-2 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Follow-up notifications are made at regular intervals as detailed in EP-CE-114-100 and contain information consistent with the guidance detailed in Section 11.E of NUREG-0654.

As a minimum the follow-up information contains the above information and the following:

0

• Actual or projected dose rates and projected integrated dose rates at site boundary 0 Projected dose rates and integrated dose at projected peak and at 2, 5 and 10 miles 0 Surface contamination estimates A mutual agreement has been reached between New York State Licensees and New-York State excluding event prognosis information fro"m initial notification messages:

4.2.2 Offsite

Emergency Organization

a. Offsite Authorities The Corporate Emergency Director ensures that offsite authorities are notified and apprised of potential or actual emergency events at the NMPNS. Notifications are made to the Oswego County and New York State Warning Points using methods described in EP-CE-114-100.

Notification to these authorities of an Unusual Event, an Alert, a Site Area Emergency or a General Emergency commences within 15 minutes following the declaration of an emergency cfassification.

A representative .from NMPNS may be sent to the State Emergency Operations Center (SEOC) and to the Oswego County Emergency Operations Center (OCEOC) for a Site Area or General Emergency when the SEOC and the OCEOC, respectively, is fully activated.

These representatives aid and assist the New York State Disaster Preparedness Commissioner and the Chairman of the Oswego County Legislature, or their representatives, in defining the extent of the emergency and mitigating measures being taken. Backup radiological emergency assistance may be provided by the U.S. De*partment of Energy in Brookhaven, N.Y. Notifications for assistance may be made by the NMPNS Corporate Emergency Director, by the Oswego County Emergency Management Director or by the New York State Commissioner of Health. 4.2.3 On-Site Notification and Organization

a. Notification of NMPNS personnel takes place through the foilowing methods: June 2016 1) PA System (GAltronics).

This system is capable of sending voice messages and signals indicating a fire, station alarm, or evacuation alarm to all areas within the protected area. It is used to alert personnel onsite of emergency conditions.

NM 4-3 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 2) Telephone.

The telephone can be used to contact any needed personnel during emergency conditions.

EP-CE-114-100 contains the implementing procedures for making appropriate notifications.

b. Upon being informed of a . potential or actual emergency condition, the affected unit SM immediately assesses the condition.

The SM ensures that appropriate actions have been initiated to maintain the safe and proper operation of the plant. This SM then classifies the condition as an Unusual Event, Alert, Site Area Emergency or General Emergency.

If the event is classified as an emergency (as defined in EP-CE-111) that requires implementation of this Plan, the SM assumes the role of Shift Emergency Director and takes the following actions:

• 1) Implement immediate actions in accordance with this Plan and the applicable Emergency Plan Implementing Procedures.

2) Ensure that on-site emergency response individuals and groups are notified (and off-site groups, if conditions require), using the PA system and/or direct communications.

3) Notify on-site individuals to implement a Local Area/Building, Protected Area or Exclusion Area Evacuation, if appropriate, which may include accountability.

These notifications are made by sounding the appropriate alarm followed by an announcement of supplementary information over the PA system. *Notification is also made to the JAFNPP Control Room (who then activates their notification system). 4) May notify the Plant Manager or their designated alternate to apprise them of the situation.

Because of the probable short duration and/or low severity of the condition, the Shift Emergency Director responsibilities are likely to remain with the SM through termination of Unusual Event classifications.

5) Ensure that off-duty station personnel are notified to provide assistance with emergency activities as necessary.

This notification process is described in EP-CE-114-100.

Off-duty personnel are called in as required.

6) Notify appropriate TSC, OSC *and EOF personnel if the condition is classified as an Alert or higher . . 4.3 Assessment Actions Provisions are made for assessment and continuing re-assessment throughout the course of an emergency to ensure the effective coordination, direction and upgrading of emergency activities in a timely manner. The assessment actions are described in detail in the Emergency Plan Implementing Procedures.

4.3.1 Unusual

Event June 2016 NM 4-4 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear The purpose of the Unusual Event classification is to provide early warning of minor events, which could lead to more serious consequences.

The Unusual Event conditions represent potential degradation of the level of safety of the plant or indicate a security threat to facility protection.

No releases of radioactive material requiring offsite, response or monitoring are expected unless further degradation of safety systems occurs. Declaring an Unusual Event assures that the first step for any response later found to be needed, has been carried out by bringing onsite staff and offsite organizations to a state of readiness, thus providing a system for handling information and decision making. The NRG; State, and Oswego County authorities will be promptly notified to assure that the first step of any necessary response can quickly be initiated.

Offsite organizations will standby for further information or termination.

On-shift *resources can be augmented to assess and respond as needed. 4.3.2 Alert Events of the Alert classification involve actual or potential degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of intentional malicious dedicated efforts of a hostile act. Any radioactivity released would result in exposures of only a small fraction of the guidelines for required offsite action. By assuring that emergency personnel are available, protective actions, such as performing confirmatory radiation monitoring and providing

/ offsite authorities with current status information, will be ensured. For events which fall into the Alert classification, the Emergency Response*

Organization will promptly notify the NRC, State and County authorities of the Alert Classification and the reasons for the classification.

The TSC and EOF will be staffed to assist in the assessment of the incident and determination of proper responses.

Periodic plant status updates will be given to offsite authorities who

• will also be advised of any change in the classification of the event. Non-essential personnel will normally be evacuated from the protected area (provided it is safe) to designated locations outside of the protected area at this level. All ERO personnel will assemble at their designated emergency facilities, and accountability may also be initiated.

This ensures that:

• Appropriate staff is available to mitigate the event,

• The potential to over-expose non-essential personnel is minimized,

• Non-essential personnel are prepared for possible exclusion area evacuation by pre-staging these,personnel outside of the protected area . . The JIC will be staffed in order to coordinate public information activities warranted by the emergency.

Offsite agencies may activate their resources and facilities and may alert other emergency personnel, such as monitoring teams, communication

• centers, the Emergency Alert System (EAS), and law June 2016 NM 4-5 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear enforcement.

They will be ready to escalate to a more severe classification, if appropriate.

• 4.3.3 Site Area Emergency A Site Area Emergency (SAE) is declared when events are in progress or have occurred which involve actual or likely major failures of plant functions needed for the protection of the public or security events that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) prevents effective access to equipment needed for the protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.

In the event that a SAE is declared, the actions to be taken by various plant groups are detailed in the implementing procedures for the plant. The Emergency Response Organization will make the initial notification to the County authorities, State, and NRC. The purpose of declaring a SAE is to assure that non-essential personnel are protected in the event of a release of radioactive materials.

Should a release be anticipated or in progress, non-essential personnel will normally be directed to evacuate to the either the Offsite Assembly Area (provided it is safe) for monitoring and if necessary decontamination, or home if there was no release of contamination from the station. If no release is anticipated or in progress, essential personnel will normally remain at designated locations within the exclusion area, to permit more rapid return of *personnel to normal duties. Accountability of personnel remaining within the protected area, as a minimum will commence at this level, and continues until event termination or escalation.

Also, offsite agency authorities will be available at primary response centers for consultation and updates on the situation, and to provide information to the public. For events which fall into the SAE classification, the County, State, and NRC will be promptly notified of the SAE classification,*

and the reasons for the SAE classification.

The TSC and EOF will be.staffed to assist in the assessment of the incident and determination of proper responses.

Periodic plant status updates will be given to offsite authorities who will also be advised of any change in the'classification of the event. The JIC will .be staffed in order to coordinate public information activities warranted by the emergency.

Offsite agencies may activate their resources and facilities and may alert other emergency personnel, such as monitoring teams, communication centers, EAS, and law enforcement.

They will be ready to escalate to a more severe classification, if appropriate.

June 2016 NM 4-6 EP-AA-1013 (Revision

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Nine. Miie Point Annex Exelon Nuclear 4.3.4 General Emergency A General Emergency (GE) is declared when events are in progress or. have occurred which involve actual or imminent substantial core damage or melting with potential loss of containment integrity or security events that result in an actual loss of physical control of the facility.

Releases of radioactive material can be expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. In the event that a GE is declared, the actions to be taken by the various plant groups are detailed in the implementing procedures for the plant. The Emergency Response Organization will make the initial notification to the County authorities, State, and NRC. Initial notification of a GE shall contain initial Protective Action Recommendations.

The purposes for declaring the GE are:

• To initiate protective actions for the public and site personnel as predetermined by projected, or by actual releases.

• To provide continuous assessment of information from the affected unit.

• To provide for consultation with offsite authorities.

• To keep the public informed through the JIC.

• To evacuate non-essential personnel from the exclusion area (provided it is safe) to either the Offsite Assembly Area (OAA) for monitoring and if necessary decontamination, or home if there has been no release of contamination from the station. The TSC and EOF will be staffed to assist in the assessment of the incident and proper determination of responses.

Periodic plant status updates will be given to offsite authorities who will also be advised of any change in the classification of the incident.

The JIC will be staffeo in order to coordinate public information activities warranted by the emergency.

Offsite agencies will activate all needed . resources and facilities.

4.4 Assessment

Capabilities

4.4.1 Field

Radiological Assessment Field radiological data is collected by onsite and offsite survey teams. The teams may be deployed for any emergency classification involving projected or actual releases of radioactive materials.

The survey teams use emergency/company vehicles (or personal vehicles, if needed) for transportation and maintain contact with the EOF or TSC. Downwind Survey equipment is maintained for emergency use by onsite and offsite survey teams.

• This equipment includes portable instrumentation for performing direct radiation surveys, performing contamination surveys and collecting and analyzing airborne samples for gross and iodine radioactivity.

• June 2016 NM4-7 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Rapid assessment of any radiological hazards resulting from the gaseous effluents are made in the field using the environmental samples taken. Radiation Protection Procedures will be used to implement the required radiological surveys/samples and analyze of the results of these surveys/samples taken from within the NMPNS. Procedure EP-AA-112-500-F-55, NMP Offsite Monitoring

• Team Guidance, will be used to analyze the offsite survey and sample results to provide an initial estimate of the offsite radiological .consequences.

Rapid field assessment of liquid samples is not considered essential because the nearest drinking water supply is far enough away to provide ample time for warning the appropriate State and local authorities in the event protective measures are required.

When field liquid samples are . required, they will be taken and transported back to the appropriate facility for assessment.

4.4.2 Field

Airborne Radioiodine Assessment Monitoring for radioiodine is accomplished by the use of portable sampling pumps equipped with a particulate filter and silver zeolite cartridges.

The particulate filter and silver zeolite cartridges can be field counted in a low background area. for immediate determination of total radioiodine concentration.

Cartridges and filters can be further analyzed using gamma spectrometry in either the NMPNS counting laboratory, the environmental laboratory or the adjacent JAFNPP counting laboratory.

The lower limit of detection for radioiodine is less than 1.0E-7 µCi/cc under all weather conditions.

4.4.3 Field

Contamination Assessment A second type of radiological data which the onsite and offsite survey teams collect is surface contamination levels for the radionuclides listed in NUREG-0654, Table 3 (Radionuclides with Significant Contribution to Dominant Exposure Modes). The data obtained from these sample measurements assist in protective action decisions affecting the general public during the emergency and post-emergency .recovery/re-entry phase. This data can be used to determine 1OCFR140 applicability.

Surface contamination may be estimated using procedure EP-AA-112-500-F-55 during the emergency and actual values are determined by sampling snow, grass, soil, leafy vegetation, surface water as deemed . appropriate during emergency recovery activities.

EP-AA-112-500-F-55 describes in detail the emergency radiological environmental sampling program. June 2016 NM 4-8 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 4.5 Dose Assessment Methods and Techniques The NMPNS has established a* method for relating various measured environmental media activity levels to dose rates for key isotopes and gross radioactivity measurements.

NMPNS has formulated provisions for estimating integrated dose from the projected and actual dose rates (refer to EP-AA-110-204, NMP Dose Assessment).

The results of these calculations can then be tabulated and compared with applicable protective action guides. The information most important in determining offsite consequences is source term, dose assessment, environmental measurements and dose projections.

The following paragraphs describe these dose assessment terms and techniques.

4.5.1 Source

Term Determination

a. Projected Source Term Determination The release rate and/or source term from . NMPNS during a nuclear emergency can be projected as described in EP-AA-110-204, and are listed as follows: 1) Containment High Range Monitors . (CHRM) (relate CHRM to a radioactivity concentration in the drywell, then assume a flowrate from the drywell to the atmosphere).

2) Grab samples. 3) Back calculation from downwind gamma dose rate measurements.

4) UFSAR/USAR postulated accident release rates. b. Actual Source Term Determination The method for determining actual release rate for source term determination from NMPNS during a nuclear emergency are described in EP-AA-110-204, and are listed as follows: 1) Effluent monitors 2) Stack teletector (Unit 1 only) 3) Grab samples 4,5.2 Offsite Radiological Dose Assessment Process Dose assessment or projection represents the calculation of an* accumulated dose at some time in the future if current or projected conditions continue.

During an accident, the Plant Parameter Display System and personal computers will provide the ERO with the timely information required to make decisions.

Radiological and meteorological instrumentation readings are used to project dose rates at predetermined distances from the station, and to determine the integrated dose received.

Dose assessment methods used by Exelon personnel to project offsite doses include: June 2016 NM4-9

• EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear a. Monitored Release Points -This method utilizes the plant's effluent .radiation monitors and system flow rates. Effluent release points are used to directly*

calculate a release rate. The point of the release determines the way the source term is affected and is adjusted by the dose assessment process. b.

Leakage/Failure

-This method uses a variety of containment failures or leak rates in conjunction with available source term estimations to develop a release rate to the environment.

A direct vent of containment can be modeled as a failure to isolate. c. Release Point Samples -This method uses a sample at the release point and an estimated flow rate to develop a release rate at the point of release. d. Field Monitoring Team Data -This method uses a field survey or sample and the atmospheric model to back calculate a release rate and ratio concentrations of radioactive material at various points up and downwind of plume centerline.

The computer applications used to provide dose calculations are evaluated against the EPA-400. plume exposure Protective Action Guides (PAGs) applicable for the early phase of an accident.

These evaluations place an emphasis on determining the necessity for offsite protective action recommendations.

Dose assessment actions will be performed.

in the following sequence:

a. First, onset of a release to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> post-accident:

1) Shift personnel' will rely on a simplified computerized dose model to assist them in developing offsite dose projections using real time data from effluent monitors and site meteorology.

b. Second, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> post-accident to event termination:

1) Estimates of off-site doses based on more sophisticated techniques are provided.

Dedicated ERO personnel will analyze the offsite consequences of a release using more complex computerized dose modeling.

These additional methods are able to analyze more offsite conditions than the simplified quick method, as well account for* rnore specific source term considerations

4.5.3 Onsite

Dose Assessment and Protective Actions Health Physics procedures provides procedures for assessing the. radiological conditions on,site, and protective actions needed in response to those actual or. projected conditions.

EP-CE-113, Personnel Protective Actions provides for control of emergency exposures.

4.5.4 Environmental

Measurements

• The second method available to assess dose is based on measured activity in environmental media. Dose can also be determined on the basis of plant and June 2016 NM 4-10 EP-AA-1013 (Revision 2).

Nine Mile Point Annex Exelon Nuclear environmental measurements collected per EP-AA-112-500-F-55 and the post-accident sampling procedures.

Environmental samples collected by the downwind survey teams and environmental survey teams are retu.rned for laboratory analysis.

Environmental media such as milk, human food products and water are analyzed in a laboratory environment to determine the concentrations of key isotopes which wo.uld then be converted (either by hand calculation or computer using appropriate formulas) to dose. 4.5.5 Dose Projection

a. Preliminary estimates of total population exposure are made using the method in EP-AA-110-204, and EP-AA-112-500-F-55.

These preliminary estimates are based ori projected or actual field measurements made during the course of the emergency.*

During the recovery phase of the emergency, these estimates are refined based upon actual emergency and environmental Optically Stimulated Luminescent Dosimeters (OSLO) results, information obtained from the Oswego County Emergency Management Office on evacuated and sheltered population, and evacuation time .estimates for various Emergency Response Planning Areas (ERPA's).

4.6 Mitigative

Actions Detailed Emergency Operating Procedures, Special Operating Procedures, and Severe Accident Procedures as appropriate are used by the station operating personnel to assist them in recognizing potential or actual emergency events and responding to emergency and severe accident conditions.

These procedures describe the mitigative actions necessary to place the plant in a safe condition.

Additionally, Emergency Plan Implementing Procedures, as listed in this Station Annex, Appendix 3, describe subsequent and/or supplemental mitigative actions for the scope of potential situations within each of the emergency classifications.

These Emergency Plan Implementing Procedures are designed to guide the actions of personnel to correct or mitigate a condition as early and as near to the source of the problem as feasible.

4. 7 . Protective Actions Protective actions are measures which are implemented to prevent or mitigate consequences to individuals during or after a radiological incident.

Protective actions within the NMPNS site boundary are the responsibility of the NMPNS Emergency Director, but may include assistance by off-site organizations.

Protective actions outside the NMPNS site boundary are primarily the responsibility of State and local emergency organizations, but may include June2016 .. NM 4-11 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear coordination of activities, dissemination of appropriate data and recommendations by the NMPNS Emergency Director.

4.7.1 Onsite

Protective Actions Onsite protective actions are directed by *the Emergency Director and are reviewed to consider the possible impact on the activities of offsite response personnel prior to being ordered. The primary protective measure for onsite personnel in an emergency is prompt evacuation from areas which may be affected by significant radiation, contamination or airborne radioactivity.

For personnel who must stay onsite as part of the on-site emergency response team other protective measures may be used as discussed in the following sections.

• In addition, a range of protective actions to protect onsite personnel during hostile* action events has been developed.

This range of protective actions ensures the continued ability *to safely shut down the reactors and perform emergency response functions.

The response functions include:

• Evacuation of personnel from target buildings

• Site evacuation by opening gates, while continuing to defend them

• Dispersal of Licensed Operators

• Sheltering personnel away from potential.site targets

• Accounting for personnel after the attack The following are the primary onsite protective actions: a. Local Area/Building Evacuation June 2016 A local area/building evacuation is confined to local areas or buildings within the protected area. This evacuation requires all personnel within the designated area or building to rapidly exit the area/building and remain clear of the area/building until further notice. The decision to implement a local area/building evacuation is the responsibility of the Emergency Director.

This decision is based largely on evaluation and judgment of the magnitude and severity of the situation on a case by case basis. Factors to be considered may include:

• the safety of personnel within the area/building

• smoke/heat or other hazards

• actual or estimated levels of radiation and/or airborne radioactivity' involved, as well as the potential exposure to personnel that would result from both evacuating and not evacuating specific station areas/buildings.

The warning of personnel in the station can be accomplished in less than . 15 minutes. (This includes vi.sitars, contractor and construction personnel).

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Nine Mile Point Annex Exelon Nuclear Notification is made by sounding the evacuation alarm, followed by an announcement over the plant PA system. (Refer to EP-CE-113, Personnel Protective Actions) b. Protected Area Evacuation

c. June 2016 A Protected Area Evacuation is confined to areas within the protected area. This evacuation requires that ERO members assemble at their designated ERF, and non-essential personnel leave the protected area and assemble at designated locations outside of the protected area. (refer to EP-CE-113).

The decision to implement a protected area evacuation is the responsibility of the Emergency Director (as appropriate).

A protected area evacuation is automatically implemented at an Alert or Site Area Emergency provided it is safe to perform. The warning of personnel in the protected area can be accomplished in less than 15 minutes. (This includes visitors, contractor and construction personnel)

Notification of a protected area evacuation is made by sounding the evacuation alarm, followed by an announcement over the plant PA system. Owner Controlled Area (OCA) Evacuation EP-CE-113 describes the evacuation of non-essential personnel from the NMPNS protected area via the Security Buildings to the Offsite Assembly Area. It also includes, as appropriate, the evacuation of individuals from the NMPNS OCA, including the Nuclear Learning Center, Energy Center, Sewage Treatment

_Facility and all other NMPNS site locations to their homes or Offsite Assembly Area The Off-site Assembly Area is normally the Oswego County Airport, Hanger K, .in Volney (Fulton).

The Emergency Director may specify alternate routes or alternate locations, if appropriate.

Personnel will use privately owned vehicles to evacuate.

Security personnel help ensure that personnel proceed to the Offsite Assembly Area .. JAFNPP is advised of the NMPNS OCA evacuation and the projected dose rates which could affect their personnel.

The decision to implement an OCA evacuation is the responsibility of the Emergency Director.

The decision is based on the declaration of a Site Area Emergency in which a radioactive release is anticipated or in progress, the declaration of a General Emergency, or upon declaration of a site evacuation by JAFNPP. Notification of an OCA evacuation is made by sounding the evacuation alarm, followed by an announcement over the station PA system. Other persons who may be in public .access areas, passing through the site, or within a NMPNS controlled location, will be notified by methods outlined in EP-CE-113.

The warning of personnel in the OCA can be NM 4-13 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear accomplished in less than 15 minutes. (This includes visitors, contractors and construction personnel)

d. Personnel Accountability To ensure that station personnel present in affected areas have been accounted for and to determine the whereabouts of personnel who have not been accounted for within the protected area, measures have been established to provide for personnel accountability.

Accountability for personnel remaining within the protected area following an accountability order is performed in accordance with EP-CE-113.

Initial accountability results in the generation of a list of missing persons within 30 minutes of an announcement to evacuate non-essential personnel or an announcement to perform accountability and/or identifying any individuals not accounted for. NOTE: The personnel accountability process is considered initiated when the announcement has been completed.

The accountability system works as follows: Personnel enter

• the protected area through security access points. Upon entering the area position their security identification proximity card (Owner Controlled Area Card) near the entrance Proximity Card Readers .. Their access is tracked by the security department computer.

In the event of an emergency, personnel within the protected area report to onsite assembly areas, or exit the protected area activating a Proximity Card Reader at the accountability area or at the protected area exit. After a number of personner have* completed this process (about 20 minutes after the announcement), a report is produced.

The information on the report yields the names of individuals who are present in the protected area, but who have not activated a Proximity Card Reader (activations are subtracted from the overall database).

The personnel accountability continues throughout the event. Search and rescue efforts begin at the completion of the initial accountability process, and are performed in accordance with EP-AA-113, Personnel Protective Actions. e. Contamination Control June 2016 The NMPNS Radiation Protection Procedures contain prov1s1ons governing the control of contamination including access control, use of protective clothing, contamination monitoring, and the release of potentially contaminated items from Restricted Areas. The requirements and guidelines of these procedures apply to contamination control during emergency conditions.

Specific onsite contamination control measures for food supplies is not necessary since no agricultural products for consumption are grown within the NMPNS exclusion area. Also, no drinking water supplies NM 4-14 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear originate onsite. Drinking water is obtained from City of Oswego water supplies or bottled water suppliers.

f. Exposure Control June 2016 The radiation exposure of station personnel during emergency operations is maintained As Low As Reasonably Achievable (ALARA), and should be maintained less than the administrative guides established in the NMPNS Radiation Protection Procedures and/or less than the Federal radiation exposure standards established in 1 OCFR20. In order to accomplish this objective, administrative means used during normal operations to minimize personnel exposure, such as Radiation Work Permits, Authorization to Exceed Radiation Exposure Guides, and ALARA measures should remain in force to the extent consistent with timely implementation of emergency measures.

If necessary actions require personnel exposures to exceed normal limits, or if normal access control and radiological work practices results in unacceptable delays, the established exposure control criteria and methods may be waived or modified at the discretion of the Shift Emergency Director or Corporate Emergency Director (as appropriate).

In the event of a declared emergency, the emergency dose limits outlined in EPA-400 have been proceduralized in EP-CE-113, Personnel Protective Actions, and may be used. EP-CE-113 also provides procedures for expeditious decision making, a reasonable consideration of relative risks, and the capacity for just-in-time authorization or emergency exposures.

Emergency dose limits are as follows: TEDE Limit (rem) Activity 5 All activities during the emergency*

10 Protecting valuable property 25 Lifesaving or protection of large populations

>25 Lifesaving or protection of large populations, only if individuals receiving exposure is a volunteer, and fully aware of risks involved.

Dosimetry equipmen,t is provided at the station as part of the normal Radiation Protection Program, and such dosimetry continues to be used during emergency situations.

Dosimetry consists of OSLDs (or equivalent) and Self-Reading Dosimeters (SRO) (or equivalent, e.g. electronic dosimeters), also known as Pocket Direct-Reading Dosimeters.

A limited number of such dosimetry are also available in emergency NM 4-15 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear supplies.

Personnel are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day during an emergency to issue and/or process dosimetry devices. The NMPNS Radiation Protection Procedures contain provisions for administration of the Facility Bioassay Program. EP-CE-113 provides guidance for accelerated or additional bioassays in the event there are individuals who are suspected of being exposed to elevated levels of airborne activity as a result of the emergency.

Radiation Protection Procedures provide for issuing, using, and reading/processing dosimetry devices and provisions for exposure record keeping. During an emergency the processing frequency is based upon the exposure rates and/or the exposure received by emergency personnel.

g. Respiratory Protection The NMPNS Radiation Protection Procedures contain prov1s1ons governing the use of respiratory protection equipment and administration of the NMPNS Respiratory Protection Program. Site specific ERO Respirator qualification requirements contained in the ERO Training and Qualification procedure take precedence over requirements contained in the Exelon Standardized Radiological Emergency Plan for Nine Mile Point Station. Exceptions to normal respiratory protection practices may be instituted by

• the Shift Emergency Director or ED (as appropriate), With the advice of the RP Director.

h. Potassium Iodide (Kl) Potassium iodide (Kl) is available for use by NMPNS employees in the event of an emergency.

Indications and when Kl should be used are contained with EP-CE-113.

4.7.2 Offsite

Protective Actions June 2016 a. Protective Actions Within Oswego County The responsibility for actions to protect offsite individuals rests with the County of Oswego, New York State Office of Emergency Management and New York State Department of Health a,s described in the New York State Radiological Emergency Preparedness Plan. The NYS Department of Health is responsible for evaluating information obtained from the NMPNS and/or other sources and recommending appropriate offsite protective actions to the OEM/OCEMO.

The principal offsite local coordinating agency for providing response to radiological emergencies in the vicinity of the NMPNS is the OCEMO. The entire 10-mile Emergency Planning Zone is contained within Oswego County.

• NM 4-16 1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear A detailed study has been conducted of the status and capacities of roads, traffic patterns and demography within the 10-mile radius Emergency Planning Zone. This study includes the estimated times to evacuate all or specific segments of the population, identifies potential problem areas and provides contingencies for dealing with adverse conditions.

The time estimates for various scenarios were performed:

1) Nighttime, normal weather; 2) Nighttime, adverse weather; 3) School in session, normal weather; 4) School in session, adverse weather. This study, "Evacuation Travel Estimates (ETE) for the James A. Fitzpatrick/Nine Mile Point Emergency Planning Zone" is contained in EP-AA-1013, Addendum 2 and was used in the development of detailed evacuation plans by the OCEMO. The ETE meets the criteria established in NUREG.;0654.

b. Oswego County Prompt Notification System The physical and administrative means for alerting and warning the population of an incident at the Nine Mile Point Nuclear Station. is described in detail in EP-CE-111 and the Oswego County Radiological Emergency Response Plan.

• The responsibility for activation of the Prompt Notification System (PNS) rests with the Chairman of the Oswego County Legislature or designee.

The Oswego County Emergency Management Office administratively activates the warning system and supplies appropriate emergency

_,. messag*es

'to the Emergency Alert System (EAS) station serving the jurisdiction in accordance with the provisions of their emergency response plans. Siren activation equipment is located at the OCEMO and the Oswego County 911 Center. The PNS consists of:

• Outdoor sirens.

• Reverse calling system (as back-up to the above).

• Emergency Alert System. This system meets NUREG-0654 and FEMA-REP-10 design and testing criteria.

System design and testing requirements are detailed in the . approved FEMA Design Report. c. Protective Action Guides and Recommendation of Protective Action Recommendations

• June 2016 Protective Action Guides (PAG's) identify protective actions to be taken prior to or following a significant release of radioactive material.

They are based on NUREG-0654/FEMA-REP-1, Rev 1, Supplement 3, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" and Frequently Asked Questions (FAQ) documented in "EPFAQ 2013-004 Final NM 4-17 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear Response".

PAGs for the "plume phase" have been established by the US Environmental Protection Agency. The numerical guides for TEDE and CDEThyroid (child) dose to the general public are listed below. The procedure used by NMPNS personnel in determining the appropriate protective action recommendation (PAR) is detailed in EP-CE-111.

PARs are reviewed prior to issuance to assess their potential impact on offsite response organization activities.

Protective Action Guidelines Early or Plume Phase . TEDE (rem) CDET (rem) Evacuate >1 >5 ' ' ' The following principles guide the formulation of PARs for the NMPNS:

• Evacuation is the preterred method of protecting the public.in the event of a significant radiological release. EPA 400 Protective Action Guidelines are used.

• NMPNS does consider sheltering due to Controlled Containment Venting with release durations of < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and dose assessments do not exceed the EPA PAGs, *

• If determined to be appropriate by New York State or Oswego County Officials, thyroid prophylaxis may be provided to the general public. NMPNS recommendations include implementation of the Kl Plan in order to be consistent with offsite plans. 4.8 Aid to Affected Personnel Procedures are established which provide for control of radiation exposure, including emergency exposure, personnel contamination, assistance to injured persons, and situations involving complications due to the presence of radiation or radioactive contamination.

June 2016 NM 4-18 EP-AA-1013 (Revision

2)

( Nine Mile Point Annex Exelon Nuclear 4.8.1 Decontamination Personnel contamination in emergency situations is controlled to the extent feasible by the normal methods of using protective clothing and surveying for contamination following the removal of such clothing:

Designated personnel decontamination areas consisting

• of showers and sinks which drain to the radwaste system, are available for either routine or emergency use at the NMPNS. Similar facilities are available at the JAFNPP. Station radiation protection personnel are instructed in the proper methods of removing minor contamination from skin surfaces.

Efforts involving significant amounts of contamination, particularly in the vicinity of facial openings, will normally be performed under the direction of Radiation Protection personnel.

Detailed methods for personnel decontamination are des.cribed

'in Radiation Protection Procedures.

Decontamination limits are detailed in station Radiation Protection Procedures.

4.8.2 First

Aid Individuals are onsite who can administer first-aid.

First aid to injured personnel is normally performed in conjunction with any necessary decontamination methods. However, if immediate treatment of the injury is vital, that treatment shall take precedence over decontamination.

This philosophy also extends to offsite emergency assistance involving radioactive contamination.

For that purpose, measures are established to ensure timely offsite medical treatment and-limiting the spread of contamination, as described in Station Annex Sections 4.8.3 and 4.8.4. 4.8.3 Medical Transportation Arrangements have been made with the Oswego County 911 Center to transport from the NMPNS to a medical treatment facility any injured personnel, including radioactively contaminated personnel and those involved in radiation exposure incidents, or a Hostile Action Based event. Copies of the agreements from faCilities/organizations which provide emergency services are contained in Station Annex Appendix 2. Ambulance emergency supplies are available for use and are stored at designated points of access to the NMPNS. 4.8.4 Medical Treatment Arrangements have been made with the Oswego Hospital (Oswego, N.Y.) for the medical treatment of patients from the NMPNS who may have a radiation exposure injury or injuries complicated by radioactive.

contamination, pr been involved in a Hostile Action Based event. The Oswego Hospital has developed a detailed procedure for handling radioactively contaminated patients or those involved in radiation exposure incidents at the NMPNS. Similar arrangements have been made with the State University of New York University Hospital at Syracuse (Syracuse, N.Y.) for medical treatment of contaminated injuries and

• significant overexposures to radiation or been .involved in a Hostile Action Based June 2016 NM 4-19 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear event. University Hospital has developed detailed procedures for handling radioactively contaminated or those patients involved in radiation exposure incidents at the NMPNS. Medical treatment facilities and on-site personnel may also contact a radiation management expert who is contracted to provide radiological treatment advice upon request. Radiation Protection Procedures describe actions ne.cessary for decontamination of emergency worker wounds, and waste disposal.

The

• Emergency Equipment Inventory procedure lists decontamination equipment available at Oswego Hospital.

This service is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day round as specified in the Letter of Agreement in Appendix 2. 4.9 Emergency Public Information and Rumor Control A telephone inquiry response program and a rumor control program has been established by NMPNS. NMPNS in conjunction with state and county governments cooperate on responses to inquiries which may occur as a result of an emergency situation at the NMPNS. Implementing procedures are contained in EP-AA-112-600, Public Information Organization.

June 2016 NM 4-20 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Class Criteria UNUSUAL Off-normal events EVENT which could indicate a potential degradation in the level of plant safety June 2016 FIGURE 4-1 ACTIVATION OF EMERGENCY ORGANIZATION

SUMMARY

OF NOTIFICATION AND RESPONSE Notifications On site Off site Onsite Personnel

1) The following

1) The following shall 1) Make prompt notifications are be notified:

off site made on an

• Oswego County notifications as-needed basis: State of New York *

• Nine Mile Point 2) Perform

• NRG Hdqtrs Fire Brigade continuing

• Damage Control assessment Teams 2) The following notifications are

• Control Room made on an 3) The following Advisory Staff as-needed basis:* actions are

• performed on an Exelon Nuclear Response Offsite Personnel

1) The following are performed on an as-needed basis:

• Provide firefighting assistance

• • Assist in rescue operations

• Provide medical transportation

• Provide medical treatment Security Force Fire units

• as-needed basis: Survey .Teams Assist in damage

• Rescue units *

• Emergency

• control

• Other Personnel

• Ambulance service Repairs Perform onsite *

• Hospital

• Administer First monitoring

• Local Area/Building Aid, and

• Institute security Evacuation

• Other medical measures treatment

• Accountability NM 4-21 EP-AA-1013 (Revision

2)

'. \ I Nine Mile Point Annex Class Criteria ALERT Events which indicate an actual degradation in the level of plant safety June 2016 FIGURE 4.1 (Cont.) ACTIVATION OF EMERGENCY ORGANIZATION

SUMMARY

OF NOTIFICATION AND RESPONSE Exelon Nuclear Notifications Response Onsite Off site Onsite Personnel Offsite Personnel

1) The following

1) The following shall 1) Make prompt offsite 1) The following are notifications are be notified:

notifications performed on an made on an

• Oswego County 2) Perform continuing as-needed basis: as-needed basis:

• State of New assessment

• Provide

• Nine Mile York 3) Staff TSC, OSC, firefighting assistance Point Fire

• NRC Hdqtrs EOF

• Assist in rescue Brigade 4) The following operations

• Damage 2) The following actions are

• Provide medical Control Teams notifications are performed on an transportation

• Control Room made on an as-needed basis:

• Provide medical Advisory Staff as-needed basis:

• Administer first aid treatment

• Security

• Fire units

• Conduct rescue

• Assist in damage Force

• Ambulance operations control

• Survey service

• Perform onsite and

• Provide onsite

• Teams

• Hospital offsite monitoring assistance as required

• Dose

• Perform offsite

• Activate primary Projection dose projections response centers Personnel

• Institute security

• Alert key

• Other measures personnel Personnel

• Fight fire

• Conduct * (as

• Perform emergency confirmatory dose necessary) repairs projections

• NotifyTSC,

• Protected Area

• Maintain OSC, and EOF Evacuation emergency personnel

• Accountability communications NM 4-22 EP-AA-1013 (Revision

2)

Nine Mile Point Annex .Class Criteria SITE AREA Events which involve EMERGENCY actual or likely major failures of plant functions needed for protection of the public June 2016 FIGURE 4.1 (Cont.) ACTIVATION OF EMERGENCY ORGANIZATION

SUMMARY

OF NOTIFICATION AND RESPONSE Exelon Nuclear Notifications Response Onsite . Offsite Onsite Personnel Offsite Personnel t) The following 1') The following shall 1) Make prompt offsite 1) The following are notifications be notified:

notifications performed on an made on an

• Oswego County 2) Perform continuing as-needed basis: as-needed basis:

• State of New assessment

• Provide firefighting . . Nine Mile York 3) Staff TSC, OSC, and assistance Point Fire

• NRC Hdqtrs EOF

• Assist in rescue Brigade 4) Accountability operations

• Damage 2) The following

5) The following actions

• Provide medical Control Teams

• notifications are are performed on an transportation

• Control Room made on an as-needed basis:

• Provide medical Advisory Staff as-needed basis:

• Administer first aid treatment

• Security

• Fire units

• Conduct rescue

• Assist in damage control Force

• Rescue units operations

• Provide onsite

• Survey

• Ambulance

• Perform onsite and assistance as required Teams service offsite monitoring

• Activate primary

• Dose

• Hospital

• Perform offsite dose response centers Projection projections

• Alert key personnel to Personnel

• Institute security standby

• Other measures

• Conduct confirmatory Personnel (as

• Firefighting dose projections necessary)

• Emergency Repairs

• Maintain emergency

• NotifyTSC,

• Recommend offsite communications . OSC, and EOF protective actions

• Place public notification personnel

• Augment resources system in standby status

• Protected Area

• Implement appropriate Evacuation near site protective

• Implement Exclusion measures Area Evacuation NM 4-23 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Class Criteria GENERAL Events which involve EMERGENCY actual or imminent substantial core degradation or melting with potential for loss of containment integrity June 2016 FIGURE4.1 (Cont.) ACTIVATION OF EMERGENCY ORGANIZATION

SUMMARY

OF NOTIFICATION-AND RESPONSE Exelon Nuclear Notifications Response Onsite Offsite Onsite Personnel Offsite Personnel

1) The following

1) The following shall 1) Make prompt offsite 1 )The following are performed notifications are be notified:

notifications on an as-needed basis: made on an

• Oswego County 2) Perform continuing

• Provide firefighting as-.needed basis:

• State of New assessment assistance

• Nine Mile York 3) Staff TSC, OSC, and

• Assist in rescue Point Fire

• NRG Hdqtrs EOF operations Brigade. 4) Exclusion Area

• Provide medical

• Damage 2) The following Evacuation transportation Control Teams notifications are 5) Accountability

• Provide medical

• Control Room made on an 6) Recommend offsite treatment Advisory Staff as-needed basis: protective actions

• Assist in damage control

• Security

• Fire units 7) The following

• Provide onsite Force

• Rescue units actions are assistance as required

• Survey

• Ambulance performed on an

• Activate primary Teams service as-needed basis: response centers

• Dose Hospital

• Administer first aid Alert key personnel to *

• Projection

• Conduct rescue standby Personnel operations

• Conduct confirmatory

• Other

• Perform onsite and dose projections Personnel (as offsite monitoring

• Maintain emergency . necessary)

• Perform offsite communications

• Notify TSC, dose projections

• Implement appropriate OSC and EOF

• Institute security protective measures personnel measures

• Mobilize emergency

• Firefighting response personnel

• Emergency Repairs Continuously evaluate *

• Augment resources dose projections

• Place public notification system in standby status NM 4-24 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear FIGURE 4.2-EMERGENCY ORGANIZATION INTERFACES (INITIAL NOTIFICATION)

Nuclear learning Center -----NMPNS Site Energy Center (if occupied)

---

NMPNS Site NMPNS Nuclear Security Staff NMPNS Security Building Notify County Agencies Oswego County Emergency Management Office _

Oswego County Bldg Fulton, NY New York State Emergency Operations Center June 2016 Albany, NY US DOE FRMAPTeam Brookhaven NY NMPNS Site Personnel Call List -----Off site Emergency Reponse Organization Notification System JAFNPP Plant ------Control Room 0 <11 QJ :§ 5 ..c 0 a. ..c <11 tJ ] w a:: Oswego Cnty NMPNS Staff Fire Control & Warning Point Contractors

---

Oswego, NY NMPNS Site NOTIFY STATE AGENCIES NY State Warning Point ------Albany, NY NMPNS Operators and SM/ ED Telephone General Electric Company Tel. 0 § .., ..c 0 a. ..c <11 Vl Cii w USN RC NRR NMPNS Control Room(s) ( Not Staffecj Technical Support Center ------------

NMPNS Site ( Not Staffecj Emergency Operations Facility and Recovery Center -----------

Fulton, NY Tel. USNRC Resident Inspector White MD NMPNS Site San Jose, CA ( Not Staffecj Operations Support Center """"------------

NMPNS Unitl Admin Bldg lnstitue for Nuclear Power Operations Atlanta, GA Oswego River Hydro Stations within 10-mile EPZ Emergency Reponse Organization Notification S stem CE Personnel American Nuclear Insurers Farmington CT

• Active at the Alert, SAE, and/or GE NM 4-25 EP-AA-1013 (Revision 2}_

Nine Mile Point Annex Exelon Nuclear .,, . . Q, "O " a:' FIGURE 4.3 EMERGENCY ORGANIZATION INTERFACES (AFTER EMERGENCY FACILITIES STAFFED) (Supersedes Standard Plan EP-AA-1000, Figures F-1 & F-2) Radios JAFNPP Security securi!Y -Bldg.

USCG Station USCG Vessel 1--Osw0g0, -"?] r-Water -.Q

_ _, §' ERPAs -g "' a: Sheriff's Lake Patrol r-ERPAs JAFNPP Operations ContrOi -Room I***-----*****

• Hotline**********************************--**-**--*-

---

, Hotline ,----Other Police Sheriff's Department , *

• JAFNPP Security Bldg. NMPNS Operations and Selected Personnel General Electric Company

"' o. :g. a:' NMPNS Security Bldg. 1-------------

Traffic Control Points & Road Blocks Sheriff's Office 1-------------

NMPNS Control Room(s)

........ II Technical Support _ __ Center TSC Emergency Director NMPNS Technical Staff Q) c: 0 .<:: c. Q) San Jose, CA Institute for Nuclear Power Operations r-----T------------Q) c: 0 .<:: c. Q) Atlanta, GA *I---------

_...._ NRG Technical Staff [AiL_ Oswego, NY NMPNS Security Radio, Telephone Q) c: 0 .<:: c. Q) oi c: NMPNS Unit 1 Admin. Bldg. Operations Support Center ,__ ___ ,_ _____ ------NMPNS Unit 1 Admin. Bldg. :r: -----------l------1 Q) c: 0 .<:: c. Q) Qi f--Oswego River Hydro Stations NMPNS Security Bldg. en z w Q) c: 0 HOTLINE§_

Q) oi .!: '5 :r: .,,en iTI r----f------------

within the 10-mile EPZ Survey Teams Radios NMPNS/JAFNPP Radios OCEMO NYSDOH 1 *'. Emergency Operations I

_

-_lf . J Volney, NY

• USN RC NRA Tel USN RC Region I US DOE Telephone I Tel ----------

-!---!------------r----Joint* Information Center White Flint, MD NMPNS Site "' 0' :c ' fl.'

_____________________

--<,J Telephone

> Telephone/radi"-o

__, Telephone Telephone/ra_d_io

_ _, June 2016 NM 4-26 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear Section 5: Emergency Facilities and Equipment Emergency facilities, equipment and communications are provided to ensure the capabilities for the prompt, efficient assessment and control of situations exists. Access to emergency facilities and equipment is governed by EPIP-EPP-14.

5.1 Emergency

Response Facilities

5.1.1 Control

Room(s) The Unit 1 and Unit 2 Control Rooms are equipped with indications and controls for major plant systems. A portion, of the indications for each Unit is the Safety Parameter Display System (SPDS). The purpose of SPDS is to display plant parameters in the Control Room(s) and TSC. The type and number of indications may be changed if future requirements change. Indications assessment aids interrelated with meteorological and radiological dose calculation data are also provided, as well as access to emergency communications systems. The Control Rooms are designed for continuous occupancy following the most limiting accident.

5.1.2 Technical

Support Center (TSC). The NMPNS TSC is a facility located in the Unit 1 Administration Building at floor elevation 248.. This is where station management and technical personnel can ; * ** access technical data and displays necessary to assist Control Room personnel during emergency conditions.

As part of their assistance, TSC personnel monitor -station parameters to-ensure-prompt corrective and mitigating actions are taken. The TSC is in close proximity to the Unit 1 and Unit 2 Control Rooms and has similar radiological habitability as the Control Rooms under accident conditions.

The TSC provides access to site. document control computer files which can provide any permanent plant record, as described in ANSI N45.2.9-1974,.

including as-built drawings.

In addition, the TSC document control facility has copies o( the NMPNS Emergency Plan and Implementing Procedures, Final Safety Analysis Reports, Technical Specifications, Administrative Procedures, Operating Procedures and other documents which may be used during an emergency.

Space has been provided for five-(5) NRG personnel.

5.1.3 Operations

Support Center (OSC) The OSC is an on-site assembly area at NMPNS to which designated station personnel report for accountability and special assignment.

It is located in the Unit 1 Administration Building and includes the 261' Maintenance and Electrical Shops, Locker Rooms, Storeroom, and 248' Radiation Protection offices, and the Contractor staging area. The OSC Core Area is located adjacent to the TSC Core Area and within the TSC envelope on elevation 248'. The OSC has sufficient space to assemble station ERO personnel, and maintain them immediately available for assignment.

After activation, the ERO personnel may June 2016 NM 5-1 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear be instructed to resume duties or may be assigned new duties in support of emergency operations.

The OSC has installed and readily available communications equipment with which to control OSC related activities.

Emergency cabinets with supplies and equipment for various teams (e.g., survey equipment, protective clothing, respiratory protection equipment, radios etc.) are located near the OSC. The First Aid Room and a personnel decontamination room are located nearby with appropriate supplies.

In addition, the Maintenance Shops can be used to obtain necessary equipment and tools for damage control teams. A listing of OSC emergency equipment is included in the Emergency Equipment Inventory procedure and is representative of equipment specified in NUREG 0654 to support OSC operations.

5.1.4 Emergency

Operations Facility (EOF) The EOF is a Co-located Licensee (NMP and JAF) controlled and operated emergency response facility located approximately 12 miles from the reactor site on County Route 176, just outside Fulton, NY, adjacent to the Oswego County Airport. The purpose of the EOF is to provide continuous coordination with local, State and Federal agencies and to provide evaluation of NMPNS activities during an emergency.

Space is provided so that Federal, State and local response agencies can monitor and coordinate with the utility response activities.

from this location.

Utility recovery operations are also handled at this facility.

It is expected that manufacturer and vendor representatives may require twenty-four (24) hours to arrive following notification.

Federal, State and County Officials could arrive at any time following notification.

The EOF has facilities and capabilities for the following:

June 2016

• Management of the overall NMP emergency response

• Coordination of radiological and environmental assessment

• Determination of Protective Action Recommendations (PAR)

• Notification of offsite agencies

• Coordination of event, plant and response information provided to public information staff for dissemination to the media and public

• Staffing within 60 minutes and activating the facility within the same time requirement or as soon as possible thereafter

• Coordination of emergency response activities with Federal, State and local agencies

• Obtaining and displaying key plant data and radiological information for NMP Units 1 and 2 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear

• Analyzing plant technical information and providing technical briefings on event conditions and prognosis to staff and offsite agency responders for NMP Units 1 and 2

• Effectively responding to and coordinating response efforts for events occurring simultaneously at more than one site for Co-located licensees . 5.1.5 Security Tactical Operations Center (STOC) The STOC is a security command center that may be activated during a safeguards contingency or site emergency to ensure effective nuclear security program direction under unusual conditions.

The STOC is located on the second floor of the west security annex building.

5.1.6 Joint

Information Center (JIC) The JIC is located near the Oswego County Airport, on County Route 176 in the Town of Volney, New York approximately 12 miles from the site. The function of this facility is to provide a single point of contact for disseminating information to the public. This dedicated facility has a large open area, used for briefings, and numerous small offices with telephones which can be used by news media personnel.

A listing of equipment necessary to perform this function is in the Emergency Equipment Inventory procedure.

The JIC is activated for an -Alert, Site Area, or General Emergency.

5.1.7 Alternative

Facility The Alternative Facility maintains the capability for staging the TSC/OSC emergency response organization personnel in the event of a hostile action. This . alternative facility has the capability for communications with the emergency operations facility, control room, and plant security and the capability for engineering assessment activities, including damage control team planning and preparation.

Consistent with NRC EPl=AQ No. 2013-005, the EOF will satisfy the offsite notification responsibilities for the Alternative Facility.

The Alternative Facility is located* at the Nine Mile/Fitzpatrick EOF on County Route 176, just outside Fulton, NY, adjacent to the Oswego County Airport. 5.1.8 Oswego County Emergency Operations Center (OCEOC) The OCEOC is located in the Emergency Management Office, County Branch Building, Fulton, N.Y. The County Warning Point is located at Oswego County 911 Center. Communications are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day at this warning point. Upon activation by the Oswego County Emergency Management Office, communications, planning, and coordination personnel become available at the OCEOC. A representative from NMPNS may be dispatched to this facility to act *as liaison between the County and the site for a Site Area Emergency or General Emergency.

June 2016 NM 5-3 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear 5.1.9 State Emergency Operations Center (SEOC) The SEOC is located in the substructure of the Public Security Building, State Office Building Campus, Albany, New York. The State Warning Point communication systems and the State Emergency Management Office are also located in this center. Communication systems operate on an around the clock basis. State direction and control of emergency operations is conducted from the SEOC. Field operations are implemented through the State Emergency Management Office, Lake District Office, in Newark, N.Y. Upon activation, planning and coordination personnel become available at the SEOC. A representative from NMPNS may be dispatched to this facility to act as liaison between the State and the site for a Site Area Emergency or General Emergency.

5.2 Communication

Systems The Nine Mile Point communication capabilities include multiple systems and redundancies which ensure the performance of vital functions in transmitting and receiving information throughout the course of an emergency.

Multiple modes and paths are available for necessary emergency communications.

Typical communications capabilities and the interfaces between expected supporting agencies.

are provided in Figure 4.2 and Figure 4.3. Systems available at the various emergency facility locations or available for use by response organizations are: 5.2.1 Telephone Systems The telephone system at .NMPNS consists of an in plant dial system with connections to the local telephone system. The main. emergency response facilities or organizations which have telephones are listed below:

• Control Rooms

• Technical Support Center

• Operations Support Center

• Emergency Operations Facility

• Security Tactical Operations .Center

• Joint Information Center

• Oswego County Emergency Operations Center

• Oswego County Warning Point (Oswego County 911 Center)

• Oswego Hospital

• University Hospital

• New York State Warning Point. June 2016 NM5-4 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear

• New York State Emergency Operations Center

• NRC

• Other Emergency Response Organizations 5.2.2 NRC Emergency Notification System (ENS) Hotline The ENS is a separate and completely independent telephone system which is part of the Federal Telephone System from the local telephone system. It is used to provide initial notification of an emergency and continuing emergency information.

NMPNS facilities at which these telephones are located include:

• Control Rooms

• Technical Support Center

• Emergency Operations Facility 5.2.3 Radiological Emergency Communications System (RECS) The RECS is a separate and completely independent system from the local telephone system and is similar to the ENS. This system is used to provide initial notification of an emergency and continuing emergency information to New York State and Oswego County Authorities.

Facilities at which these telephones are located include:'

• Control Rooms

• Technical Support Center

• Emergency Operations Facility

• JAFNPP Control Room, TSC

• Oswego County Warning Point (Oswego County 911 Center)

• Oswego County Emergency Operations Center

• NYS Warning Point

• NYS Alternate Warning Point (State Police Communications Center)

• NYS Emergency Operations Center

• NYS Department of Health (Headquarters in Albany) 5.2.4 NRC Health Physics Network (HPN) The HPN telephone system is also a part of the Federal Telephone System. It is primarily used to transmit health physics (radiological) data to the NRC during an emergency.

NMPNS facilitie$

at which these HPN telephones are located include:

• Technical Support Center

• Emergency Operations Facility June 2016 NM 5-5 .EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 5.2.5 Other Dedicated Telephone Line Systems Dedicated telephone systems provide direct communication between the points shown. As appropriate these points are linked by one or more dedicated lines. They can be used in any situation but are primarily for emergency use. These systems include:

• Control Rooms to Technical Support Center

• Technical Support Center to Operations Support Center

• Emergency Operations Facility to Technical Support Center 5.2.6 Public Address and Page System This system (commonly referred to as the GAltronics) is located in the various NMPNS facilities and includes outdoor speakers.

It is a communications system which can be used by all station personnel.

Public Address Systems (other than GAltronics) are also located in the TSC, JIG, OSC and EOF. The system in the TSC allows announcements to be heard throughout the TSC and the OSC Core Area. The EOF and JIG systems allow announcements to be heard throughout the EOF or JIG. The OSC PA System permits announcements to be made throughout the OSC. 5.2.7 Radio Systems

• NMPNS has various radio . frequencies assigned for use. These frequencies include off-site and in-plant repeater channels, NMPNS channels and Oswego . County public safety frequencies; All radio systems used for emergencies have significant redundancies (that is, separate power sources, antennas, feed lines, and consoles) that *preclude loss of radio capability during emergencies.

All NMPNS emergency facilities are equipped with consoles that allow use of all frequencies that may be used for emergencies.

Thus, all emergency facilities (including.

the Control Rooms) are capable of contacting radio-equipped

• personnel within the plant and the 10-mile EPZ, and with Oswego County 911 Center and County emergency facilities.

Additionally, all ambulances that service NMPNS have direct communication with Oswego and University Hospitals.

NMPNS utilizes a telephone activated notification system to notify ERO personnel.

5.2.8 Emergency

Response Data System (EROS) A computer system that collects a variety of information regarding plant operating parameters, meteorological data, effluent information and other data, and transmits it to the NRG. June 2016 NM 5-6 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 5.3 Assessment Facilities and Systems 5.3.1 Onsite Assessment Facilities

• a. Initially following an emergency, the primary on-site emergency assessment facility is the affected unit .Control Room. This assessment function is transferred to the TSC after that on-site facility has been activated.

These facilities are described in the Station Annex Section 5.1.1. b. If background radiation levels permit, post-accident radiological samples may be analyzed on-site in the NMPNS Chemistry laboratory located at Unit 1 or the Unit 2 Chemistry Counting Room located at Unit 2. These in-plant laboratories have full computer/gamma isotopic, gross beta and gross alpha analysis*

capabilities.

• These facilities are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day seven days per week as needed. 5.3.2 Offsite Assessment Facility a. The offsite emergency assessment facility is the EOF. This facility is described .in Station Annex, Section 5.1 .4. b. NMPNS maintains an agreement with JAFNPP to have environmental samples evaluated by a vendor maintained by JAFNPP. Post-accident radiological samples can be sent off-site to the JAFNPP vendor in the event that the NMPNS in-plant laboratory is unavailable for any reason. If the JAFNPP vendor cannot perform the analyses or cannot handle the number of analyses required, samples can be sent to the Calvert Cliffs Nuclear Plant laboratory, located in Lusby Maryland.

This laboratory also has similar capabilities to the NMPNS Health Physics laboratory.

These facilities are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day seven days per week as needed. 5.3.3 Assessment Systems a. Plant Process Computer (PPC) and Safety Parameter Display System (SPDS) The PPC and SPDS provide historical and real plant data via displays and hard-copy devices that are located in the Control Rooms, TSC, and EOF. Both systems are designed to assist emergency response staff and Control Room operators in the decision making process during normal and abnormal plant conditions.

These systems are described in greater detail in the Unit 1 UFSAR and Unit 2 USAR. b. Radiological Monitoring June 2016 1) Plant Radiation Monitoring Systems These systems, consisting of process and area radiation monitors, provide accident assessment by measuring and recording radiation levels and radioactivity concentrations at strategically selected NM 5-7 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear June 2016 locations throughout the plant. Local alarm functions associated with the monitors provide for plant personnel protection.

A listing of these monitors is contained in Volume 3 Section XII Unit 1 UFSAR and Unit 2 USAR Chapter 12.3. 2) Onsite Radiological Monitoring System There are 6 environmental radiological monitoring stations which surround the site or are located within the site boundary.

Onsite monitoring stations surround the plant as specified in the Offsite Dose Calculation Manual (ODCM) *and are designed to continuously collect* particulate and iodine air samples. The capability to collect precipitation samples is also available.

Environmental Thermoluminecent Dosimeters (TLD), are located at approximately 70 stations, both onsite and offsite. The TLD's are collected, and evaluated quarterly.

The TLD stations (on-site and off-site) exceed the NRG Radiological Assessment Branch Technical Position in total number and quality of monitors.

In addition to the environmental TLD monitoring,*

a group of Optically Stimulated Luminescent Dosimeters (OSLO) called Emergency Preparedness OSLD's and 1 OCFR20 OSLD's have been placed in various locations around the site and the county. These OSLD's are evaluated during or after an emergency situation has occurred and as part of the facilities 1 OCFR20 program. The emergency OSLD's and 1 OCFR20 OSLD's are also renewed quarterly.

3) Containment High-Range Radiation Monitor Unit 1 is equipped with two, containment high-range radiation monitors with a gamma detection range of .1 o 0 to 10 8 R/hr. Unit 2 is equipped with four high gamma detectors capable of monitoring radiation in the range of 1 O to 10 7 R/hr. The purpose of these monitors is to detect gross fuel failure. 4) Off site Radiological Monitoring Systems There are approximately nine offsite radiological monitoring stations.

These stations surround the plant and are described in the ODCM. Each of these monitoring stations is designed to continuously collect particulate and iodine air samples, and each has the capability for collecting precipitation samples, if required.

Four (4) of the monitoring stations are along the site boundary and have radiation monitors.

The radiation monitors are used to measure dose rates resulting from possible plume releases of radioactive material from the plant. Environmental Thermoluminecent Dosimeters (TLD) and Optically Stimulated Luminescent Dosimeters (OSLO) are as described in Section b.2 above. NM 5-8 EP-M-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 5) Emergency Radiological Survey Teams In addition to the monitoring capabilities provided by the fixed assessment systems, suniey teams may be dispatched on-site and off-site to take direct radiation readings and collect samples for field or laboratory evaluation in the field. Survey team members are notified through normal station communications systems, the standard call-out procedure by telephone or radio activated beepers. Survey teams can be deployed within approximately 60 minutes of notification.

Direction of the survey teams may be initiated by the affected control room, but is normally transferred to the TSC when it is activated.

Following activation of the EOF, direction of the teams, including receipt_ and analysis of data is transferred to this facility.

Monitoring information from the State and/or County may also be available and would be

c. Containment Monitors June 2016 Containment monitor data may be used to determine the extent of core d.amage. EPIP-EPP-09 provides the required implementation steps to determine the extent of core damage, using information obtained from these monitors.

1) Containment High-Range Radiation Monitor See Station Annex, Section 5.3.3.b.3.

2) . Containment Pressure Monitor Continuous indication and recording of containment pressure from -5 psig to 250 psig is provided in the Unit 1 Control Room for each pressure transmitter.

The Unit 2 drywall pressure monitors provide continuous indication and recording of containment pressure from -5 psig to 150 psig in the Unit 2 Control Room. 3) Containment Water Level Monitor Continuous indication and recording of the torus pool water level from 15 inches above the bottom of the torus to 3 feet, 8.5 inches above the normal water level of the torus pool is provided in the Unit 1 Control Room for each transmitter.

The Unit 2 suppression pool water level from the 192' level to the 217' level is continuously indicated and recorded in the Unit 2 Control Room. 4) Containment Hydrogen Monitor Redundant continuous indication of hydrogen concentration in the containment is provided in the control room over the range from 0 NM 5-9 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear to 20% for Unit 1 and over the range from 0 to 30% for Unit 2 by the Hr02 Sampling System. d. Sampling Systems Data obtained from sampling systems may be used to determine the extent of core damage. EPIP-EPP-09 provides the required implementation steps to determine the extent of core damage, using information obtained from these systems. 1) Plant *Effluent Monitoring System The Unit 1 OffGas Effluent Stack Monitoring Systems (OGESMS) performs a continuous analysis of stack gross radioactivity via an isokinetic probe. Particulate and iodine samples are collected by standard cartridges which are manually inserted into the main sample lines, allowed to collect samples for a specified period of time, removed from the lines and analyzed.

The Unit 2 Wide Range Gaseous Monitoring Systems (WRGMS) performs a continuous analysis of stack and vent gross radioactivity via isokinetic probes. Particulate and iodine samples are collected by standard cartridges which are manually inserted into the stack .and vent main sample lines, allowed to collect samples for a specified period of time, removed from the lines and analyzed.

2) In-Plant Iodine Instrumentation Portable instrumentation is used for the sampling of in-plant iodine levels. Samples are taken on silver zeolite or TEDA impregnated charcoal sampling cartridges.

The charcoal sample cartridges are then taken to the Station Laboratory where they are purged to remove entrapped noble gases and then analyzed.

The silver zeolite cartridges have an iodine retention efficieqcy in excess of 99% while retaining only trace amounts of noble gases and thus do not have to be purged prior to analysis.

3) Grab Samples A grab sample can be taken for determination of liquid or gaseous activity.

e. Fire Protection Systems June 2016 Fire protection at each Unit is provided by a complete network of fire detection, suppression and extinguishing systems. These systems are activated by a variety of thermal and products of combustion fire detection devices located throughout the station. At present the fire zones cover the turbine generator unit, vital areas and general station areas. Station Operating Procedures identify fire detectors and their locations.

NM 5-10 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear f. Geophysical Phenomena Monitoring System Monitors are provided to detect and record natural phenomena events which could result in plant damage due to ground motion or structural vibration and stress. Backup information can be obtained from: the other NMPNS Unit, the JAFNPP which also has seismic detectors; a contracted weather service; a local National Weather Service station, etc. Hydrologic conditions (e.g., floods, low water, hurricanes) would be observed by the shift operating crew and/or information would be provided by the U.S. Coast Guard, a contracted weather service or a local National Weather Service station. g. Meteorological Measuring System Wind speed, wind direction and temperature sensors are installed on a suitably isolated tower at elevations of approximately 30, 100 and 200 feet

• above plant grade. The data collected by these sensors are telemetered to the NMPNS Unit 1 and Unit 2 Control Rooms and are designed to be continuously recorded on strip charts in the Control Rooms and the TSC (wind speed/direction only). In addition to this primary tower, a single level, 90-feet tall, backup tower and a single level, 30-feet tall inland tower are maintained as alternate sources of meteorological data. This data is also available in the TSC and the EOF. Meteorological data can also pe supplied by local weather stations.

Regional National Weather Service offices may provide access to their meteorological data, as required.

Other sources include several supplemental towers located in the general area outside the 10-mile EPZ. Wind Roses may be obtained from Unit 1 UFSAR or Unit 2 USAR. . 5.4 Protective Facilities Onsite facilities and designated assembly locations are provided which ensure adequate radiological protection for personnel assigned to emergency duties in the plant, and for the accommodation of other personnel evacuated from areas that may be affected by radiation and/or airborne radioactivity.

5.4.1 Control

Rooms In addition to serving as the first line control for emergency situations, each Unit Control Room has the following features which provide protection for personnel who have control room duties throughout the course of any emergency:

a. Adequate shielding by concrete walls to permit continuous occupancy under severe accident conditions.

b. An independent emergency air supply system, equipped with absolute and activated charcoal .filters.

June 2016 NM 5-11 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear c. Continuous monitoring of radiation levels in the Control Room and throughout the plant by the Area Radiation Monitors (ARM) system, with readout in the Control Rooms. d. Emergency lighting and power, supplied by a 125 V de System. e. Communications systems, as described in Station Annex Section 5.2. Additional details regarding the design and inherent protective capabilities of each Unit's Control Room are discussed in the respective Nine Mile Point Nuclear Station UFSAR/USAR as appropriate.

5.4.2 Technical

Support Center (TSC) The TSC serves as the long range emergency control facility for the station. To allow for long-term human occupancy during an emergency situation, the following personnel protective features have been incorporated into the design: a. . Adequate shielding to permit continuous long term occupancy under severe accident conditions.

b. An independent emergency air supply system, equipped with absolute and activated charcoal filters. c. Emergency lighting and reliable power supplies.

d. Communications

$ystems as described in Station Annex Section 5.2. e. Continuous monitoring of radiation and airborne activity levels in the TSC. 5.4.3 Onsite Assembly Areas/ Evacuation Assembly Areas Specific locations at the station are designated for assembly of personnel in the event of the need to account for all personnel within the protected area. These areas provide space to accommodate personnel who may be at the station. They are located on the basis of logical access routes and physical separation from likely areas of radiation and/or airborne radioactivity.

Other areas outside of the protected area but within the exclusion area are designated locations (evacuation assembly areas) to which non-essential personnel are required to report during a Protected Area Evacuation.

The purpose of these locations is to provide a location close to the protected area to allow for rapid return of personnel following termination of the emergency, yet outside of the protected area and away from any potential unnecessary exposure.

Upon announcement of a Protected Area Evacuation, personnel in the protected area, including office .personnel and visitors, evacuate immediately to the designated Evacuation Assembly Areas. As they exit through the security access, they card out. The Control Room Operators remain in the Control Rooms and other operators on-site (on-shift, relief or operators in training) report to the OSC. TSC and OSC staff card in and remain in their respective emergency facilities, which are designated as assembly areas. Designated security personnel assemble at the Main Security Building, and the Alternate Access Point. June 2016 NM 5-12 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Adequate shelter from inclement weather is provided.

Onsite Assembly Areas are described in procedure EP-CE-113.

The responsibility to ensure that a visitor evacuates to the proper area rests with the individual accompanying the visitor at the time evacuation occurs. 5.4.4 Off-site Assembly Area The. purpose of the Off-site Assembly Area (OAA) is to provide a location for the assembly, monitoring, and, if necessary, decontamination of the personnel who leave the site following an Exclusion Area Evacuation.

The Oswego County Airport, Hanger K; in Volney, New York, is designated as the Off-site Assembly Area. This facility is located approximately 12 miles from the site. Personnel may be monitored for contamination upon arrival at OAA. Decontamination will be done in accordance with normal station procedures.

Supplies are available .at the OAA such as: protective clothing and decontamination supplies.

Detailed personnel and equipment decontamination methods, and techniques for removal of radioiodine and other particulates are contained in station Radiation Protection procedures.

5.5 On-Site First Aid and Medical Facilities A first aid treatment facility, equipped with industrial first aid supplies, is located near the Locker Rooms in the Unit 1 Administration Building.

The Site Medical Facility is also equipped with industrial first aid supplies and is located in the P Building at Unit* 2. A listing of first aid equipment that is located within the Protected Area is contained in Emergency Equipment inventory procedures.

Additional medical equipment is provided at designated locations throughout the station. 5.6 Decontamination Facilities for Emergency Personnel Personnel decontamination rooms are located in the Unit 1 Administration Building and the Unit 2 Control Building.

These are the primary facilities for decontaminating emergency personnel.

If these facilities are unavailable for any . reason, emergency personnel may be decontaminated at the JAFNPP facility.

The liquid waste from each of these decontamination facilities is disposed of via the respective plants liquid radwaste system. Solid waste is disposed of in containers provided for this purpose located at each decontamination facility.

If additional decontamination facilities are necessary, the station locker room shower facilities can be used on an interim basis for performing decontamination, even though they do not drain to radwaste.

• June 2016 NM 5-13. EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 5. 7 Damage Control Equipment Damage control equipment consists of normal and special purpose tools and devices used for emergency maintenance functions throughout the station. Personnel assigned to damage control teams are cognizant of the locations of specific equipment which may be required in an emergency.

The Rescue Cabinet inventory, Damage Control Tool Box inventory and shoring materials, including scaffolding (stored in the Unit 1 Turbine Building), and various shapes

• of angle iron, plate and bar stock are available through the warehouse.

Heavy duty and specialized equipment, and trained equipment operators, can be provided if necessary.

5.8

• Emergency Vehicles NMPNS has access to helicopters and fixed wing aircraft.

Their use can be requested to assist in an emergency response effort through the Emergency Operations Facility (EOF). The EOF also coordinates the use of helicopters operated by the New York State Police, Oswego County and Onondaga County. Also, keys for selected site vehicles are maintained in Control Rooms, and the osc. 5.8 CATEGORIES OF EMERGENCY EQUIPMENT

5.8.1 Equipment

available for use during emergencies is described in the Emergency Equipment Inventory procedure.

Equipment/Facilities important to maintaining

• Emergency Preparedness is detailed in EP-CE-121-1004, Nine Mile Point Equipment Matrix.

• 5.8.2 *Equipment for use in coping with a radiation emergency which would necessitate site evacuation is stored in a number of strategic locations:

the Technical Support Center, the Control Room, the Operational Support Center, and the EOF. Sufficient variety and quantities of equipment are stored in each location:

Dedicated equipment is inventoried to insure it is available, using the equipment list in the Emergency Equipment Inventory procedure. Equipment includes radiation monitors, protective breathing equipment, communications and data retrieval capability, dosimetry and protective clothing.

5.8.3 The Operations Support Center contains equipment for general use, as well as equipment for specific survey team use. The general use equipment includes communications equipment, reference material, survey instruments, dosimeters, counting equipment, sampling equipment, protective clothing, and decontamination equipment.

June 2016 NM 5-14 EP-AA-1013 (Revision

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• Nine Mile Point Annex Exelon Nuclear Section 6: Maintaining Emergency Preparedness A concept of in-depth preparedness is employed regarding the Nine Mile Point Nuclear Station Emergency Preparedness Program. This concept is accomplished through training, emergency drills and exercises.

Personnel are trained to provide an in-depth response capability for required actions in an emergency situation.

Similarly, members of the population within the emergency planning zone. are informed as to their expected response to an emergency at *the Nine Mile Point Nuclear Station. This section of the Station Annex includes the means to achieve and maintain emergency preparedness and to ensure maintenance of an effective emergency program. 6.1 Organizational Preparedness 6.1 .1 Training The Site Training Director is responsible for the Emergency Preparedness Training and Qualification Program provided to ERO personnel in accredited programs (Op.erations, Maintenance, Radiation Protection, Engineering and Chemistry).

• The Emergency Preparedness Manager is responsible for maintenance of all non-accredited ERO personnel position specific qualifications.

Training requirements for ERO personnel are detailed in the ERO Training and Qualification procedure.

• The NMP Senior Nuclear Site Communications Specialist coordinates with the Oswego County Emergency Management Office . to schedule public news organization training, administer the training and provide records of the activities to the Emergency Preparedness*

Department for record retention.

The Director, Oswego County Emergency Office is responsible for planning and conducting emergency preparedness training for emergency response personnel in Oswego County. Emergency training includes, as appropriate:

a. Unescorted personnel entering or working within the Nine Mile Point Nuclear Station Protected Area receive, as a minimum, orientation regarding individual employee responsibilities, response to station alarms, the use of applicable station communications systems and requirements associated with personnel accountability and evacuations

.. . b.

• Temporary work force personnel onsite are informed of their emergency response in accordance with applicable procedures for evacuations, and accountability.

c. Personnel assigned to the NMPNS ERO with specific emergency preparedness duties and responsibilities receive specialized training for June 2016 NM 6-1 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear their respective assignments.

Station Annex Figure 6.2 delineates which personnel receive specialized training, the type of training and the required frequency of such training.

d. The New York State Office of Emergency Management develops, conducts, and coordinates a training program for State personnel and may assist the County in developing training policy for disaster operational readiness.

The Oswego County Emergency Management Director is

• responsible for planning and conducting emergency preparedness training of county emergency response personnel.

The New York State Division of Military and Naval Affairs, has the responsibility for a statewide warning and communication system and may be requested to assist State and local agencies in specific disasters.

e. The key personnel from the emergency/disaster services organizations listed below are invited, on an annual basis, to participate in a training program. The program, as appropriate, identifies interfaces between the NMPNS emergency organizations and the offsite (i.e., State, County and Federal) emergency organizations.

The program shall include a review of appropriate sections of the NMPNS Station Annex and appropriate Emergency Plan Implementing Procedures including:

classification of emergencies; emergency action levels; reporting requirements; assessment, protective and mitigative actions; and communications networks.

The organizations invited include but are not limited to: 1) New York State Office of Emergency Management

• 2) New York State Department of Health 3) Oswego County Emergency Management Office f. NMPNS provides for training to local offsite support organizations as specified in respective letters of agreement and as required to ensure a

• high state of emergency preparedness and* response capability of these organizations.

The local organizations that may provide onsite emergency assistance are encouraged to *become familiar with the Nine Mile Point Nuclear Station (including the physical plant layout, site access arrangements and procedures, and key station personnel), and are invited to attend emergenQy preparedness training conducted by NMPNS. Such training is provided annually to the appropriate organizations and individuals:

June 2016 1) The local fire, local law enforcement and ambulance companies are invited to participate in a training program that may include but is not limited to: i. Interface with the NMPNS Security Force during emergencies ii. Basic health physics training NM 6-2 EP-AA-1013 (Revision

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\ '* Nine Mile Point Annex Exelon Nuclear iii. Nine Mile Point Nuclear Station facility layout including arrangements and procedures for site access for Offsite Response Organization Responders iv. Onsite fire protection system equipment (permanent and portable)

v. Differences between onsite firefighting equipment and fire company supplied equipment vi. Communications system vii. Review of appropriate sections of the NMPNS Emergency Plan and Emergency Implementing Procedures viii. The onsite emergency organization including the interface with the Nine Mile Point Nuclear Station Fire Brigade 2)

• The local medical support organizations and individuals are invited to participate in a training program that may include but is not limited to: i. ii. iii. iv. Communications systems The onsite emergency organization including the interface between NMPNS Radiation Protection personnel, the local medical support personnel, and the radiatbn medicine consultants (Oswego Hospital, University Hospital or others) Radiological aspects of emergency medical treatment Nine Mile Point Nuclear Station Emergency Plan Implementing Procedures and Radiation Protection Procedures for decontamination

v. Review of appropriate sections of the radiation emergency plans and/or procedures of the Oswego Hospital and University Hospital

• g. Annually, a. program to acquaint the news media (that is, major public news organizations serving the NMPNS area, such as local radio/TV stations, newspapers, local wire service offices and local correspondents to national new media) with the NMPNS emergency

• plan, information concerning radiation, the emergency classification scheme and points of . contact for release of public information during an emergency, will be conducted.

h. Personnel responsible for the Nine Mile Point emergency preparedness effort receive appropriate training to maintain their level of competency.

• The Site Emergency Preparedness Manager and staff attend relevant seminars and meetings on emergency preparedness issues, such as . those held by the NRC/FEMA and Nuclear Energy Institute.

In addition, June 2016 NM 6-3 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear appropriate technical literature (such as any information received from NEI, FEMA, NRC, etc.) is reviewed to assist in maintaining this competency.

Training requirements for NMP personnel responsible for the emergency planning effort are contained in EP-AA-120, Emergency Plan Administration.

6.1.2 Exercises

and Drills Exercises are realistic, pre-planned simulations of accidents, designed and conducted so

• that the response of the emergency organization closely approximates their response to an actual incident.

Drills are pre-planned simulations in which the participants are "walked" or "talked" through one or more procedures, or aspects of the Station Annex. The primary purpose of drills is to provide individuals with hands-on training in a controlled situation.

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

Drills are evaluated by drill controllers and observers.

The response of Division personnel to an actual emergency condition may be allowed to satisfy a particular drill requirement, provided that a critique is performed and . documented in the manner specified for a drill. In addition, selected training sessions can satisfy drill requirements as allowed by procedure.

Biennial exercises and annual drills are conducted in order to test the state of emergency preparedness of participating individuals, organizations, and agencies.

An exercise or drill may be conducted that simulates an emergency that results in offsite radiological releases requiring response by offsite authorities to: 1) ensure that the participants are familiar with their respective duties and responsibilities;

2) verify the adequacy of both the NMPNS Emergency Plan and the methods used in the appropriate Implementing Procedures;

3) test communications networks and systems; 4) check the availability of emergency supplies and equipment;

5) verify the operability of emergency equipment; and 6) verify adequate interrelationships with offsite agency plans. Exercise scenarios provide the ERO with the opportunity to

• demonstrate proficiency in the key skills necessary to implement the principal . functional areas of emergency response.

Principal functional areas include: Management and coordination of the emergency response, Accident assessment, Event Classification, Notification of Offsite authorities, Assessment of the Onsite/offsite impact of radiological releases, Protective Action Recommendation development, Protective Action decision making, Plant system repair and mitigative action implementation, Public Notification

/Information processes.

Biennial Exercise scenarios are submitted to the NRC for review and approval.

Biennial Exercises are evaluated and graded by the NRC and FEMA to determine that there is "reasonable assurance" that adequate protective measures will be taken in the event of an emergency.

The NRC may require a remedial exercise if they cannot find reasonable assurance or determine that the June 2016 NM6-4 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear ERO has maintained the key skills specific to emergency response.

All Drills and exercises that provide performance opportunities to develop, maintain or demonstrate key skills, provide for a formal critique with controllers and players following the completion of the drill. The critiques are to identify weak or deficient areas that need correction.

During the critique, comments are gathered which are used to improve the emergency preparedness program, and a final assessment of the.drill or exercise is made. Weaknesses or deficiencies identified in critiques are corrected and tracked through the Corrective Action Program. The Site Emergency Preparedness Manager is responsible for planning, scheduling, and coordinating emergency planning related exercises and drills. The Fire Marshal, in conjunction with the Manager Operations and the Manager Training, is responsible for planning, scheduling, and coordinating Fire Brigade related drills. Drill.s are subject to management review. The Site Emergency Preparedness Manager is responsible for reviewing pre-exercise information to ensure only appropriate information is provided to the participants.

In addition, participants are not permitted to review or otherwise view exercise scenarios.

Exercises and drills are conducted to simulate actual emergency conditions as closely as possible and may be scheduled such that more than one drill or exercise can be conducted simultaneously.

Scenarios are prepared that emphasize coordination among onsite and offsite organizations as appropriate and may involve participation by the Nine Mile Point Fire Brigade; monitoring teams; varying degrees of participation of county, state, and Federal agencies and organizations and local offsite support personnel and organizations.

Scenarios are varied and include a wide spectrum of radiological releases and events. These .events include hostile actions, no or minimal radiological release, initial or rapid Site Area or General Emergency declarations, Severe Accident Management and Large Area Loss (1 OCFR50.54(hh)(2)), integration of offsite resource and events that simultaneously involve both NMP and JAF.

• Emergency Preparedness Drills and Exercises may include: communications drills, fire drills, medical emergency drills, radiological monitoring drills, and health physics drills. EOF activation drills are periodically conducted to maintain the proficiency of the EOF staff; Drills/Exercises are planned, scheduled and evaluated in accordance with EP-AA-122, Exercise and Drills. 6.1.3 Site Emergency Preparedness Manager The Site Emergency Preparedness Manager is the individual with overall responsibility and authority for radiological emergency response preparedness for the NMPNS. See Figure 6.1 for Emergency Preparedness organization.

The primary duties of the Site Emergency Preparedness Manager include, but are not limited to: June 2016 NM 6-5 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear a. Ensuring the coordination of the NMPNS Emergency Plans with: 1) Federal Plans 2) State Plans 3) County Plans 4) NMPNS Physical Security Plan 5) NMPNS Fire Protection Plan b. Ensuring that the information, in the Emergency Plan Implementing Procedures are consistent with the NMPNS Station Annex. c. Ensuring that the Emergency Plan Implementing Procedures interface properly with the Administrative Procedures, Security Procedures, Chemistry Procedures, Radiation Protection Procedures, Special Operating Procedures, Emergency Operating Procedures, Severe Accident Management Guidelines, and Training Procedures.

d. Assisting the Manager Training in coordinating emergency planning related specialty training., e. Coordinating emergency preparedness related drills and exercises.

f. Coordinating the review and update of the NMPNS Emergency Plan and Emergency Plan Implementing Procedures.

g. Ensuring the maintenance and inventory of emergency equipment and supplies by scheduling inventory surveillances.

h. Keeping abreast of changes in Federal regulations and guidance that may

• affect emergency planning.

i. Ensuring qualified review of exercise materials and scenarios.

6.2 Reviewing

and Updating of Plans and Procedures

6.2.1 Responsibility

for Reviewing*and Updating Reviewing and updating of the NMPNS Emergency Plan and Emergency Plan Implementing Procedures are the responsibilities of the Site Emergency Preparedness Manager. Reviews of the plan and procedures are performed annually by the Site Emergency Preparedness Manager and/or the Emergency Preparedness staff. Recommended changes are reviewed and approved in accordance with NMPNS Administrative Procedures.

An independent review of the emergency preparedness program and implementing procedures shall be conducted, in accordance with 1 OCFR50.54(t), at least every 24 months or as necessary based on an assessment by the licensee against performance indicators, and as soon as reasonably.

practicable after a change occurs in June 2016 NM 6-6 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but no longer than 12 months after the change. This review will be conducted by Quality and Performance Assessment as part of the QA Audit program, under the cognizance of the Nuclear Safety Review Board

6.2.2 Changes

to the Plans or Procedures Any recommendation for corrective actions or rev1s1ons to the NMPNS Emergency Plans and the Emergency Plan Implementing Procedures shall be forwarded to the Site Emergency Preparedness Manager. These recommendations may result from audits, exercises, drills, changes in operating procedures or conditions, or changes in organization, equipment; personnel, phone numbers or methods of communication or operation.

The Site Emergency Preparedness Manager shall implement approved recommendations for changes in accordance with station procedures.

Review and approval of these recommended changes shall be conducted in accordance with Technical Specifications and Administrative Procedures.

The letters of agreement will be updated at least every 2 years. Verification of the telephone numbers found in the Station Annex and Implementing Procedures occurs quarterly in accordance with the Emergency Equipment Inventory procedure.

6.2.3

• Recertification of Plans and Procedures The Emergency Plan and procedures are reviewed annually in accordance with site administrative procedures.

The Emergency Plan is recertified annually in accordance with EP-AA-120, Emergency Plan Administration.

Emergency plans and procedures are written to comply with the 'guidance in the Procedure Writers Manual. Changes will be submitted for approval in accordance with Technical Specifications and Administrative procedures and* distributed to official copy holders. 6.2.4 Distribution Holders of official copies of the Nine Mile Point Nuclear Station Annex (SEP) receive approved changes to the SEP so that they can maintain th-eir copies current. 6.3 . Maintenance and Inventory*

of Emergency Equipment and Supplies 6.3.1 Responsibility for Maintenance and Inventory*

The Site Emergency Preparedness Manager is responsible for ensuring the maintenance and inventory of emergency equipment and supplies.

The authority for planning, scheduling, and performing the quarterly inventory and inspection of designated emergency equipment and supplies has been delegated as outlined in the Emergency Equipment Inventory procedure.

• June 2016 NM 6-7 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 6.3.2 Maintenance and Inventory Emergency supplies are inspected and inventoried as specified in the Emergency Equipment Inventory procedure.

Instruments will be inspected for operability and calibration status in accordance with station calibration procedures.

Instruments with expired calibrations or instruments with calibrations which will expire prior to the next inspection/inventory will be removed and calibrated, or replaced with *calibrated equipment prior to their expiration date. Sufficient instruments are available to replace those removed from service for calibration or repair. Procedures for instrument calibration are contained in the station procedures.

Calibration intervals meet or exceed any written recommendations of the manufacturers of the equipment.

In addition, emergency communications systems. involving dedicated telephone lines, base station, portable and console radios are tested periodically in accordance with the Emergency Equipment Inventory procedure.

6.3.3 Discrepancies

Any discrepancies found during inventory and inspection will be corrected as detailed in the Emergency Equipment Inventory procedure 6.4

• Public Education and Information

-6.4.1 Instructional Material The NMPNS, in cooperation with the James A. Fitzpatrick Nuclear Power Plant and with state and county authorities, develop and periodically disseminate emergency planning instructional material to residents and transient populations in the Emergency Planning Zone (EPZ). This ensures that the permanent and transient adult population is provided an adequate opportunity to become aware of this information.

This instructional material includes basic education information on:

• Basic educational information on radiation

• Public notification system

• Public response to warning signals

• Protective measures

• Sheltering procedures

• E:vacuation routes and procedures

• Special needs of the handicapped

• Contact for additional information June 2016 NM 6-8 . EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 6.4.2 Dissemination of Instructional Material The following methods may be used to ensure that emergency planning information is transmitted to residents and transients in the EPZ:

• Advertisements summarizing the actions to be taken by residents are published annually in the local newspapers

• Printed instructions and evacuation maps are distributed to EPZ residents

• Printed instructions are included in the local telephone directory

• Printed instructions and evacuation maps are distributed to motels, hotels and recreation areas A sample of this material is retained in the Emergency Preparedness Permanent Plant File. This material is developed and distributed periodically as required by CNG-EP-1.01-1002.

June 2016 NM 6-9 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear FIGURE 6.1 EMERGENCY PREPAREDNESS DEPARTMENT PRESIDENT SITE VICE PRESIDENT NMP *MANAGER SITE REGULATORY ASSURANCE SITE EMERGENCY PREPAREDNESS MANAGER June 2016 NM 6-10 EP-AA-1013 (Revision.2)

1. 2. 3. 4. Nine Mile Point Annex Emergency Response Category Emergency Plan Indoctrination Emergency Directors/

ERF Coordinators Personnel responsible for accident assessment and/or accident management Radiological Monitoring

/Analysis personnel June 2016 Exelon Nuclear FIGURE 6.2 INITIAL TRAINING AND PERIODIC RETRAINING*

Involved Personnel

{Typical)

Persons granted unescorted access to the Protected Area Plant Mar:iager; Managers of Operations,*

SMs, Initial responders, and others as designated SM/Emergency Director and the Emergency Director at EOF, TSC, OSC and EOF Managers; and Alternates Radiation Management Supervisors, Radiation Protection lechnicians, and others as designated NM 6-11 Initial Training and Periodic Retraining Initial -Emergency Plan content and implementation; specifically:

personal actions, warnings, assembly areas, use of station communications, personnel accountability and evacuation to an offsite assembly area. Initial -Instruction on the scope, responsibilities, and function of the Emergency Plan and Implementing Procedures, including Incident Command System (ICS) concepts, position titles and terminology.

Periodic -Once per calendar year not to exceed 1 B months Between training sessions.

Review of any changes made . since the last training period. Initial -Instruction on the NMPNS Emergency Plan and Implementing Procedures and Technical Support Guidelines germane to their particular assessment/management function, including Incident Command System (ICS) concepts, position titles and terminology.

Periodic -Retraining will be once per calendar year not to exceed 18 months between training sessions and will include a review of the above material and any changes made since the last training period. Selected Radiation Protection personnel receive substantial training in radiation monitoring.

Initial -Training for personnel performing r(3.diation monitoring and analysis duties will consist of instruction in the downwind and/or in plant radiation monitoring and sampling Implementing Procedures, including Incident Command System {ICS) concepts, position titles and terminology.

Periodic -Retraining will be once per calendar year not to exceed 18' months between training sessions with hands-on instrumentation usage including interpretation of results. EP-AA-1013 (Revision

2)

Nine Mile Point Annex Emergency Response *category

5. Fire Response /First Aid/Rescue/Medical Support 6. Damage Control/RepairTeams personnel

7. Security Personnel/Local Law Enforcement Officials

8. Communication Personnel June 2016 Exelon Nuclear FIGURE (;.2 (Cont.) INITIAL TRAINING AND PERIODIC RETRAINING*

Involved Personnel (Typical)

NMPNS Fire Brigade/Offsite Fire Departments Ambulance and Hospital Personnel Nuclear Operators, Nuclear Auxiliary Operators, Maintenance Supervision, l&C Supervision, Radiation Protection Supervision Selected Maintenance, l&C and Radiation Protection Personnel, and others as designated Security personnel assigned responsibilities for Emergency Plan function, and Local Law Enforcement Officials

.. As designated NM6-12 Initial Training and Periodic Retraining Designated members will receive training as appropriate in basic patient care and treatment.

Members will also be instructed on the availability of onsite medical treatment supplies and equipment; communication systems; access controls radiological hazards; and roles, interfaces and responsibilities with local fire/ medical support personnel, including Incident Command System (ICS) concepts, position titles and terminology.

Repair and Damage Control are considered a normal part of the job functions of the listed personnel and, as such, special . training in these functions, other than appropriate emergency

• plan and procedures training, is not required.

Training and retraining requirements are outlined in the Nine Mile Point Nuclear Security Training and Qualification Plan, including Incident Command System (ICS) concepts, position titles and terminology.

Initial -Training shall consist of a review of appropriate Implementing Procedures, communications equipment and messages, including Incident Command System (ICS) concepts, position titles and terminology.

Periodic -Retraining will be conducted once per calendar year not to exceed 18 months between training sessions.

EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear ** Section 7: Recovery Actions taken during an emergency situation fall into two general categories; response and recovery.

Response actions are those taken to manage the consequences of an emergency and to bring the emergency under control. Recovery actions are those longer term actions taken to restore the station, as nearly as possible, to its emergency condition.

This section describes recovery actions and establishes typical criteria for declaring that an emergency has entered the recovery phase. 7 .1 Progression From Emergency Response to Recovery The two general action categories, response and recovery, are directed by separate organizations:

the On-Site Emergency Organization is responsible for initial response while the Recovery Organization is responsible for long term response and recovery.

7 .1 .1 Re-entry Phase The Re-entry Phase is the period following evacuation during which access to the station is restricted.

This period can commence with the start of the emergency, or can develop as the emergency progresses, and may last into the recovery phase. Re-entry may be made to perform essential tasks such as saving human lite; controiling release of radioactive materials, and preventing additional damage to plant and equipment.

Additional actions to be taken during the Re-entry Phase are controlled by implementing procedures and will be directed by the Emergency Director or the Recovery Manager (RM). Planning for re-entry will include evaluation of available survey data, review of exposures incurred, projection of manpower and equipment needs, and re-entry survey team activation.

Upon re-entry a comprehensive survey of the plant will be made to define radiological problem areas. Data gathered during the re-entry operation and additional information developed by the various technical support groups will be assessed and used in developing subsequent recovery plans.

• The planned radiation exposure limits for re-entry should be consistent with 1 O CFR 20. If the need arises for exposures in excess of the limits of 1 O CFR 20, the ED may institute the higher limits identified in Section 4.0 of the NMPNS Station Annex.

• 7.1.2 Termination of Emergency Phase The Corporate Emergency Director will periodically evaluate and assess the status of the emergency, the effectiveness of emergency actions, and the need to update the emergency class. The Corporate Emergency Director, in consultation with the Station Emergency Director and. offsite authorities, will determine when the emergency phase has ended. Notification of the appropriate authorities (e.g., county, state, and federal agencies, etc.) and the Emergency Response Organization will then take place. Criteria for declaring an emergency situation resolved is dependent on the emergency classification declared but may June 2016 NM 7-1 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear include: Radiation levels in all in-plant areas are stable or are decreasing with time. *

• Reactor and associated systems are in a safe, stable condition, a reactor cool-down is in progress and it has been determined that the plant has the ability to achieve and maintain a cold shutdown condition.

• Releases of radioactive materials to the environment are under control or have ceased.

• Any fire, flooding or similar emergency conditions are under control or have ceased.

• Drywall pressure is at normal levels. Emergency Plan Implementing Procedure EP-CE-115, Termination and Recovery provides the specific guidance on termination of the emergency phase and commencement of the recovery phase. 7 .1 .3 Recovery Phase During the initial stage of the Recovery Phase, data gathered from re-entry operations and additional information developed by the various technical support groups will be assessed.

A plan of action for returning the plant to a: condition within Technical Specifications limits will be developed using the guidance provided in EP-CE-115.

7.2

• Recovery Operations Recovery operations necessary to restore the plant to an operational condition will be conducted within the framework of the Recovery Organization.

From the EOF, the CED or Recovery Manager (RM) and EOF staff will direct entry into recovery operations.

Specific recovery tasks and the sequence in which they are performed will be at the direction of the Recovery Manager. The Recovery Manager will be responsible for deactivating the Recovery Organization.

Activities for which the Recovery Organization is responsible during the recovery phase include, but are not necessarily limited to, the following:

a. Logistical

b. Corrective Actions c. Engineering

d. Radiological

e. Administrative Procedures detailing performance of the above tasks will be developed if required, during the recovery phase. June 2016 NM 7-2 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear During recovery operations, the radiation exposure limits of 1 O CFR 20 apply. Compliance with those limits will be the responsibility of the Recovery Manager via the applicable Health Physics organization.

Recovery actions that plan for or may resul.t in radioactive releases will be evaluated by the Recovery Manager and EOF staff as far in advance of the action as possible.

These actions and data pertaining to the release will be reported to the appropriate off-site emergency response organizations and agencies.

7.3 Emergency

Organization Transformations The emergency response organization may go through a series of transformations depending upon the time of initiation, type, severity and duration of the emergency condition.

A long-term recovery organization that is general in-nature has been defined. The transition to the Recovery Organization will be communicated to concerned parties by the Recovery Manager, via the ERF managers/coordinators.

7.4 Recovery

Organization The Recovery Organization is comprised of two major groups: Functional and Support. (See Figure 7-1) The Functional Group is essentially comprised of the normal station organization and would be responsible for the development and implementation of plans and procedures necessary for the long-term emergency response and recovery operations.

The Functional Group is directed and coordinated by the RM through the Plant Manager, the Engineering Director, the Maintenance Director and the Director, .Work Control and Outage Management.

The Functional Group utilizes personnel performing duties they normally perform, such as; Operations, Maintenance, Engineering, Chemistry, Radiation Protection.

and Outage Management.

The Support Group is comprised essentially

• of those positions established in the augmentation of the initial. on

• shift emergency response at the Emergency Operations Facility with the addition of the following managers/directors providing support functions as required/needed from the following organizations:

Human Resources, Training, Business Planning, JIC Director, Quality and Performance Assessment, Security and Emergency Preparedness (Corpora,te), Procurement and Warehouse Services (Corporate), IT and Telecommunications Services (Corporate).

The Support Group would assist the Functional Group in areas such as plant modification, design, construction, recovery engineering, quality assurance/control, and administrative support functions such as purchasing, transportation, treasury, materials management, communications, legal, claims, and risk management, etc. June 2016 NM 7-3 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear Other personnel may be called upon to enable the Recovery Organization to function on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day basis for extended periods or to provide special expertise in specific areas as dictated by the type and severity of the particular emergency.

7.4.1 Recovery

Organization Staff As stated above, the recovery organization is comprised of positions already in place during the emergency, and other staff performing normal functions.

Examples of additional staff that may be called on to support the recovery operations are described below. It is expected that the additional.

staff will be performing duties similar to those they are normally expected to perform on a day to day basis, thus additional training for these positions is not required.

7.4.1.1 Functional Group June 2016 a. Plant Manager The Plant Manager is the typical designee for this position.

The Plant Manager reports . to the Recovery Manager during the recovery phase of an emergency and is responsible for obtaining and coordinating services from the various departments that are the normal direct reports to this position.

Additionally, the Plant Manager has responsibility for oversight of the Plant Operations Review Committee (PORC). These services/departments may include: * *Operations

• Chemistry

• Radiation Protection

• Reactor Engineering The Plant Manager will be expected to ensure that staffing and

• work schedules are setup as required to support* the recovery organization.

b. Director Engineering The Director Engineering is the typical designee for this position.

This position reports to the Recovery Manager during the recovery phase of an emergency and is responsible for obtaining and coordinating services from the various departments that are the normal direct reports to this position.

These services/departments . may include:

• Electrical Engineering

• Structural Engineering

• Mechanical Engineering

• .systems Engineering

• . Thermo-hydraulic Engineering The Director Engineering Services will be expected to ensure that staffing and work schedules are setup as required to support the recovery organization.

c. Director Maintenance The Director Maintenance is the typical designee for this position.

This position reports to the Recovery Manager during the recovery phase of an emergency and is responsible for obtaining and NM EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear coordinating services from the various departments that are the normal direct reports to this position.

These services/departments may include any of the maintenance disciplines (electrical, mechanical, I & C). The Director Manager will be expected to ensure that staffing and work schedules are setup as required to support the recovery organization.

d. Director.

Work Management The Director, Work Management is the typical designee for this position.

This position reports to the Recovery Manager during the recovery phase of an emergency and is responsible for obtaining and coordinating services from the* various departments that are the normal direct reports to this position.

These services/departments may include: work control, outage planning and scheduling, project management and onsite material procurement services.

The Director, Wo,rk Management will be expected to ensure that staffing and work schedules are setup as required to support the recovery organization.

7.4.1.2 Support Group *June 2016 a. Director, Training The Director, Training is the typical designee for this position.

This position reports to the Recovery Manager during the recovery phase of an emergency and is responsible for providing whatever training services are required.

b. Manager, Human Resources The Manager, Human Resources is the typical designee for this position.

This position reports to the Recovery Manager during the recovery phase of an emergency and is responsible for providing all necessary aspects of human resources, including occupational . health and safety.aspects as required.

c. Manager. Finance and Business Operations The Director Finance and Business Operations is the typical designee for this position.

This position reports to the Recovery Manager during the recovery phase of an emergency and is responsible for ensuring all necessary business management aspects of the emergency recovery are provided for as required.

d. Manager. Quality & Performance Assessment The Director Quality and Performance Assessment is the typical designee for this position.

This position reports to the Recovery Manager during the recovery phase of an emergency and . is responsible for ensuring all quality aspects of the emergency recovery as required.

NM 7-5 EP-AA-1013 (Revision

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'* Nine Mile Point Annex Exelon Nuclear e. Directors (Corporate)

The Directors of Security and Emergency Preparedness, Procurement and Warehouse Services, and Information Technology and Telecommunications are the typical designees for these positions

.. These positions, as requested, report to the ALM during the recovery phase of an emergency and are responsible for obtaining and coordinating services from their departments.

These services may include:

• Nuclear Security

• Procurement

• Emergency Preparedness

• Site Services

• Technical Services The Directors (Corporate) will be expected to ensure that staffing

• and work schedules are setup as required to support the recovery organization.

7.4.2 Augmentation

of the Emergency Response/

Recovery Organization Additional augmentation may be. necessary, as the situation dictates, by the Institute for Nuclear Power Operations (technical personnel and equipment)', by the NSSS vendor (technical personnel, equipment and replacement parts as needed) and by other local nuclear power plants * (survey teams and laboratory facilities).

7.4.2.1 Contract Services Long-term emergency response and recovery activities may require additional personnel and equipment.

When contracted services are required, the normal practice of assigning a NMPNS employee to administer the contracted service, i.e., provide overall technical direction, coordination, and review, will be employed to ensure the actions of the contractor support the needs of the recovery operation.

7.4.2.2 Local Support Services June 2016 Local support services necessary to support a large influx of personnel from the contractors, vendors and government support organizations may be required.

These services include items such as: *Lodging *Food

• Transportation There are sufficient facilities in the vicinity of the station to supply these basic services.

Individual contracts will be negotiated for these facilities as necessary.

NM 7-6 EP-AA-1013 (Revision

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Nine Mile Point Annex. Exelon Nuclear Figure 7.1: Typical Recovery Organization (for Site Area or General Emergency) r Recovery Manager<1> ... I I I I Onsite Recovery Offsite Recovery Public Information Other EXELON Director<2 l Director<3 l Director<4 l Support Directs Recovery activities Directs the interface with Directs the EXELON Public Legal, Financial, and so forth. to restore the plant to pre-Federal, State and local Information Program during incident conditions.

agencies during the the Recovery process. Recovery process. Functional Support NOTES: . (1) The Recovery Manager position will normally be filled by a Vice President-or designee.

IF the station VP does not fill position the Recovery Manager reports to the VP. (2) The Onsite Recovery Director position will normally be filled by the Plant Manager or designee.

The normal plant staff will support recovery activities as required.

A special Radiation Protection Manager and/or Administrative and Logistics Manager may need to be appointed for events which involving severe plant damage or large releases of radioactive materials inside or outside the plant. (3) The Offsite Recovery Director position will normally be filled by the Site Emergency Preparedness Manager or designee.

Radiological support positions should be designated to support offsite recovery activities if there was a significant release of radioactive materials.

(4) The Public Information Manager position will normally be filled by the Communications Department personnel.

(5) Other positions may be designated to support completion of the Recovery Plan as needed. June 2016 NM 7-7 EP-AA-1013 (Revision

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, __ Nine Mile Point Annex Exelon Nuclear SECTION 8: ACRONYMS AND DEFINITIONS

8.1 Acronyms

This section contains the acronyms of terms that are used in a special context in this plan and/or are unique to Nine Mile Point Nuclear Station (NMPNS). o ALARA -As Low As Reasonably Achievable 0 0 0 0 0 0 0 0 0 0 0 0 0 0 o_ 0 0 0 0 0 0 0 0 0 0 June 2016 ARM -Area Radiation Monitor CDET -Committed Dose Equivalent

-Thyroid (Child) CRS -Control Room Supervisor CWP -County Warning Point DOE -U.S. Department of Energy EAL -Emergency Action Level EAS -Emergency Alert System ED -Emergency Director EDE -Effective Dose Equivalent ED-Emergency Director ENS -Emergency Notification System EOC -Emergency Operations Center EOF -Emergency Operations Facility EPA -U.S. Environmental Protection Agency EPIP -Emergency Plan Implementing-Procedure EPMP -Emergency Plan Maintenance Procedure EPZ -Emergency Planning Zone ERF -Emergency Response Facilities ETE -Evacuation Time Estimate FRMAP -Federal Radiological Monitoring and Assessment Plan FSAR -Final Safety Analysis Report ISFSI -Independent Spent Fuel Storage Installation JAFNPP -James A. Fitzpatrick Nuclear Power Plant JIC -Joint Information Center Kl -Potassium Iodide NM 8-1 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear o LCO -Limiting Condition for Operation o MMS -Meteorological Monitoring System o NED -Nuclear Engineering Department o NMPNS -Nine Mile Point Nuclear Station o NRC -U.S. Nuclear Regulatory Commission o NSRB -Nuclear Safety Review Board *o NSSS -Nuclear Steam Supply System o NWS -National Weather Service o NYSDOH -New York State Department of Health o OCEMO -Oswego County Emergency Management Office o OCEOC -Oswego County Emergency Operations Center . o

• ODAM -NMPNS Offsite Dose Assessment Manager o OEM -Office of Emergency Management (New York State) o OSC -Operations Support o OSLO -Optically Stimulated Luminescent Dosimeter o PAG -Protective Action Guide o PAR -Protective Action Recommendation o PNS -The Oswego County Prompt Notification System o PORC -Plant Operations Review Committee o QATR -Quality Assurance Topical Report o RAM -NMPNS Radiological Assessment Manager o RECS -Radiological Emergency Communications System. o RO -Reactor Operator o SEP -NMPNS Station Annex o SEOC -State Emergency Operations Center o SM -Shift Manager o SOP -Special Operating Procedure o SRD -Self-Reading Dosimeters o SRO -Senior Reactor Operators June 2016 NM 8-2 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 8.2 o STA -Shift Technical Advisor o STOC -Security Tactical Operations Center o SUNY -State University of New York o SWP -State Warning Point o TEDE -Total Effective Dose Equivalent o TIBL -Thermal Internal Boundary Layer o TLD -Thermoluminescent Dosimeter o TSC -Technical Support Center o USAR -Updated Safety Analysis Report q WSFO -Weather Service Forecasting Office Definitions This section contains the definitions of terms that are used in a special context in this plan and/or are unique to Nine Mile Point Nuclear Station (NMPNS). o ACCESS CONTROL POINTS -Checkpoints for incoming traffic to be stopped and identification verified.

These points are established by Nuclear Security at the Alert, or higher emergency classification, or as directed by the Emergency Director. Access Control Points are designated at two. locations:

• Owner Controlled Area (OCA) Checkpoint, Lake Road

• NMP/Fitzpatrick Property Line, Lake Road o AFFECTED UNIT -The affected unit is NMPNS Unit 1 and/or Unit 2

• whichever has declared an emergency

.. o ALTERNATE STATE WARNING POINT -The Alternate SWP is located in the N.Y. State* Police Communications Center in the Public Security Building, State Office Building Campus, Albany, N.Y. This facility is manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day and could perform the same functions as the State Warning Point (see State Warning Point). o AREA RADIATION MONITOR (ARM) -A fixed instrument which typically measures gross gamma radiation levels in a local area and alarms when the radiation exposure rate reaches the preset alarm level. o ASSESSMENT ACTIONS -Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures.

o ASSESSMENT FACILITY -A facility used for evaluation of information

• including instrument data, to assess the scope and severity of . an emergency condition.

Such facilities available to Nine Mile Point include: June 2016

• NM 8-3 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear

• Onsite Control Rooms Technical Support Center

• Off-Site Emergency Operations Facility o CDET -Represents the dose equivalent to the child thyroid, weighted on the basis of the relative detriment to the individual, for an exposure period of 50 years. o MITIGATIVE ACTIONS -Those emergency measures taken to mitigate or terminate an emergency situation at or near the source of the problem in order to prevent an uncontrolled release of radioactive material or to reduce the magnitude of a release. o COUNTY WARNING POINT (CWP) -The communications center at Oswego County 911 Center in Oswego, N.Y. is the County Warning Point. It serves as a 24-hour notification point for messages from the utilities to appropriate officials in the county. o DOSE PROJECTION -A calculated estimate of the potential dose to individuals at a given location onsite or offsite. It is determined from the quantity of radioactive material released and the appropria:te meteorological transport and diffusion parameters.

o EMERGENCY -A situation outside of routine operational events or minor equipment malfunction which could lead to a radiological hazard affecting the health and safety of workers. or the public, or result in significant damage to property o EMERGENCY ACTIONS -A collective term encompassing the assessment, corrective and protective actions taken during the course of an emergency.

o EMERGENCY ACTION LEVELS (EAL) -Specific indications or conditions used as thresholds for initiating specific emergency actions. o .EMERGENCY ALERT SYSTEM (EAS) -A system of radio stations organized to permit designated government officials to issue emergency information and instructions in threatened or actual emergencies.

o EMERGENCY CLASSIFICATION -A condition which falls into one of the following categories:

Unusual Event, Alert, Site Area Emergency, or General Emergency.

o EMERGENCY DIRECTOR -The individual responsible for the implementation and administration of the NMPNS Station Annex. Directs the emergency response organization and has overall authority for control of the emergency situation and for assuring continuity of resources.

June 2016 NM 8-4 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear o EMERGENCY OPERATIONS CENTERS (EOC) -Local and State facilities for assessment of emergency information and direction of local and State emergency response personnel.

o EMERGENCY PLAN IMPLEMENTING PROCEDURES -A procedure that provides detailed instructions to NMPNS personnel and implements an action or activity described in the Station Annex. These procedures are considered Technical Specification related and are listed in Appendix 3. o EMERGENCY PLAN MAINTENANCE PROCEDURES

-Procedures which provide instructions, checklists, and guidance to maintain the emergency preparedness program, equipment and associated documents.

o EMERGENCY PLANNING ZONE (EPZ) -A designated area around NMPNS used to facilitate offsite emergency planning.

There are two Emergency

• Planning Zones: the plume .exposure pathway and the ingestion exposure pathway. o EMERGENCY RESPONSE FACILITY (ERF) -A generic term referring to a faciiity that is used for emergency purposes.

These facilities include the Control Room, Technical Support Center, Emergency Operations Facility, Operations Support Center, Joint Information Center, Oswego County Emergency Operations Center, etc. o EMERGENCY RESPONSE/RECOVERY ORGANIZATION The organization, which consists of Division, corporate and outside personnel, that manages the large scale or long-term respor:ise to and recovery from an accident.

o E.NVIRONMENTAL MONITORING TEAMS These teams are characterized by personnel from the station staff (Radiation Protection or Environmental Departments) or contractor staff that collect environmental

• measurements as part of the Expanded Radiological Environmental Monitoring Program. *

• o EVACUATION ASSEMBLY AREAS -Areas outside of the protected area where personnel evacuated from the protected area are assembled.

The two primary areas. typically designated are the P-Building at Unit 2 for personnel exiting the protected area via the Unit 2 security access, and the Nuclear Learning Center for personnel exiting the protected area via the Unit 1 security access. o EXCLUSION AREA -The area controlled by NMPNS surrounding the station, in which the licensee has the authority to determine all activities . including exclusion or removal of personnel and property from the area. *For emergency preparedness purposes, the NMPNS/JAFNPP exclusion areas are considered to be one exclusion area. o EXPANDED RADIOLOGICAL ENVIRONMENTAL MONITORING . PROGRAM.-This program is characterized by an increase in the number June 2016 NM 8-5 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear and frequency of samples collected, plus other additional sampling of critical pathways (such as snow, ground deposition, surface water, etc.) o FEDERAL RADIOLOGICAL MONITORING AND ASSESSMENT PLAN (FRMAP) -The Federal government's means of providing in-depth assistance to licensees, States, and local governments in the event of a radiological emergency.

The monitoring and assessment teams are normally provided by the Department of Energy (DOE). o HAZARDOUS MATERIALS

-Any element, compound or combination thereof, which is detonable, flammable, corrosive, toxic, an oxidizer, an etiologic agent, or highly reactive and which because of handling, storage processing, or packaging may have detrimental effects upon operating personnel and emergency personnel, the public, plant equipment, and/or the environment.

o INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) -The ISFSI is a complex designed and constructed for the interim storage of spent fuel, solid reactor-related greater than Class C (GTCC) waste; and other radioactive materials associated with spent nuclear fuel assemblies discharged from NMPNS Unit 1 and Unit 2 reactors.

o INGESTION EXPOSURE PATHWAY -The principal exposure from this pathway would be from ingestion of contaminated water or foods such as milk or fresh vegetables.

The duration of principal exposures could range in length from hours to mon_ths. o LOCAL AREA EVACUATION

-Evacuation of personnel from localized areas within the station with outside the affected local area. o NINE MILE POINT NUCLEAR STATION L.L.C (NMPNS) -A limited liability corporation and operator of Nine Mile Point Nuclear Station. o NUCLEAR SAFETY REVIEW BOARD (NSRB) -a committee which provides independent review and audit of designated activities affecting the safe operation of the stations.

o OFFSITE -Any area outside of the joint property controlled by NMPNS and JAFNPP. o OFFSITE ASSEMBLY AREA (OAA) -Specific location outside the NMPNS 1 O mile EPZ for the assembly of personnel in the event of an -exclusion area evacuation.

This area is typically the Oswego County Airport, Hanger K; in the town of Volney. o ONSITE -The area within the joint property controlled by NMPNS and JAFNPP, the exclusion area. o ONSITE ASSEMBLY AREAS -These are areas within the protected area where personnel will gather to allow for continuous accountability of personnel remaining within the protected area. o OSWEGO COUNTY EMERGENCY OPERATIONS CENTER (OCEOC) -A facility that serves as the county command post from which emergency operations will be directed and coordinated.

The OCEOC is located in the June 2016 NM 8-6 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear 0 0 0 Oswego County Emergency Management Offices in the basement of the Oswego County Branch Building, Route 481, Fulton, N.Y. OWNER CONTROLLED AREA (OCA) EVACUATION

-Evacuation of all non-essential personnel from the NMPNS OCA to either the designated Offsite Assembly Area or to their home. This includes, as appropriate, the evacuation of individuals from the NMPNS OCA including the Nuclear Learning Center; Energy Center, Sewage Treatment Facility, all other NMPNS site locations, and a notification to the James A. Fitzpatrick Nuclear Station of the evacuation.

PERSONNEL ACCOUNTABILITY SYSTEM -A system of accounting for personnel within the Protected Area. The system was developed in response to NUREG-0654 (Section 11.J.5) and uses the Nuclear Security Proximity Cards assigned to personnel entering the Protected Area, Emergency Accountability Card readers located throughout the protected area, and a computerized database.

The system provides timely identification of individuals who have NOT reported to Onsite Assembly Areas or exited the protected area and generates a personnel accountability report. PA SYSTEM -A generic term used throughout the Site Emergency Plan referring to a Public Address system where an announcement or alarm can be made and heard throughout the protected area. Other terms used for the PA system are the GAltronics, Plant Paging System, Page Party/Public Address Communications Subsystem (PP/PA), etc. o PREVENTIVE PAG -These are projected dose commitment values at which recommendations should be made to responsible offsite officials.

These actions should have minimal impact to prevent or reduce the radioactive contamination of hu.man food or animal feed. o PLANT OPERATIONS REVIEW COMMITTEE (PORC) -A review group which, in accordance with the QATR, functions by advising the PORC Chairman and the Nuclear Safety Review Board concerning the safety aspects of proposed courses of action. o PLUME EXPOSURE PATHWAY -A pathway by which individuals can be exposed to radiation.

The principal exposure sources from this pathway are: (a) whole body external exposure to gamma radiation from the plume and from deposited material; and (b) inhalation exposure from the passing radioactive plume. o . PROTECTED AREA -This is the area within the station security fence designated to implement the security requirements of 1 OCFR73. It is sometimes referred to in the context of Unit 1 and/or Unit 2 protected area. o PROTECTED AREA EVACUATION

-Evacuation of nonessential individuals within the stations' protected area, to assembly areas outside of the protected area designated as Evacuation Assembly Areas. These

• areas are .typically the Nuclear Learning Center and the P-Building.

June 2016 NM 8-7 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear o PROTECTIVE ACTIONS -Those emergency measures taken before or after a release of radioactive material has occurred for the purpose of preventing or minimizing radiological exposures to persons' that would be likely to occur if the actions were not taken. Some of the possible protective actions are:

• Evacuation

• Isolation of Ingestion Pathway and Sources.

• Radioprotective Drug Administration o PROTECTIVE ACTION GUIDES (PAGs) -Projected radiological dose or dose commitment values to individuals in the general population that warrant protective action before or following a release of radioactive material.

Protective actions would be warranted provided that the reduction in individual dose expected to be achieved by carrying out the protective action is not offset by excessive risks to individual safety in taking the protective action. The PAG does not include the dose that has unavoidably occurred prior to the assessment.

o RADIOLOGICALLY CONTROLLED AREA (RCA) -Major plant areas to which access is limited for the purpose of protecting personnel from exposure to radiation and contamination.

-o . RADIOLOGICAL EMERGENCY COMMUNICATIONS SYSTEM (RECS) -A dedicated telephone system used to provide initial notification of an emergency, and-continuing emergency information, to the State and to Oswego County.

• o . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Characterized by the collection of normal radiological samples required by technical specifications and additional optional samples not covered in technical specifications (such as soil; meat, poultry, etc.) o RECOVERY ACTIONS -Those actions taken after an emergency to restore the plant as nearly as possible to its pre-emergency condition

.. o REQUISITE TRAINING -The training specified for an emergency position, and contained within Training Department Procedures for Emergency Preparedness.

o RESTRICTED AREA -Any area to which access is controlled by NMPNS for purposes of protection of individuals from exposure to radioactive materials.

o SAFE SHUTDOWN SYSTEM -A descriptive term applying to a combination of systems that can be used to provide a decay heat removal. path. o SAFETY ANALYSIS REPORT (SAR) -A periodically updated multi volume report describing a nuclear power station's site, design features, safety features and the utility's intended methods of operation.

The SAR must be submitted to the U.S. NRC by the utility when applying for an June 2016 NM 8-8 EP-AA-1013 (Revision

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' ' \ Nine Mile Point Annex Exelon Nuclear operating license for the nuclear station. The Unit 1 SAR may be referred to as UFSAR and Unit 2 to as USAR. o SAFETY ANALYSIS *REPORT FOR THE ISFSI -The Standardized NUHOMS Updated Final Safety Analysis Report (NUHOMS provides the generic safety analysis for the Standardized NU HOMS R system for storage of light water reactor spent nuclear fuel assemblies (No. NUH-003, Revision 11, NRC Docket No. 72-1004).

This system provides for the safe dry storage of spent fuel in a passive ISFSI which fully complies with the requirements of 1 OCFR72 and ANSI 57.9. This U FSAR formed the basis for generic N RC certification of the standardized NU HOMS system and is used by 1 OCFR50/1 OCFR72 general license holders in accordance with 1 OCFR72 Subparts K and L. o SAFETY PARAMETER DISPLAY SYSTEM (SPDS) -This system provides a display of plant* parameters from which the safety status of station operations may be assessed in the Control Rooms and Technical Support Center. o SECURITY CONTINGENCY EVENT -A deliberate act or perceived threat of an act which could imperil the station and endanger the public health and safety by exposure to radiation.

0 0 SECURITY TACTICAL OPERATIONS CENTER (STOC) -A security command center that may be activated during a security contingency event, or activation ofthe site emergency plan. SHIFT MANAGER/EMERGENCY DIRECTOR -The individual responsible for the implementation and administration of the NMPNS Site Emergency Plan. Directs the emergency response organization and has overall authority for control of the emergency situation and for assuring continuity of resources until relieved by the Emergency Director in _the EOF.

• o* SITE EMERGENCY PREPAREDNESS MANAGER -The individual responsible for the coordination of emergency planning efforts. o SPECIAL* OPERATING PROCEDURES (SOP) -These procedures contain instructions for station operators usually attributed to emergency procedures in the regulatory guides and standards.

o STATE EMERGENCY OPERATIONS CENTER (SEOC) -The State command post from which emergency operations will be directed and coordinated.

• o STATE WARNING POINT (SWP) -Serves as a notification point for messages from the utilities to appropriate officials in the State. The SWP. is manned on a 24-hour per day basis. o STATION -As used in the Site Emergency plan, Station refers to the site containing the two Nine Mile Point reactors, associated outbuildings and all personnel working to support the operation of the site. o TECHNICAL SUPPORT CENTER MANAGER (TSCM) -The individual responsible for implementation of on-site support activities necessary to June 2016 NM EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear effectively implement the SEP and mitigate the emergency.

The TSCM has the leadership role to ensure on-site emergency activities are carried out in accordance with the SEP and implementing procedures at the direction of the Shift Emergency Director or ED. o TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) -Represents the sum of the effective dose equivalent and the committed effective dose equivalent.

o UNRESTRICTED AREA -Any area to which access is not controlled by NMPNS for purposes of protection of individuals from exposure to radiation and radioactive materials, and any area used for residential quarters.

June 2016 NM 8-10 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear NU REG 0654 A.1.a A.1.b A.1.c A.1.d A.1.e A.2.a A.2.b A.3 A.4 B.1 B.2 B.3 B.4 B.5 B.6 B.7 June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA NMPNS STATION ANNEX SECTION Identification of Response Organizations 2.1,

• 2.2, 2.9, 2.10, 2.11 Organization of Concept of Operations 2.1, 2.2, 2.9, 2.10, 2.11 Organizational Block Diagram Fig. 2.1, Fig. 2.2, Fig. 2.6, Fig. 2.3, Fig 2.4, Fig 2.5, Fig. 4.2, Fig. 4.3 Designation of Organization Direct<:>r 2.1, 2.3, 2.4 24 Hour Response/Communication 2.1, 2.2, Organization Authority Appendix 5 Legal Basis for Organization Authority Appendix 5 Formal Intra-Government/Organization Agreements Appendix 2 Designated Authority for Organization Resource 2.6 Continuity Provision for Onsite Shift Emergency 2.1, 2.1.1, 2.1.2, 2.2, EP-AA-1013, Addendum 1 Designation of Onsite Emergency Coordinator 2.1,

• 2.2 Line of succession for the Emergency Coordinator 2.2.1, 2.2.2b, 2.2*, 2.1, 2.3, 2.4 Functional Responsibilities of the Emergency 2.2, 2.5 Coordinator Qualification of Onsite Emergency Personnel 2.2, Fig. 2.1 Onsite Emergency Organization Interface Fig. 2.1-2.6, Fig. 4.2, Fig. 4.3 Corporate level support and Table B-1 2.1, 2.8 App 1-1

• EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear NU REG 0654 B.7.a B.7.b B.7.c B.7.d B.8 B.9 C.1.a C.1.b C.1.c C.2.a C.2.b C.3 C.4 D.1 D.2 D.3 D.4 June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND REV 1 CRITERIA NMPNS STATION ANNEX SECTION Logistical Support for Emergency Personnel

2.6 Technical

Support Planning/Reentry/Recovery

7.4 Management

level Interface with Governmental 2.6, Fig. 2.1 Authorities Augmentation of Media Release personnel 2.6, Fig. 2.1 Augmentation by Private Contractors/Organizations 7.4.2, 2.9, 2.1 O Local Agency Support Services and Agreements 4.8, Appendix 2, 2.1 O ,A.uthority to request Federal Resources 2.2.b, 2.3, 2.6.2.a Resources expected and Arrival Times 2.11 Support Available for Federal Response 5.1.4, 5.2, 2.11 Representative of State/County to EOF Appendix 5 NMPNS Representative to State/County EOCs 2.6.2.i, 2.6.2.j Radiological Laboratory Capabilities 5.3.1 , 5.3.2 Sources for Nuclear Assistance 5.6, 9.4.2, Appendix 2, 2.9, 2.10, 4.8, 5.1.7, 5.1.8, 5.3 Facility Emergency Classification Methodology 3.1, 4.3, Fig 3.1 Initiating Conditions 3.1, 4.3, Fig. 3.1

• State Emergency Classification System Appendix 5 State and Local Procedures Appendix 5. App 1-2 EP-AA-1013 (Revision 2).

• \ Nine Mile Point Annex Exelon Nuclear NU REG 0654 E.1 E.2 E.3 E.4 &

E.5 E.6 E.7 F.1.a F.1.b F.1.c F.1.d F.1.e p.1.f F.2 F.3 June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA Bases for NotificationNerification NMPNS STATION ANNE'.X SECTION 4.2.1 I 4.2.2, 4.2.3, Fig. 4.1 Personnel Notification/Alerting/Mobilization 4.2.2, 4.2.3 Initial Emergency Message Content 4.2.1 Provisions for Content of Plant Follow up Messages 4.2.1 Dissemination of Information from Plant to Public Appendix 5 via EAS Means for Population Notification 4.2.2.a, 4.7.2, Appendix 5 Provisions for Written Public Instruction Messages 24 Hour Notification/Activation of State and County Emergency Response Communications with State/County

• Communications with Federal Emergency Response Organizations Communications between Plant and EOF/State and County and monitoring teams Provisions for alerting each Response Organization Communications between Plant/ NRC HQ and Regional Office/ the EOF/ and monitoring team assembly areas Communications for fixed and mobile medical facilities Periodic Communications testing App 1-3 4.7.2, 6.4.1, Appendix 5 2.1,5.2, 2.5,4.2.1, 4.2.2, ' 5.1.7, 5.1.8, 5.2.1, 5.2.3, 5.2.8, Appendix 2, Appendix 5 . Fig. 4.2, Fig. 4.3, 5.2, 5.2.3 Fig. 4.2, Fig. 4.3, 5.2, 5.2.1, 5.2.2, 5.2.4 4.2.1, 4.2.3, Fig. 4.2, Fig. 4.3, 5.2, 5.2.1, 5.2.3, 5.2.4, .5.2.6, 5.2.7 Fig. 4.2, Fig. 4.3, 4.2.2,. 5.2 Fig. 4.2, Fig. 4.3, 5.2, 5.2.2, 5.2.4, 5.2.8 5.2.1, 5.2.7 6.3.2 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear NU REG 0654 G.1 G.2 G.3.a G.3.b G.4.a G.4.b G.4.c G.5 H.1 H.2 H.3 H.4 H.5.a H.5.b H.5.c H.5.d H.6.a June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA NMPNS STATION ANNEX SECTION Public Emergency Education/Information 6.4.1 ' 6.4.2 Public Emergency Education Program 6.4.1, 6.4.2 Media Contacts and Locations 5.1.6, 2.6.3 Media at the EOF 5.1.6 Designated Public Information Spokesperson 2.6.3.b Timely Exchange Among Spokespersons 2.6.3.b Arrangements for Rumor Control 4.9, 2.6.3.h News Media Education Program 6.1.1g NUREG 0696 TSC and OSC Requirements 5.1 .2, 5.1.3 Near Site EOF 5.1.4 State and County EOCs Appendix 5 Timely Activation/Staffing of ERFs/EOCs 2.2, Onsite Monitoring Systems -Geophysical 5.3.3.f, 5.3.3.g, 5.3.3.h. Onsite Monitoring Systems -Radiological 5.3.3.b, 5.3.3.d. Onsite Monitoring Systems -Process 5.3.3.a, 5.3.3.c. Onsite Monitoring Systems -Fire 5.3.3.e. Offsite Monitoring Systems/Equipment

-5.3.3.f, 5.3.3.g., 5.3.3.h. Geophysical App 1-4 EP-AA-1013 (Revision

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I . Nine Mile Point Annex Exelon Nuclear NU REG 0654 H.6.b H.6.c H.7 H.8 H.9 H.10 H.11 H.12 1.1 1.2 1.3.a 1.3.b 1.4 1.5 1.6 *June 2016 APPENDIX 1 . CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA Offsite Monitoring Systems/Equipment

-Radiological Sampling/Rate meters/Dosimetry Offsite Monitoring Systems/Equipment

-Laboratories Offsite Radiological Monitoring Equipment Meteorological Monitoring Instrumentation/Procedures NMPNS STATION ANNEX SECTION 5.3.3.b 5.3.2 5.3.3.b.4 5.3.3.g, 5.3.3.h Provision for the OSC 5.1.3 Inspection/Inventory/Calibration of Emergency

6.3.2 EquipmenVlnstruments

Identification of Emergency Equipment

5.8 Central

Point for Collection/Analysis of Field Data 5.3.3.b.5 Identification of Plant Condition Parameters and 3.1, 3.2, 4.5.1, 5.3.3 Corresponding Emergency Classes . Monitoring Capabilities 4.5.1, 5.3.3 Methods/Techniques for Source term Determination 4.5.1, 5.3.3 Methods/Techniques to determine Release 4.5.1, 5.3.3 Magnitude Onsite/Offsite Exposures/Contamination for Effluent 4.5.1, 4.5.2, 5.3.3.h Monitor Readings Acquisition of Meteorological Information 4.5.2, 5.2.8, 5.3.3.g, 5.3.3.h Determination of Release Rate/Projected Doses 4.5, 4.5.2, 4.5.4 given Inoperable Instrumentation App EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear NU REG 0654 1.7 1.8 1.9 1.10 1.11 J.1.a J.1.b J.1.c J.1.d J.2 J.3 J.4 J.5 J.6.a June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA Capabilities for Field Monitoring within the Plume Exposure EPZ Capability for Assessment of Actual/Potential Magnitude and Location of Radiological Hazards Capability to Detect Airborne Radioiodine Concentrations as low as 5e-08 microcuries Estimation of Integrated Doses; Comparison with PAGs Arrangements to Locate and Track the Plume Capability to warn personnel

-Employees with Emergency Assignments Capability to warn personnel

-Visitors Capability to warn personnel

-Contractor and Construction Capability to warn personnel

-Others in the Exclusion Area Offsite Sheltering/Evacuation of Onsite Personnel Radiological Monitoring of Personnel Evacuated from Site Onsite Non-essential Personnel Evacuation/Decontamination at Offsite Facility Accountability for Onsite Personnel Onsite Personnel Protection

-Respiratory App 1-6 NMPNS STATION ANNEX SECTION 4.4.1, 4.4.2, 4.4.3 4.4, 4.5, 5.2, 5.3.3.b.5 4.4.2 4.4, 4.5 Appendix 5 4.7.1.a, b, c, d,5.4.3 4.7.1.a, b, c, d, 5.4.3 4.7.1.a, b, c, d, 5.4.3 4. 7.1.c, d, 5.4.3 4.7.1.c 5.4.4 4.7.1.c, 5.4.4 4.7.1.d. 4.7.1.g EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear NU REG 0654 J.6.b J.6.c J.7 J.8 J.9 J.10.a J.10.b J.'10.c J.10.d J.10.e J.10.f J.10.g J.10.h J.10.I J.10.j J.10.k J.10.I June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA Onsite Personnel Protection

-Protective Clothing Onsite Personnel Protection

-Kl Prompt Notification of Offsite Authorities

-PARs Onsite Plan Contains Plume Exposure EPZ ETEs Protective Action Guides (Personnel Exposure and Food Stuffs) Maps -Evacuation Routes/ Areas/Pre-selected Sampling Points/Relocation Centers/Shelter Areas Maps -Population Distribution By ERPA Means for Notifying Resident and Transient Population Means to Protect Mobility Impaired Kl Distribution Kl Administration Means for Relocation Relocation to Reception centers in Host Areas Traffic Capabilities of Evacuation Routes Evacuated Area Access Control Contingencies for Impediments on Evacuation Routes ETEs for EPZ App 1-7 NMPNS STATION ANNEX SECTION 4.7.1.e 4.7.1.h 4.7.2.c 4.7.2, 4.7.2.a, EP-AA-1013, Addendum 2 Appendix 5 Appendix 5, 7 . EP-AA-1013, Addendum 2 Appendix 5, 7 4.7.2.b, Appendix 5, 7 Appendix 5 Appendix 5 Appendix 5 Appendix 5 Appendix 5 Appendix 5 Appendix 5 Appendix 5 Appendix 5, EP-AA-1013, Addendum 2 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear NU REG 0654 J.10.m J.11 J.12 K.1.a K.1.b K.1.c K.1.d K.1.e K.1.f K.1.g K.2 K.3.a K.3.b K.4 K.5.a K.5.b June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA NMPNS STATION ANNEX SECTION Basis for PARs During Emergencies 4.7.2.c, Appendix E & F Protective Measures for Ingestion Pathway Appendix E Registration and Monitoring of Evacuees Appendix E Onsite Exposure Guidelines

-Removal of Injured 4.7.1.f Persons Onsite Exposure Guidelines

-Corrective Actions 4.7.1.f Onsite Exposure Guidelines

-Performing 4.7.1.f Assessment Onsite Exposure Guidelines

-Performing First Aid 4.7.1.f Onsite Exposure Guidelines

-Performing Personnel 4.7.1.f Decontamination Onsite Exposure Guidelines

-Providing Ambulance 4.7.1.f Services Onsite Exposure Guidelines

-Providing Medical 4.7.1.f Treatment Onsite Radiation Protection Program 4.7.1.f Provide for 24 Hour/Day Dosimetry

4. 7 .1. f Provide for Reading Dosimetry 24 Hour/Day 4.7.1.f Authorizations for Personnel Exposure in Excess of Appendix E PAGs Determining Need for Decontamination 4.7.1.e, 4.8.1 Means for Decontamination of Emergency Workers 4.8.1, 5.4.4, 5.6 App 1-8 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear NU REG 0654 K.6.a K.6.b K.6.c K.7 L.1 L.2 L.3 L.4 M.1 M.2 M.3 M.4 N.1.a N.1.b N.2.a June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA Onsite Contamination Controls -Area Access NMPNS STATION ANNEX SECTION 4.7.1.e Onsite Contamination Controls -Drinking Water and 4.7.1.e Food Stuffs Onsite Contamination Controls -Criteria for return 4. 7 .1.e to normal use Capability for Decontamination of Relocated Onsite 5.4.4 Personnel Ability of Medical/Health Services to Evaluate 4.8.4, Appendix 2 Radiation Exposure/Handle Contaminated Personnel Onsite First Aid Capability

4.8.2 Identification

of Medical Services Facilities Appendix 5 Equipped/

Trained to Treat Radiological Accident Victims Transportation to Medical Facilities 4.8.3, Appendix 2 General Plans for Re-Entry/Recovery and 7.1.1, 7.2 Relaxation of PARs Designation of Facility Recovery Organization Fig. 7.1 Notification of Recovery Organization

7.3 Methodology

for Estimating Total Population Dose 4.5.4 Drill Simulating Offsite Releases 6.1.2 Exercise Tests all Elements, Times, & Weather 6.1.2 Conditions, Some Unannounced Communications Drills 6.1.2 App 1-9 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear NU REG 0654 N.2.b N.2.c N.2.d N.2.e.1 N.3.a N.3.b N.3.c N.3.d N.3.e N.3.f N.4 N.5 0.1.a 0.1.b June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA Fire Drills Medical Emergency Drills Radiological.

Monitoring Drills Health Physics Drills -Response/Analysis of Airborne & Liquid Samples/ Direct Radiation Readings in the Environment Drill Scenarios

-Objectives/Evaluations Drill Scenarios

-Date/Time/Place/Participants*

Drill Scenarios

-Simulated Events Drill Scenarios

-Time Schedule Drill Scenarios

-Narrative Summary Drill Scenarios

-Arrangements for Official Observations Officlal Observers Critique Exercises with Formal Evaluation Improvements and Corrective Actions based upon comments received Training

-Site Specific Training for Offsite Organizations Training Requirements

-Offsite Agencies Fire/Police/

Ambulance/Rescue

• App 1-10 NMPNS STATION ANNEX SECTION 6.1.2 6.1.2 6.1.2 6.1.2 6.1.2 6.1.2 6.1.2 6.1.2 6.1.2 6.1.2 6.1.2 6.1.2 6.1.1 6.1.1 , Appendix 5 EP-AA-1013 (Revision

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Nine Mile Point Annex Exelon Nuclear NU REG 0654 0.2 0.3 0.4.a 0.4.b 0.4.c 0.4.d 0.4.e 0.4.f 0.4.g 0.4.h 0.4.i 0.4.j 0.5 June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA NMPNS STATION ANNEX SECTION Onsite ERO Training/Practicals/Drills with on the 6.1.2 spot correction Onsite First Aid Training*

Fig. 6.2 Initial and Continuing Training Requirements

-Fig. 6.2 Directors/Coordinators Initial and Continuing Training Requirements

-Fig. 6.2 Accident Assessment Personnel Initial and Continuing Training Requirements

-Fig. 6.2 Radiological Monitoring and Analysis Teams Initial and Continuing Training Requirements

-6.1.1, Fig. 6.2 Police, Security, Fire Fighters Initial and Continuing Training Requirements

-Fig. 6.2 Damage and Repair Teams Initial and Continuing Training Requirements

-First Fig. 6.2 Aid and Rescue Personnel Initial and Continuing Training Requirements

-Local 6.1.1, Fig. 6.2 Support Services Personnel Initial and Continuing Training Requirements

-6.1.1, Fig. 6.2 Medical Support Personnel Initial and Continuing Training Requirements

-Fig. 6.2 Licensee Headquarters Personnel Initial and Continuing Training Requirements

-Fig. 6.2 Communicators Initial and Continuing Training Requirements

-ERO Fig. 6.2 App 1-11 EP-AA-1013 (Revision

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'.,._)-' Nine Mile Point Annex Exelon Nuclear NU REG 0654 P.1 P.2 P.3 P.4 P.5 P.6 P.7 P.8 P.9 P.10 June 2016 APPENDIX 1 CROSS-REFERENCE INDEX BETWEEN NMPNS EMERGENCY PLAN AND NUREG-0654/FEMA-REP-1 REV 1 CRITERIA EP Department Personnel Training EP Director Authority Requirement EP Director Responsibility Requirement Annual Recertification of Plan and Procedures Procedures for Plan and Procedure Revision/

Distribution Listing of Supporting Plans Requirement for List of Implementing Procedures Requirement for SEP Table of Contents, NU REG 0654 Cross Reference

• NMPNS STATION ANNEX SECTION 6.1.1, 1.1.h 6.1.3, Fig. 6.1 6.1.3 6.2.3 6.2, 6.2.3 Appendix 5 Appendix 3 Table of Contents, Appendix 1 Requirement for Independent Audit of EP Program 6.2.1 Requirement to Update Telephone Numbers 6.2.2 Quarterly App 1-12 1013 (Revision 2).

Nine Mile Point Annex Exelon Nuclear APPENDIX 2 LETTERS OF AGREEMENT The up-to-date Letters of Agreement are maintained under separate cover in the Emergency Preparedness Group's file but are considered to be incorporated as part of this document by reference.

Current Letters of Agreement In regards to exist between NMPNS and: 1) EA Engineering, Science, and Provides technical assistance Technology

2) James A. Fitzpatrick Nuclear Each provides personnel, equipment, and facilities as R. E. Ginna Nuclear Plant required.

JAF provides for siren mechanical maintenance, and laboratory services 3) General Electric Provide assistance per SIL #324 4) INPO Provide information on the availability of personnel and equipment able to assist 5) New York State Provide assistance as per the New York State Radiological Emergency Preparedness Plan 6) Derek R. Cooney, MD, Provide emergency medical care FF/NREMT-P.

FACEP 7) County of Oswego a) Oswego County Provide assistance as per the Oswego County Emergency Management Radiological Emergency Preparedness Plan Office b) Oswego County 911 Provides 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 7 day a week contact point for local Center fire and ambulance service. c) Oswego County Sheriff's Provides for support from all local law enforcement Department agencies.

8) Oswego Hospital Provide medical care of radioactivity contaminated patients June 2016 App 2-1 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX2 LETTERS OF AGREEMENT The up-to-date Letters of Agreement are maintained under separate cover in the Emergency Preparedness Group's file but are considered to be incorporated as part of this document by reference.

Current Letters of Agreement In regards to exist between NMPNS and: 9) State University of New York, . Provide emergency medical care for radioactively University Hospital contaminated patients 10) Department of Energy Provide radiological assistance Provide emergency medical assistance (REACffS)

11) Oswego County Airport Provide support for the following via service level agreement:

• Use of Hanger K for Alternate and Alternative facilities for NMPNS 12) Dr. Padma Ram, MD Provide emergency medical care 13) Local transportation providers Provide for fixed wing and helicopter ai.r service and ground transport equipment/service June 2016 App 2-2 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear Number EP-CE-113 EP-AA-112-500-F-55 EP-CE-111 EP-CE-113 APPENDIX 3 Emergency Plan Implementing Procedures Title Personnel Protective Actions Methods used to conduct evacuations including protected area, exclusion area and accountability for those remaining in the protected area. NMP Offsite Monitoring Team Guidance Responsibilities and actions for performing onsite and offsite emergency and environmental surveys. Emergency Classification and Protective Action Recommendations Criteria to classify emergencies.

Personnel Protective Actions Actions to provide radiological controls for emergency exposure, use of Kl and emergency respiratory protection EP-CE-114-

• Emergency Notifications 100 Instructions for prompt notification to offsite authorities, emergency response agencies and selected NMP personnel.

EP-AA-112-

• Public Information Organization 600 EP-AA-112-400 EP-AA-112-100 EP-AA-112-200 EP-AA-112-300 EP-CE-115 June 2016 . Guidance for dissemination of emergency information Emergency Operations Facility Activation and Operations Emergency responsibilities and duties of the EOF ERO members. Control Room Operations Responsibilities and duties of on-shift ERO in the event of Emergency Plan activation.

Technical Support Center Activation and Operations Emergency responsibilities and duties of the TSC ERO .members.

Operations Support Center Activation and Operations Emergency responsibilities and duties of the OSC ERO members. Termination and Recovery Transition into and conduct of operations during termination phase of a classified event. App 3-0 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear Number EP-AA-110-204 EPIP-EPP-01-EAL EPIP-EPP-02-EAL EPIP-EPP-09 OP-NM-106-APPENDIX3 Emergency Plan Implementing Procedures Title NMP Dose Assessment Method to perform dose assessment and projections Emergency Action Level Matrix Unit 1 Emergency Action Level Matrix Unit 2 Multi-colored matrices used to evaluate initiating conditions for entry into an emergency classification.

Determination of Core Damage Under Accident Conditions Method to determine the degree of reactor core damage utilizing sampling and calculations based on core inventory.

Security Contingency Actions 104 Process to establish and maintain interface during Security Contingency Events. EPIP-EPP-21 Radiation Emergencies EP-AA-1013, Addendum 3 EP-AA-1013, Addendum 4 June 2016 Handling radiation emergencies with consequences limited to the Nine Mile Point Site. Unit 1 Emergency Action Levels for Nine Mile Point Station Unit 2 Emergency Action Levels for Nine Mile Point Station Explanation and rationale for each Emergency Action Level (EAL). App 3-1 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Responsibilities Note: The positions and responsibilities described in this Appendix apply to Nine Mile Point station and supersede the list of ERO positions and respective ERO responsibilities identified in the Exelon Standard Plan. 1.0 ON-SHIFT STAFF POSITIONAL RESPONSIBILITIES

1.1 Shift

Emergency Director I Shift Manager: NOTE:

• Indicates Non-Delegable responsibilities when performing Emergency Director duties.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Perform or direct emergency PA announcements.

• Ensure flow of information within and between the emergency response facilities.

• Integrate ERO activities with the Incident Command Post (ICP) response activities.

• Assume overall command and control of emergency response.

• Classify and declare emergencies.*

• Direct notification and activation of the ERO.

• Direct and approve offsite emergency notifications to state and local authorities*.

• Direct ENS communications with the NRC.

• Oversee the performance and evaluate the results of dose projection activities.

• Ensure appropriate accountability and search and rescue actions for plant personnel.

• Ensure appropriate evacuation actions for plant personnel*.

• Approve the issuance of Kl.

• Make Protective Action Recommendations to offsite authorities*.

• Approve emergency exposures.*

• Terminate the emergency event. 1 .2 Shift Manager (After Transfer of Command and Control)

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Perform or direct emergency PA announcements.

• Ensure flow of information within and between the emergency response facilities.

• Participate in Inter-Facility Briefings to communicate and obtain event and response information.

• Authorize and prioritize requests for external assistance (police, fire, medical) as necessary.

• Assist with Emergency Classification.

June 2016 App 4-1 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 4 Emergency Response Organization Responsibilities

1.3 Shift

Technical Advisor (STA), SROs and ROs

• Assist with emergency classification.

1 .4 Designated Shift Communicator

• Notify the ERO.

• Perform offsite emergency notifications to state and local authorities.

• . Provide plant data and plant information to the NRC via the ENS. 1 .5 Designated Shift Dose Assessor

• Perform dose assessments.

1.6 Shift

Radiation Protection Technician(s)

• Ensure habitability is established and maintained for occupied onsite areas.

• Monitor in-plant radiological conditions.

• Coordinate RP support for personnel dispatched into the plant. 1.7 . Shift Chemistry Technician

• Conduct sampling to assist with emergency assessment activities.

1 .8 Security Shift Supervisor

• *Supervise security force activities.

• Perform offsite emergency notifications to state and local authorities.

• Establish and maintain Protected Area accountability.

• Establish and supervise plant access controls.

• Supervise security actions for site evacuation.

• Coordinate administration of Kl to the security officers.

1.9 Other

Shift Personnel (Non-licensed Operators, Security Force, Maintenance Personnel)

• Support emergency response as directed.

2.0 TECHNICAL

SUPPORT CENTER (TSC) 2.1 Station Emergency Director

• Manage all onsite emergency activities in support of plant operations.

• Establish plant/station response priorities.

• Integrate ERO activities with the Incident Command Post (ICP) response activities.

• Authorize and prioritize requests for external assistance (onsite technical support, manpower) as necessary.

• Assist with emergency classification.

• June 2016 App 4-2 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 4 Emergency Response Organization Responsibilities

• Provide informational updates and recommendations to the ED, regarding plant status and activities.

• Direct ENS communications with the NRC.

• Authorize emergency response facility relocations.

• Evaluate event assessments and mitigative strategies to determine operational and response actions.

• Authorize and direct extreme measures (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Ensure appropriate accountability and search and rescue actions for plant personnel.

• Ensure accountability, once established, is maintained in all occupied areas of the station.

• Ensure appropriate evacuation actions for plant personnel.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility briefing to communicate and obtain event and response information.

• Coordinate integration of the NRC Site Team

• Assist in the development of recovery plans. 2.2 TSC Director

• Activate the Facility.

• Establish and maintain facility accountability.

• Manage the operation of the facility.

• Review and ensure facility displays are maintained current.

• Coordinate ERO shift relief rosters for the onsite facilities.

• Develop ERO shift relief rosters for the facility.

• Perform or direct emergency PA announcements.

• Coordinate integration of the NRC Site Team.

• Arrange for logistics support. .

• Ensure flow of information within and between the emergency response facilities.

• Provide input for facility briefs and updates.

• Coordinate TSC relocation.

2.3 Technical

Manager

• Manage the activities of the TSC engineering I technical staff.

• Ensure additional personnel and/or equipment is arranged for, as necessary.

• Provide engineering support for accident detection and assessment.

• Develop mitigative strategies based on assessment of the event. June 2016 App 4-3 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 4 Emergency Response Organization Responsibilities

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Provide input for facility briefs and updates. 2.4 Electrical Engineer

• Provide engineering support for accident detection and assessment.

• Provide input into mitigative strategies.

-* Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

2.5 Mechanical

Engineer

• Provide engineering support for accident detection and assessment.

• Provide input into mitigative strategies.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• 2.6 Core/Thermal Hydraulic Engineer

• Provide engineering support for accident detection and assessment.

• Provide input into mitigative strategies.

• Perform core damage estimations.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

2.7 Technical

Staff

• Provide input for mitigative strategies

• Support the setup of systems and equipment within the facility.

2.8 TSC/OSC Computer Specialist

• Support the setup of systems and equipment within the facility.

• Monitor facility equipment (computer related and communications) to ensure adequate operation.

• Resolve any IT related malfunctions.

2.9 TSC Operations Manager

• Manage the activities of the TSC Operations staff.

• Assist with emergency classification.

• Provide technical assistance communication path to the Shift Manager.

• Support the establishment of plant/station response priorities.

• Provide operations support for accident detection and assessment.

June 2016 App 4-4 . EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 4 Emergency Response Organization Responsibilities

• Recommend operations actions to the Shift Manager in support of restoration and accident mitigation.

• Analyze and develop extreme measures actions (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Coordinate between CR, OSC and TSC to set osc*team task priorities.

• Coordinate operations activities outside of the Control Room between the Shift Manager and OSC.

• Provide input for facility briefs and updates. 2.1 O ENS Communicator

• Provide event data and plant information to the NRC via the ENS.

• Verify Emergency Response Data System (EROS) operation.

• Monitor assigned communication line and provide key information to facility staff.

• Monitor event information on the facility display systems. 2.11 TSC Operations -Communicator

• Communicate key information between the facilities over the Technical Information Line.

• Monitor assigned communication line and provide key information to facility staff.

• Display, monitor and trend plant data and event information on the facility display systems. 2.12 CR Operations Communicator

• Communicate key information between the facilities over the Technical Information Line.

• Monitor assigned communication line and provide key information to facility staff. 2.13 Maintenance Manager

• Provide input into mitigative strategies.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Coordinate repair and OSC team task information between the and osc.

• Provide input for facility briefs and updates. 2.14 TSC Radiation Protection Manager * . Manage and direct the radiological activities of the RP personnel.

• Ensure additional personnel and/or equipment is arranged for, as necessary.

• Provide radiological support for accident detection and assessment.

June 2016 App 4-5 EP-AA-1013 (Revision.2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Responsibilities

• Monitor, evaluate and communicate conditions involving any release of radioactivity.

• Provide support and logistics for site evacuation activities.

• Evaluate the need for and ensure proper use of Kl.

• Ensure habitability is established and maintained for occupied onsite areas.

• Ensure proper emergency exposure controls are taken for personnel.

• Provide radiological assistance for planni11g rescue operations and repair team monitoring.

• Direct personnel decontamination activities.

• Provide radiological assistance for the transfer of injured and/or contaminated personnel.

• Provide input for facility briefs and updates. 2.15 Security Coordinator

• Integrate ERO activities with the ICP response activities.

• Manage the activities of the site security force.

• Request and coordinate emergency activities with Local Law Enforcement Agencies (LLEAs).

• Provide security related communications with the NRC.

• Direct accountability and search & rescue activities.

• Direct site evacuation activities.

• Direct site access controls activities.

• Coordinate security activities between the SSS and OSC.

• Determine radiation protection measures for security force personnel and law enforcement agency personnel on site.

• Provide input for facility briefs and updates. 2.16 TSC Administrative Staff

• Perform administrative and logistic support functions for facility personnel.

• Establish and maintain facility accountability.

NOTE: NMP TSC EIS Operator duties may be performed by the TSC/OSC Computer specialist.

• 2.17 TSC EIS Operator

• Collect and input data and maintain EIS displays.

June 2016 App 4-6 EP-AA: 1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 4 Emergency Response Organization Responsibilities

3.0 Operations

Support Center (OSC): 3.1 OSC Director

• Activate the Facility.

• Manage the operation of the facility.

• Develop ERO shift relief rosters for the facility.

• Ensure flow of information within and between the emergency response facilities.

• Support the establishment of plant I station response priorities.

• Direct accountability and search & rescue activities.

• Establish and maintain facility accountability.

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Coordinate OSC team dispatch and control.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility Briefing to communicate and obtain event and response information.

3.2 Assistant

OSC Director

• Coordinate between CR, OSC and TSC to set OSC team task priorities.

• Participate with OSC team dispatch and control.

• Assemble and dispatch OSC and offsite monitoring teams.

• Provide input for facility briefs and updates. 3.3 OSC Group, Chemistry and Operations Leads

• Manage OSC manpower needs.

• Assist with formation of OSC teams.

• Participate with OSC team dispatch*and control.

• Provide technical support to dispatched OSC teams. 3.4 OSC Group, Chemistry and Operations Personnel

• Perform job duties as an OSC team member. 3.5 OSC Radiation Protection (RP) Lead

• Manage OSC manpower needs.

• Brief and dispatch the onsite/offsite radiation monitoring teams.

• Monitor in-plant radiological conditions.

• Ensure habitability is established and maintained for occupied onsite areas.

• Participate with OSC team dispatch and control.

• Coordinate RP support for OSC teams.

• Track OSC Team emergency exposure.

June 2016 App 4-7 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Responsibilities

• Implement appropriate protective measu.res for OSC personnel.

• Establish OSC and plant access radiological controls.

• Provide input for facility briefs and updates. 3.6 OSC Radiation Protection Technicians(s)

• Perform habitability monitoring in occupied areas.

• Perform job duties as an OSC team member. 3.7 OSC Team Tracker * . Maintain Team Tracking Status display.

• Participate with OSC team dispatch, control and tracking.

• Track and maintain communications with OSC teams. 3.8 OSC Operations Communicator

• Communicate key information between the facilities over the Technical Information Line. * *

• Monitor the Technical Information Line and announce key information to facility staff.

• Display, monitor and trend plant data and event information on the facility display systems. 3.9 OSC Administrative Staff

• Perform administrative and logistic support functions for facility personnel.

NOTE: EIS tasks may be performed by the Ops Communicator

-OSC . . 3.1 O OSC EIS Operator

• Collect and input data and maintain EIS displays.

4.0 Emergency

Operations Facility -Offsite ERO 4.1 Emergency Director NOTE:

• Indicates Non-Delegable res.ponsibilities when performing Emergency Director duties.

• Assume overall commahd and control of en:iergency response.

• Ensure all EXELON emergency response facilities are properly staffed and activat_ed

..

• Classify emergencies.*

• Direct and approve offsite emergency notifications to state and local authorities.*

June 2016 App 4-8 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Responsibilities

• Make Protective Action Recommendations to off site authorities.*

• Direct ENS communications with the NRC.

• Ensure appropriate evacuation actions for plant personnel.*

• Approve the issuance of Kl.

• Approve emergency exposures.*

• Integrate ERO activities with the Incident Command Post (ICP) response activities.

• Authorize and prioritize requests for external assistance (governmental) as necessary.

• Authorize and prioritize requests for external assistance (offsite technical support, manpower) as necessary.

• Ensure other organization's management/decision makers (NRC, State; EXELON, etc.) are kept informed of the emergency situation.

• Ensure flow of information within and between the emergency response facilities.

• Approve technical content of media statements.

• Coordinate integration of. the NRC site team. .

• Authorize and direct extreme measures (SAMGs, EDMGs, §50.54(x) or suspend security controls).

• Terminate the emergency event.

• Establish a recovery plan and organization.

• Conduct facility briefs and updates.

• Conduct an Inter-Facility briefings to communicate and obtain event and response information.

4.2 EOF Director

• Activate the Facility.

• Manage the operation of the facility.

• Assist offsite agency personnel responding to the facility.

• Coordinate integration of the NRC site team.

• Assist with emergency classification.

• Support the completion of timely offsite event notifications to State and local authorities.

• Evaluate conditions and determine recommendations for PARs.

• Assist in the development of recovery plans.

• Participate in the Inter-Facility briefing to communicate and obtain event and response information.

• Provide input for facility briefs and updates. June 2016 App 4-9 EP-AA-1013

.<Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 4 Emergency Response Organization Responsibilities 4.3 EOF Technical Advisor

• Assist with emergency classification.

• Monitor plant status and Control Room activities.

• Provide input for facility briefs and updates. 4.4 EOF Operations Communicator

• Communicate key information between the facilities over the Technical Information Line.

• Monitor assigned communication line and provide key information to facility staff.

• Display, monitor and trend plant data and event information on the facility display systems. 4.5 EOF Logistics Manager

• Ensure ERO personnel have been properly notified and are responding to the . facilities.

• Oversee staffing of EOF and assist with staffing for other facilities.

• Develop ERO shift relief rosters for the facility.

• Coordinate ERO shift relief rosters for all facilities and the notification of personnel.

• Manage the administrative support staff.

• Review and ensure facility displays are maintained current.

• Manage the procurement and logistical support activities for the onsite and offsite emergency response personnel and facilities . .

• Monitor and maintain access controls for the facility.

• Communicate with and coordinate support for ERO responders or plant personnel sent offsite to relocation areas.

• Provide input for facility briefs and updates 4.6 EOF/JIC Computer Specialist .

• Support the setup of systems and equipment within the facility.

• Monitor facility equipment (computer related and communications) to ensure adequate operation.

• Resolve any IT related malfun.ctions.

• Assist in operation of JIC audio visual equipment.

• Perform the duties of EOF EIS Operator.

4. 7 EOF Administrative Staff

• Callout ERO relief shift.

• Set up EOF equipment in preparation for facility activation.

• Perform administrative and logistic support functions for facility personnel.

June 2016 App 4-10 EPWAA-1013 (Revision

.2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Responsibilities 4.8 EOC Communicator

• Monitor plant conditions and event response activities.

• . Provide information updates to and address questions and support requests from the offsite liaisons.

• Notify and brief external agencies and groups (INPO, ANI) of the emergency event.

• Provide input for facility briefs and updates. 4.9 State Liaison

• Communicate EOC I ICP actions and decisions to the EOF.

• Provide technical support and information to the EOC I ICP. 4.10 County Liaison(s)

• Communicate EOC I ICP actions and decisions to the EOF.

• Provide technical support and information to the EOC I ICP. 4.11 EOF Radiation Protection Manager

• Manage and direct the radiological activities of .the Off site RP personnel.

• Coordinate activities with the external agency field monitoring teams.

• Coordinate the comparison and exchange of dose assessment results with offsite agency personnel.

• Assist with emergency classification.

• Monitor, evaluate and communicate conditions involving any release of radioactivity.

• Oversee the performance and evaluate the results of dose projection activities.

• Perform dose assessment.

• Oversee the performance and evaluate the results of Offsite Monitoring Team (OMT) activities.

• Provide support and logistics for site evacuation activities.

• Evaluate the need for and ensure proper use of Kl.

• Evaluate conditions and determine recommendations for PARs.

• Ensure proper emergency exposure controls are taken for personnel.

• Provide assistance to state and federal agencies for ingestion pathway radiological activities.

• Provide input for facility briefs and updates. 4.12 HPN Communicator

• Provide event data and plant information to the NRC via the HPN.

• Monitor assigned communication line and provide key information to facility staff. June 2016 App 4-11 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Resp'onsibilities 4.13 Dose Assessor

• Monitor, evaluate and communicate conditions involving any release of radioactivity.

• Perform dose assessment.

• Evaluate conditions and determine recommendations for PARs. 4.14 Environmental Coordinator

• Direct and track Offsite Monitoring Team activities.

• Coordinate activities with the external agency field monitoring teams.

• Establish and maintain OMT communications.

• Maintain and update the radiological status displays.

• Coordinate the receipt, analysis, storage and transfer of field monitoring samples.

• Record and report field monitoring survey, sample and exposure information.

4.15 Offsite Monitoring Teams

• Establish and maintain OMT communications.

• Perform equipment checks inventories in preparation of deployment.

• Track radiological plumes.

• Perform and report results of radiation surveys and environmental sampling.

• Coordinate the receipt, analysis, storage and transfer of field monitoring samples.

• Communicate exposure status to the Environmental Coordinator.

1) State/Local Communicator

• Perform off site emergency notifications to state and local authorities.

• 2) EIS Operator

• Collect and input data and maintain EIS displays.

5.0 Public

Information ERO (JIC Staff) 5.1 JIC Manager

• Activate the Facility.

• Manage the operation of the facility. ,

• Assist offsite agency personnel responding to the facility.

• Coordinate integration of the NRC Site Team.

• Provide liaison to the NRC Site Team.

• Arrange for support for Emergency Alert System (EAS) information.

June 2016 App 4-12 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Responsibilities

• Ensure. flow of information within and between the emergency response facilities.

• Interface with offsite agency Public Information Officers (PIOs) to coordinate overall information flow to the media and public.

• Coordinate facilitation of the media briefing schedule.

• Ensure news media briefings are held regularly during the course of the emergency.

• Oversee conduct of media briefings.

• Integrate ERO activities with the Incident Command Post (ICP) response activities

• Assist in the development of recovery plans.

• Conduct facility briefs and updates.

• Participate in the Inter-Facility Briefing to communicate and obtain event and response information.

5.2 Company

Spokesperson

• Establish periodic contact with the communications personnel in the corporate office.

• Interface with offsite agency PIOs to coordinate overall information flow to the. media and public.

• Provide interviews.

to the media.

• Serve as Company Spokesperson during press conferences at the JIC.

• Participate in the Inter-Facility Briefing to communicate and obtain event and response information.

• Provide input for facility briefs and updates. 5.3 EOF Logistics Manager

• Manage the administrative support staff.

• Develop ERO shift relief rosters for the facility.

• Arrange for logistics support.

• Oversee set-up and testing of JIC equipment.

• Maintain access control to the JIC.

• Provide input for facility briefs and updates.

• Oversee collection of technical data and station activities for drafting Media Statements and answering JIC questions.

• Coordinate preparation, review and distribution of Media Statements.

• Obtain ED approval for the technical content of Media Statements.

• Keep JIC staff informed of plant status and EXELON emergency response activities.

June 2016 App 4-13 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Responsibilities 5.4 News Writer

• Prepare draft Media Statements.

• Develop public information materials (bulletins, backgrounders and chronologies).

5.5 JIC Technical Advisor

• Provide technical expertise to the JIC staff.

• Assist the News Writer with development of technically accurate media statements.

• Provide answers to technical questions from the news media regarding the emergency situation.

• Periodically monitor EOF!fSC briefings and Technical Information Line to obtain information.

• Provide technical information, support to the Company Spokesperson.

-* Monitor event information on the facility display systems.

• Provide inputfor facility briefs and updates: 5.6 Media Liaison

• Ensures media is informed of protocol and schedules established for media briefings. .

• Coordinate preparations for media briefings.

• Distribute media statements to the-media in the media briefing area.

• Coordinate media relations in JIC and update media betvyeen press conferences.

• Coordinate special interviews and facility tours for the media.

• Coordinate JIC briefing area preparation and establish briefing protocol.

5.7 JIC Administrative Staff

• Assist in badging and direction of members of the media to proper work locations.

• Perform administrative and logistic support functions for facility personnel.

• Distribute media materials to the press. 5.8 Media Monitoring I Rumor Control Coordinator

• Supervise media monitoring and Inquiry Phone Team personnel.

• Review Media Monitoring team information for trends, misinformation and rumors.

• Review Phone Team information for trends, misinformation and rumors.

• Ensure adequate staff is available to perform media monitoring and phone team functions.

• Provide input for facility briefs and updates. June 2016 App 4-14 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX4 Emergency Response Organization Responsibilities

5.9 Inquiry

Phone Team

• Respond to and log phone inquiries from the media and the public.

• Monitor telephone lines for trends, misinformation and rumors. 5.10 Media Monitoring Team

• Monitor media coverage of the event for trends 5.11 JIG Security

• Provide badging and access controls for the facility.

5.12 JIG EIS Operator

• Collect and input data and maintain EIS displays.

6.0 In addition to the position specific responsibilities listed above all ERO members have the following general responsibilities:

• Perform position turnover for protracted events

• Respond as directed when notified of a* declared event

• Maintain personal event logs and records in support of the after action report

• Restore area and materials upon event termination

• Apply fundamental ERO knowledge in the performance of your ERO duties

• Properly use ERO procedures and checklists in the performance of your ERO duties

• Acquire & maintain qualification in your assigned ERO position

• Apply human performance error reduction techniques in the performance of you ERO duties June 2016 App 4-15 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 5 OSWEGO COUNTY RADIOLOGICAL EMERGENCY PREPAREDNESS PLAN NEW YORK STATE RADIOLOGICAL EMERGENCY PREPAREDNESS PLAN The Oswego County Radiological Emergency Preparedness Plan and the New York State Radiological Emergency Preparedness Plan are submitted under separate cover but are considered to be incorporated as part of this document by reference.

Locations of maps to relocation centers in host areas as required by NU REG 0654 11.J.1 Oa are contained within the Host County Plan and is included by reference to the Oswego County Radiological Emergency Preparedness Plan. June 2016 App 5-1 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 6 TYPICAL ADDITIONAL SUPPORT RESOURCES

1. AIRFIELDS

a. Greater Rochester International 1200 Brooks Avenue Rochester, NY 14624 Tel. (585) 753-7020 b. Oswego County Airport 40 Airport Dr. Fulton, NY 13069 Tel. (315) 591-9130, (315) 591-9132 c. Griffiss International Airport 592 Hangar Rd Rome, NY 13342 Tel. (315) 736-4171 -Airport Manager d. Syracuse Hancock International Airport Hancock Field Syracuse, NY 13212 Tel. (315) 374-4629 Director of Operations, Operations Department (315) 374-4403, 4405 (315) 455-6218 (Air Traffic Control) \ e. Watertown International Airport 22529 Airport Dr. Dexter, NY 13634 Tel. (315) 639-3809 2 COMMAND POSTS a. NMPNS Emergency Operations Facility County Route 176 & Airport Rd. R.D.#2 Box 656 Fulton, NY 13069 June 2016 App 6-1 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear . APPENDIX 6 TYPICAL ADDITIONAL SUPPORT RESOURCES

2. COMMAND POSTS (Cont.). b. NMPNS Technical Support Center NMPNS Lake Road P.O. Box 63 Lycoming, NY -13093 Tel. (315) 349-2487

• c. Joint Information Center Oswego County Airport County Route 176 Volney, NY 13069 Tel. (315) 592-3700 d. New York State Emergency Operations Center Emergency Management Office Public Security Building, State Campus Albany, NY 12232 Tel. (518) 457-9997 e. Oswego County Emergency Operations Center 200 North Second Street *

• Fulton, NY 13069 Tel. (315) 591-9150 3. TELEPHONE SYSTEMS IN 10-MILE EPZ a. Windstream 108 S. 2nd St. Fulton, NY 13069 (800) 800-6609, (315) 592-8246 Verizon June 2016 1095 Avenue of the Americas New York, NY 10036 (800) 579-8702, (800) 890-6611 (Repair No.) App 6-2 EP-AA-1013 (Revision

2)

Nine Mile Point Annex Exelon Nuclear APPENDIX 6 TYPICAL ADDITIONAL SUPPORT RESOURCES

4. NINE MILE POINT UHF RADIO SYSTEM a. Base, mobile, and portable transceivers

b. In plant and off-site repeaters June 2016 App 6-3 EP-AA-1013 (Revision

2) c.... c: ::J CD I\) 0 ...... O'l )> "O "O -...J I ...... m "'U I ...... 0 ...... (,,) -JJ CD < (ii" O" ::J I\) .-ToJIC Conference

! Conference Loading Dock gi Env1roomemal Stoiage Dose Assessment and Downwind Survey Team Room --County/State/FE MA Room I Room"""""" ;;t O> 3 !!.' 0 iil co .. NMP Alternate OSC AdminArea NMP Plant Assessment Room EOFCore NRC Room Command/ Technical Area I L Comm Room Fax/Copy Room Storage B JAF Plant Assessment Room Lobby @hi1te1µ,y EOF and Alternate TSC/OSC .=Exelon.

Office A I Storage C Tel corn Network J ,,t;, Break Room NMP Storage Office B I Storage I Monitoring A Decon Main Entry Aux Entrance NMP Alternate TSC m s: m JJ G) ........ m -IZ '< ()

() PJ 0 JAF Alternate TSC )> "'U ...... m ...... JJ § )> (.Cl -I CD -30 CD z :J CJ) ...+ -"'Tl )> JAF Alternate OSC () r -I -< > "tJ "tJ m z c >< .....i ::0 m en 0 c: ::0 0 m s: > -4 m ::0 > r z ::::J C'D s: Ci)' "tJ 0 ::::J -> ::::J ::::J C'D >< m >< C'D 0 ::::J z c n Ci)' D> ""Ii Nine Mile Point Annex Exelon Nuclear APPENDIX 7 -RESOURCE MATERIAL OPERATIONS SUPPORT CENTER (Typical Arrangement)

...--Unit 1 RP .Acces Rad Protection Staglng Area Unit 1 Admin. Bldg. Lobby TSC Reference Library June 2016 Unit 1 Storeroom (261 ') Maintenance Shops LJ ' Rest Rooms First Aid Room Main osc Entrance Contractor Staging Area (24S') Truck Bay (261' Electrical Shop Men's Locker Room Women's Locker Room OPERATIONS SUPPORT CENTER TYPICAL ARRANGEMENT UNIT 1 ADMINISTRATION BUILDING EL, 261' STATUS BOARDS JOINT INFORMATION CENTER (Typical Arrangement)

App 7-2 KEY [§] Gaitronics

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Nine Mile Point Annex Section(s)/Step Number 3.2.1 , 4.1.3 5.2 , 5.4 , 7.1.4 5.2.2 June 2016 Exelon Nuclear Appendix 8 Emergency Plan Commitments NCTS Number NCTS #503441-02 NCTS #504223-26 App 8-1 Description Revise SEP and procedures to more clearly follow the intent of the NRC rule. Delete Sympathetic Alert. Identify the control room staffing requirements during Modes 1 , 2 , 3 and when the emergency plan is activated EP-AA-1013 (Revision 2)